ANSI N14.33-2005 Storage and Transport of Damaged Spent Nuclear Fuel《受损核废燃料的储存和运输》.pdf

1、 vANSI N14.33-2005 American National Standard Characterizing Damaged Spent Nuclear Fuel For The Purpose of Storage and Transport Copyright American National Standards Institute Provided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-v

2、iANSI N14.33-2005 American National Standard Characterizing Damaged Spent Nuclear Fuel For The Purpose of Storage and Transport Secretariat Institute for Nuclear Materials Management September 29, 2005 American National Standards Institute, Inc. Copyright American National Standards Institute Provid

3、ed by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-viiCopyright American National Standards Institute Provided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-viiiAMERICA

4、N NATIONAL STANDARD Approval of an American National Standard requires verification by ANSI that the requirements for due process, consensus, and other criteria for approval have been met by the standards developer. Consensus is established when, in the judgment of the ANSI Board of Standards Review

5、, substantial agreement has been reached by directly and materially affected interests. Substantial agreement means much more than a simple majority, but not necessarily unanimity. Consensus requires that all views and objections be considered, and that a concerted effort be made toward their resolu

6、tion. The use of American National Standards is completely voluntary; their existence does not in any respect preclude anyone, whether he has approved the standards or not, from manufacturing, marketing, purchasing, or using products, processes, or procedures not conforming to the standards. The Ame

7、rican National Standards Institute does not develop standards and will in no circumstances give an interpretation of any American National Standard. Moreover, no person shall have the right or authority to issue an interpretation of an American National Standard in the name of the American National

8、Standards Institute. Requests for interpretations should be addressed to the secretariat or sponsor whose name appears on the title page of this standard. CAUTION NOTICE: This American National Standard may be revised or withdrawn at any time. The procedures of the American National Standards Instit

9、ute require that action be taken periodically to reaffirm, revise, or withdraw this standard. Purchasers of American National Standards may receive current information on all standards by calling or writing the American National Standards Institute. Copyright American National Standards Institute Pr

10、ovided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-ixCopyright American National Standards Institute Provided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-vCONTENT

11、S Page FOREWORD vii 1. SCOPE . 1 2. DEFINITIONS 1 3. APPLICATION . 2 4. RULES AND GUIDANCE FOR DRY STORAGE AND TRANSPORT . 2 5. PROCEDURES FOR USE OF THIS STANDARD . 4 6. IDENTIFICATION AND CLASSIFICATION OF CLADDING OR MECHANICALLY DAMAGED FUEL 5 7. CANNING OF DAMAGED FUEL FOR DRY STORAGE OR TRANSP

12、ORT . 8 8. DRAINING, DRYING AND BACK-FILLING . 9 9. REQUIREMENTS FOR STORAGE AND TRANSPORT OF CLADDING DAMAGE, LEVEL II FUEL 9 10. RECORDS . 9 11. QUALITY ASSURANCE 9 APPENDIX A. DAMAGED FUEL CHART 10 Copyright American National Standards Institute Provided by IHS under license with ANSINot for Resa

13、leNo reproduction or networking permitted without license from IHS-,-,-viiCopyright American National Standards Institute Provided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-viiFOREWORD The accredited Standards Committee on Packag

14、ing and Transportation of Radioactive and Non-Nuclear Hazardous Materials, N14, under whose jurisdiction this standard was developed, has the following scope: Standards for the packaging and transportation of fissile and radioactive materials, non-nuclear hazardous materials including waste and mixe

15、d materials, but not including movement or handling during processing and manufacturing operations. This standard, ANSI N14.33, describes good engineering practice for activities that involve storage and transport of damaged spent nuclear fuel. The standard was developed to assist users in dealing w

16、ith damaged spent nuclear fuel in a safe manner, and is intended to comply with the requirements, guidance, and practices established by the U.S. Nuclear Regulatory Commission. Some aspects of the treatment of spent nuclear fuel in storage and transport relate to the radiological safety consideratio

17、ns of containment, shielding, and criticality. These radiological safety evaluations, which apply to both damaged and undamaged spent nuclear fuel, are assumed to be addressed as part of the regulatory certification process, and are not the subject of this standard. This standard focuses on aspects

18、of damaged spent nuclear fuel that include such things as identification and classification, preparation, and handling of damaged spent nuclear fuel. The intent of the standard is to provide a descriptive definition of damaged spent fuel and offer methods of determining and categorizing damage, meth

19、ods of handling and treating damaged fuel, and methods of demonstrating fuel condition. The standard is organized into a main body, which may be supplemented by informative appendixes. To meet the standard, the requirements of the main body must be met. The requirements are designated as the “shall“

20、 statements of the standard. In addition to the requirements, the standard may contain recommended practices, designated by the word “should,“ and allowed actions, designated by the word, “may.“ Appendixes are not part of the standard, but serve to provide non-mandatory guidance. Suggestions for imp

21、rovement of this standard will be welcome. They should be sent to the Institute of Nuclear Materials Management, 60 Revere Drive, Suite 500, Northbrook, IL 60062. This standard was prepared and approved for submittal to ANSI by the Accredited Standards Committee on Packaging and Transportation of Ra

22、dioactive and Non-Nuclear Hazardous Materials, N14. Committee approval of the standard does not necessarily imply that all committee members voted for its approval. At the time it approved this standard, the N14 Committee had the following members: Copyright American National Standards Institute Pro

23、vided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-viiiRichard R. Rawl, Chair William H. Lake, Vice-Chair M. B. Hawk, Secretary Organization Represented Name of Representative ASTM J. R. Johnston Health Physics Society. K. Nelson In

24、stitute of Nuclear Materials Management R. R. Rawl U.S. Department of Energy M. E. Wangler U.S. Department of Transportation R. Boyle U.S. Environmental Protection Agency. J. S. Telofski U.S. Nuclear Regulatory Commission. N.L. Osgood Individual Members Dr. E. Bentz B. Jody R. R. Rawl R. Best J. R.

25、Johnston T. Rummell R. Boyle L. Johnston (Alt.) A. C. Rymer A. E. Castagnacci A. Kapoor T. A. Shelton M. Charette M. Krzaniak (Alt.) J. S. Telofski M. E. Darrough W. H. Lake D. C. Thomas P. Eyre M. T. Lambert G. A. Townes F. Falci B. Lester Dr. P. Turula F. Ferate R. E. Luna Dr. R. A. Vaughan L. E.

26、Fischer Dr. G. W. May J. M. Viebrock D. Goertzen E. McNeil B. H.Wakeman C. Green K. Nelson R. Walker P. C. Gregory D. J. Nolan M. E. Wangler A.W. Grella Dr. J. J. Oras, Jr D. J. Warriner R. M. Grenier N. L. Osgood R. H. Yoshimura M. B. Hawk R. B. Pope A. Zimmer J. H. Hummer S. A. Porter Members of t

27、he subcommittee N14.33 on Storage and transport of damaged spent nuclear fuel that developed this standard are as follows: Ray Lambert, Chair Jayant Bondre Arpad L. Lengyel, Secretary Robert Burgoyne Matthew Eyre Geoffrey Hornseth William H. Lake W.J. Lee Paul Plante Brian H. WakemanCopyright Americ

28、an National Standards Institute Provided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-1AMERICAN NATIONAL STANDARD ANSI N14.33-2005 American National Standard Characterizing Damaged Spent Nuclear Fuel For The Purpose of Storage and T

29、ransport 1. SCOPE This standard defines terms related to dry storage and transport of damaged light water reactor (LWR) spent nuclear fuel. It establishes procedures for identifying, categorizing, and managing damaged fuel. The standard provides: methods for identifying and classifying damaged and u

30、ndamaged spent nuclear fuel assemblies; preparation and handling requirements for damaged spent nuclear fuel assemblies for dry storage and transport; requirements for record keeping and quality assurance; and specifies the requirements for canning damaged fuel assemblies. 2. DEFINITIONS Terms defin

31、ed in the applicable documents in Clause 4.0 have the same meaning in this standard. Additional terms have been defined, particularly for the purpose of this standard, and may not conform to those in other publications. Can. An enclosure device to permit routine handling of an individual fuel assemb

32、ly and/or to prevent the escape of any fuel fragments of significant size that may originate from cladding defects in the fuel assembly. The can normally has a fine mesh screen to achieve the particulate confinement, but may be a sealed container that may be integral or separate from the cask. Canni

33、ng. The process of encapsulating a damaged fuel assembly in a can. Copyright American National Standards Institute Provided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-2Confinement. The establishment of a physical barrier that prev

34、ents the escape of fuel fragments of significant size. Confinement need not provide a vapor or liquid tight seal. Containment. The establishment of one or more physical barriers that seals the system and prevents the escape of solid, liquid, or gaseous material that may exist within the containment

35、boundaries. Damaged Fuel. Spent nuclear fuel with known or suspected cladding defects greater than a pinhole or hairline crack. Fuel is also considered damaged if the fuel assembly structure is mechanically damaged or has geometrical changes to the assembly structure such that the assembly cannot be

36、 handled using normal handling methods. Damaged fuel may be classified into the following categories: Cladding Damage, Level I: Cladding defects greater than pinholes or hairline cracks but the fuel assembly still remains intact as a fuel assembly. Cladding Damage, Level II: Fuel that is no longer i

37、n the form of a fuel assembly and consists of debris, loose pellets and particles, rod segments, etc. Fuel Assembly Mechanical Damage: Fuel assemblies that have structural damage such that they can not be handled by normal methods. Pinhole or Hairline Crack: Cladding defects of such a nature that th

38、ey are very small and tight and do not have the potential for any significant amount of fuel particles (particulate) escaping. Retrievability: The ability to handle individual fuel assemblies or canned fuel assemblies using normal methods. 3. APPLICATION The standard applies to dry storage and trans

39、port of damaged commercial light water reactor (LWR) fuel assemblies that are required to be stored or transported in a non-oxidizing environment. 4. RULES AND GUIDANCE FOR DRY STORAGE AND TRANSPORT 4.1 REGULATIONS Regulations pertinent to radioactive material transport packages and to the use of th

40、is standard are specified in: Copyright American National Standards Institute Provided by IHS under license with ANSINot for ResaleNo reproduction or networking permitted without license from IHS-,-,-34.1.1 Title 10 of the Code of Federal Regulations Part 71, “Packaging and Transport of Radioactive

41、Materials“ (10 CFR Part 71). 4.1.2 Title 10 of the Code of Federal Regulations Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste“ (10 CFR Part 72). 4.1.3 Title 49 of the Code of Federal Regulations Part 173 (49 CFR Part 173). 4.1.4 In

42、ternational Atomic Energy Agency (IAEA) Safety Standard Series, “Regulations for the Safe Transport of Radioactive Material,“ No. TS-R-1, 2005 Edition, IAEA, Vienna, Austria. (Although IAEA has no regulatory enforcement authority, their transport regulations serve as the basis for many national regu

43、latory requirements). 4.2 REGULATORY GUIDANCE Regulatory guidance pertinent to the use of this standard may be found in: 4.2.1 U.S. Nuclear Regulatory Commission (NRC) Spent Fuel Project Office Interim Staff Guidance documents, as appropriate. 4.2.2 U.S. Nuclear Regulatory Commission (NRC), Director

44、s Decision Under 10 CFR 2.206, DD-84-09, April 13, 1984. 4.2.3 U.S. Nuclear Regulatory Commission (NRC), “Standard Review Plan for Dry Cask Storage Systems,“ NUREG-1536, January 1997. 4.2.4 U.S. Nuclear Regulatory Commission (NRC), “Standard Review Plan for Transportation Packages for Spent Nuclear

45、Fuel,“ NUREG-1617, March 2000. 4.2.5 U.S. Nuclear Regulatory Commission (NRC), “Standard Review Plan for Spent Fuel Dry Storage Facilities,“ NUREG 1567, March 2000. 4.3 OTHER APPLICABLE STANDARDS 4.3.1 American National Standards Institute, American National Standard for Radioactive Materials, Requi

46、rements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants, ANSI N45.2.9. 4.3.2 American National Standards Institute, American National Standard for Radioactive Materials, Leakage Tests on Packages for Shipment, ANSI N14.5-1997. 4.3.3 American Society of

47、Nondestructive Testing, NDT Personnel Training, Qualifications and Certification- Audit Checklist 1996 and all activities shall be in accordance with a quality assurance program, as described in clause 11.0. Definitions, rules, and guidance for use of this standard are found in clauses 2.0 and 4.0.

48、A flow chart graphically describing the fuel classification methodology is attached as Appendix A. The following processes shall be followed for using this standard: (1) All fuel assemblies shall be evaluated for cladding damage prior to loading for dry storage or transport. The evaluation shall be used to identify and classify damage. If cladding damage is such that it meets the definition of Cladding Damage, Level I or less, then the classification process may proceed. If cladding damage meets the definition of Cladding Dama