ASME STP-NU-015-2008 A Guide to American Crane Standards for Electric Overhead Traveling Cranes Hoists and Related Equipment for Nuclear Facilities《核能设施用电气高架移动式起重机 小型起重机和相关设备的美国起重机.pdf

《ASME STP-NU-015-2008 A Guide to American Crane Standards for Electric Overhead Traveling Cranes Hoists and Related Equipment for Nuclear Facilities《核能设施用电气高架移动式起重机 小型起重机和相关设备的美国起重机.pdf》由会员分享，可在线阅读，更多相关《ASME STP-NU-015-2008 A Guide to American Crane Standards for Electric Overhead Traveling Cranes Hoists and Related Equipment for Nuclear Facilities《核能设施用电气高架移动式起重机 小型起重机和相关设备的美国起重机.pdf（25页珍藏版）》请在麦多课文档分享上搜索。

1、STP-NU-015A GUIDE TO AMERICANCRANE STANDARDSFor Electric Overhead Traveling Cranes,Hoists, and Related Equipment for NuclearFacilitiesSTP-NU-015 A Guide to American Crane Standards for Electric Overhead Traveling Cranes, Hoists and Related Equipment for Nuclear Facilities Prepared by: ASME Committee

2、 on Cranes for Nuclear Facilities Date of Issuance: April 8, 2008 This report was prepared as an account of work sponsored by the ASME Board on Nuclear Codes that is, “should” is used rather than “shall” throughout the document. However, when nuclear power plant owners invoke NUREG-0554 in crane spe

3、cifications, they typically intend that the crane designer consider all of its guidelines as mandatory. Appendix 3.1 to NUREG-0554, “Checklist of Most Important NUREG-0554 Requirements,” was written by the NRC separately from the NUREG (and apparently not formally issued or added to the base documen

4、t). This Appendix does not cover all the guidelines of the NUREG. It is assumed that NRC licensees (U.S. nuclear power generation plants) and their crane suppliers are expected to demonstrate compliance with all guidelines, and that any deviations are potentially subject to acceptance by the license

5、e and the NRC. The primary intent of NUREG-0554 is to preclude dropping the critical load. A SFP crane design conforming to NUREG-0554 could be assumed acceptable to the NRC and therefore to satisfy regulatory concerns, upon review and acceptance of its design features. Such a design may be enhanced

6、 to provide additional features to protect against the potential for a dropped load, depending on the level of protection desired by the owner. Although NUREG-0554 specifies provisions for emergency lowering and manual positioning of the rated load, it does not consider issues such as operational re

7、coverability from component or system failures, or electrical redundancy/supervisory control. These are frequently important to owners of facilities handling highly radioactive or other hazardous materials, or fragile, explosive, flammable or valuable loads where the consequences of loss of operabil

8、ity or unwanted motion may be unacceptable. In the absence of industry standards, the owner must write his own specifications covering such criteria. 4.2 NUREG-0612, Control of Heavy Loads at Nuclear Power Plants 14 This NRC document, issued in 1980, provides guidelines to operators of nuclear power

9、 plants for handling heavy loads, particularly those moved by overhead cranes. The guidance is based on a philosophy of “defense in depth” against serious load-handling accidents by implementation of training, inspections, safe load paths, administrative controls and analysis of the consequences of

10、dropped loads. The objectives are to preclude damage to nuclear fuel, impairment of equipment necessary for safe shutdown of the reactor or release of radioactive material to the environment. If a load must unavoidably be handled in an area where its falling could result in unacceptable consequences

11、, NUREG-0612 guides the owner to use a SFP crane designed in accordance with NUREG-0554, in addition to the implementation of other appropriate safeguards. Appendix C to NUREG-0612 provides guidelines for modification of existing cranes, including commentary on implementation of NUREG-0554 for opera

12、ting plants with cranes that may need to be upgraded with single-failure-proof features. Note that NUREG-0612 does not offer complete guidelines for SFP crane design. It also is not intended to impose additional guidance to that given in NUREG-0554, and therefore need not be invoked if NUREG-0554 is

13、 already specified. However, its Appendix C suggests optional methods for compliance with certain of the NUREG-0554 guidelines, particularly for existing cranes. A Guide to American Crane Standards STP-NU-015 9 4.3 NUREG-0800, Standard Review Plan (Formerly NUREG-75/087) 15 This NRC document was pub

14、lished to provide guidance to its own staff responsible for review of applications to construct and operate nuclear power plants. Although compliance with standard review plans is not mandatory, familiarity with them can be of considerable benefit to plant owners in their efforts to secure regulator

15、y acceptance. Some sections of NUREG-0800 are applicable to crane design and may be invoked in owners specifications. These would typically be Sections 3.7.2, Seismic System Analysis, and 3.7.3, Seismic Subsystem Analysis. 4.4 Generic Letter 83-42 16 This NRC letter to all nuclear power plant operat

16、ors, dated December 19, 1983, informs them that certain electrical system problems can cause loss of control of the load in certain instances. The potential problem areas include phase loss and phase reversal in AC powered motor and control systems. Appendix 3.1 to NUREG-0554 refers to Generic Lette

17、r 83-42. For new or upgraded SFP cranes, 83-42 can be treated as an addendum to NUREG-0554. However, it is not limited to cranes designated as SFP. All cranes in U.S. nuclear power plants should potentially be evaluated against the criteria in this letter. 4.5 Bulletin 96-02: Movement of Heavy Loads

18、 over Spent Fuel, over Fuel in the Reactor Core or over Safety-Related Equipment 17 This bulletin was issued by the NRC to nuclear plant operators on April 11, 1996. It alerts them to the importance of complying with existing regulatory guidelines related to control of heavy loads, requests that the

19、y review their plans and capabilities for handling heavy loads, and requires that they report to the NRC their compliance with the requirements of the bulletin. It clarifies the regulatory intent regarding NUREG-0612 and related NRC documents. Bulletin 96-02 expresses concern on the part of the NRC

20、that licensees may believe they comply with guidelines for control of heavy loads based on prior reviews of the subject, when in fact the NRC did not necessarily take the same view and may not consider all of the licensees conclusions to be valid. The required reports are to address handling heavy l

21、oads with the reactor at power, with consideration to the possibility of damage to safety-related equipment, fuel in the reactor core or spent fuel. The reports also must consider the potential complications resulting from the breach of a dry storage cask. Bulletin 96-02 does not address the design

22、of cranes or other load-handling equipment. Its implementation may lead to the conclusion that a crane once considered safe enough should be upgraded with SFP features. 4.6 NRC Regulatory Issue Summary 2005-25: Clarification of NRC Guidelines for Control of Heavy Loads 18 This Regulatory Issue Summa

23、ry (RIS) was issued by the NRC on October 31, 2005, followed by Supplement 1 dated May 29, 2007. It summarizes, clarifies and emphasizes regulatory guidance provided in previous NRC documents, primarily NUREG-0612 but also including NUREG-0554, NUREG-1774 and GL 96-02. It addresses a range of issues

24、 including safe load paths, procedures for load handling, crane operators, crane design, crane inspection, testing and maintenance, special lifting devices, slings, consequence evaluations of load drops, upgrade of existing cranes to SFP and seismic qualification of crane structures. The RIS states

25、that the Advisory Committee on Reactor Safeguards (ACRS) has endorsed several recommendations, including a recommendation that the NRC endorse ASME NOG-1 (Type I) as an acceptable design basis for single-failure-proof cranes. STP-NU-015 A Guide to American Crane Standards 10 4.7 10 CFR Part 50, Appe

26、ndix B 19 Part of the Code of Federal Regulations (CFR), which is U.S. federal law, this document mandates quality assurance provisions for the design, construction and operation of structures, systems and components used in nuclear power plants licensed by the NRC. A quality assurance program in ac

27、cordance with ASME NQA-1, if properly established and implemented, may meet the criteria of Part 50, Appendix B. Note that some U.S. nuclear power plants, as well as other facilities handling nuclear materials may have as part of their license or regulatory requirements quality provisions based on s

28、tandards other than Appendix B. In such cases the applicable standards should be identified by the owner for implementation by the equipment supplier. 4.8 10 CFR Part 21 20 10 CFR “Part 21, Reporting of Defects and Noncompliance”, is a provision of U.S. federal law. It obligates individuals or organ

29、izations having knowledge of a potential safety deficiency in a component or equipment used in a nuclear power plant to report the potential problem to the NRC. This includes crane components or systems that, if they failed, could create a substantial safety hazard at a facility regulated by the NRC

30、. 4.9 29 CFR Part 1910.179 21 29 CFR, Labor, is the section of U.S. federal law commonly known as OSHA (for Occupational Safety and Health Act). Part 1910.179 is the section of the regulation dealing with overhead cranes. It applies to all overhead cranes, including those in nuclear facilities. Its

31、main intent is to ensure the safety of persons operating or maintaining the equipment or having reason to be on or near it. OSHA is a safety code, not a design standard. It requires the owner of the equipment to make sure it meets federal standards for such things as access, footwalks and handrails,

32、 ladders, brakes, guards, rail sweeps, bumpers, operational limits and warning devices. Owners typically specify that their suppliers of new equipment or equipment modifications comply with the applicable OSHA provisions. The owner retains the responsibility for compliance, including inspection and

33、maintenance. Part 1910.179 invokes ASME B30.2. A Guide to American Crane Standards STP-NU-015 11 5 INDUSTRY AND NATIONAL CONSENSUS STANDARDS 5.1 Crane Manufacturers Association of America (CMAA) Specification No. 70 22 Widely accepted in the United States, and often invoked in crane procurement spec

34、ifications for other countries, this standard is produced by the CMAA engineering committee and published for CMAA by its parent organization, Material Handling Industry of America (MHIA). CMAA 70 provides minimum design standards for multiple-girder, top-running bridge and gantry cranes. It establi

35、shes six classes of service, A through F, based on loading spectrum and frequency of operation. It has a section on building design considerations including clearances, runway tolerances and runway conductors. Design sections include structural, mechanical and electrical. CMAA specifications are pri

36、marily intended for commercial industrial applications. They do not address special requirements such as seismic qualification, SFP features or enhanced safety options, recoverability features or quality assurance programs. 5.2 CMAA Specification No. 74 23 A companion standard to CMAA 70 Specificati

37、on No. 74 applies to single-girder cranes, both top-running and underhung, that utilize under-running trolley hoists. Since it anticipates the use of standard commercial monorail hoists, its mechanical and electrical design sections omit hoists for the most part, and deal primarily with bridge and t

38、rolley travel equipment. 5.3 CMAA Specification No. 78 24 This standard, titled “Standards and Guidelines for Professional Services Performed on Overhead and Traveling Cranes and Associated Hoisting Equipment”, was first published in 2002. It was prepared by the Crane Manufacturers Service Committee

39、, a standing committee of the CMAA. As its title suggests, CMAA 78 offers guidance and recommendations on a variety of topics related to inspection and service of cranes. These include qualifications for crane inspectors and technicians, job site safety guidelines and recommended practices for inspe

40、ction, maintenance and testing. 5.4 Monorail Manufacturers Association ANSI Standard MH 27.1, Specifications for Patented Track Underhung Cranes and Monorail Systems 25 This industry standard provides design requirements for underhung cranes and monorail systems that use patented track, which is a s

41、pecially rolled, extruded or fabricated section having a flat, hardened lower flange as the running surface for the wheels of an underhung end truck or monorail hoist. The standard covers duty service classifications, runway and monorail track design and tolerances, track switches, openers, and lift

42、 or drop sections, carriers, trolleys, cranes, brakes and electrical systems. It does not address special requirements such as seismic qualification, SFP features or enhanced safety options, recoverability features or quality assurance programs. STP-NU-015 A Guide to American Crane Standards 12 5.5

43、Monorail Manufacturers Association ANSI Standard MH 27.2, Specifications for Enclosed Track Underhung Cranes and Monorail Systems 26 This industry standard is a parallel or companion standard to MH 27.1, for enclosed track runways and monorail beams rather than patented track. It covers essentially

44、the same information as MH 27.1. 5.6 Association of Iron & Steel Technology (AIST) Technical Report No. 6 27 This report, entitled “Specification for Electric Overhead Traveling Cranes for Steel Mill Service”, was prepared by a committee of the AIST consisting of steel mill crane owners, engineers a

45、nd crane manufacturers. Since many steel mill cranes handle loads frequently and often operate in hot and dirty environments, one of the primary objectives of this standard is to promote equipment designs that result in long-term reliability and ease of maintenance and repair. Technical Report No. 6

46、 establishes four classes of crane service, based on load spectrum and frequency of use. Structural, mechanical and electrical design sections provide specific design criteria. These are in some cases more conservative than those of CMAA specifications, in keeping with the primary objectives of the

47、standard, and typically result in a heavier and potentially more durable crane. AIST No. 6 does not address some of the criteria pertinent to critical load handling cranes such as SFP features, formal quality assurance programs, recoverability features or seismic qualification. 5.7 National Electric

48、al Code (NFPA 70) 28 The National Electrical Code (NEC) is prepared by the National Electrical Code Committee and published by the National Fire Protection Association, Inc. (NFPA). Article 610, Cranes and Hoists, is applicable to the installation of electrical equipment and wiring used in connectio

49、n with cranes, hoists, monorail hoists and runways. It includes provisions for, among others, hazardous locations, wiring methods, types of conductors and their rating, fittings, contact conductor systems (such as sliding shoe runway conductors), disconnecting means, protective features, controllers and grounding. The NEC (specifically Article 610) is referenced in CMAA 70 and 74, NOG-1, and NUM-1. 5.8 ANSI/AWS D14.1, Specification for Welding of Industrial and Mill Cranes and Other Material Handling Equipment 29 Notwithstanding its title, the scope section