Regulatory Guide 1.244

Control of Heavy Loads at Nuclear Facilities; Presentation to EPRI Hoisting, Rigging and Cranes User Group, Lexington, Ky

ML22130A563
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Issue date:	06/16/2022
From:	Steve Jones NRC/NRR/DSS/SCPB
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Steve Jones NRR/DSS 301-415-2712
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ML22152A146	List: ML22152A151 Regulatory Guide 1.244
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RG-1.244
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Regulatory Guide 1.244 Control of Heav y Loads at Nuclear Facilities Presentation to EPRI Hoisting , Rigging and Crane Users Group

Steven Jones Containment and Plant Systems Branch Office of Nuclear Reactor Regulation June 16, 2022 Agenda

5. Public Comments

6. Conclusion Introduction

• Purpose of RG 1.244:

- Endorse appropriate consensus standards

- Update guidance contained in current technical reports

- Expand applicability to include major component replacement and spent fuel storage

• These consensus standards provide updated guidance:

- methods to assure safety functions are accomplished

- standards for design, fabrication, operation, maintenance, and testing , especially for enhanced safety systems Continuing NRC Guidance

• NUREG-0612, Control of Heavy Loads at Nuclear Power Plants

- Provides criteria for protection of safety functions

- Specifies good practices for the handling of heavy loads

• NUREG-0554, Single Failure -Proof Cranes for Nuclear Power Plants

- Provides criteria for crane design, fabrication, and testing

- Specifies features to control load following challenges

• ANSI N14.6, Radioactive Materials Special Lifting Devices for Shipping Containers Weighing 10 000 Pounds (4500 kg)

or More for Nuclear Materials

- Provides criteria for lifting device design and testing

- Specifies inspection and testing to verify continued compliance RG 1.244 Endorsed Standards

• American Society of Mechanical Engineers (ASME) Standard NML -1-2019, Rules for the Movement of Loads Using Overhead Handling Equipment in Nuclear Facilities

- Replacement for NUREG- 0612

- Qualitative risk- informed approach

- Scope expanded for wider use at nuclear facilities

- Updated to reflect operating experience

• Restrictions on use of slings

• Simplified compliance testing for special lifting devices Endorsed Standards (cont.)

• ASME Std. NOG-1- 2020, Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder)

- Replacement for NUREG-0554

- Reflects current top- running overhead crane technologies

• ASME Std. BTH-1- 2017, Design of Below- the-Hook Lifting Devices, Chapters 1- 3 (mechanical devices)

- Provides criteria for the design and fabrication of special lifting devices and load lifting attachments

- NML- 1 and BTH-1 combined address scope of ANSI N14.6 Significant Changes in Guidance

• Incorporates lessons from several decades of operating experience

- Administratively restricts sling usage for nuclear safety critical lifts

• Straight connections between specially designed attachment points

• Basket configurations around large diameter rounded objects

- Reduced burden for design, fabrication, and testing of special lifting devices

• Supports standardization of programs

- Lifts conducted by contracted personnel during refueling o u ta ge s

- Adds rig gers to scope of training included in program Changes in Guidance ( Cont )

• Flexible lifting system design guidance included for special conditions:

- Large component replacement (e. g., steam generator replacement)

- Space/structural limitations

- Outside nuclear power plant structures (e. g., ISFSI

operations)

Safety Significance

• Standard nuclear overhead handling systems provide reliable performance

- Reasonably low frequency of uncontrolled load motion based on nuclear plant operating experience

- Acceptable when safety function accomplishment would not be challenged by handling system problems

- NML-1 provides controls for standard and special lifts

• Enhanced safety handling systems

- Reduces frequency of uncontrolled load motion

- Acceptable for Nuclear Safety Critical Lifts Public Comments

• Availability of Draft Guide 1381 for public comment published in Federal Register on May 4, 2021

• Public comment period ended on July 5, 2021

• 24 Nuclear Energy Institute (NEI) comments:

- 11 related to clarification of specific items

- 5 related to licensing basis change control process

- 4 related to endorsement of additional standards

- 4 related to enhance flexibility through credit for administrative controls or alternative design elements

• Toverlapped with NEI comments.wo individuals provided additional comments that Comment Response

• Background

- Explained ANSI-N14.6 and ASME BTH-1 relationship

- Clarified that controlled ranges of motion and enhanced safety handling systems constitute complete acceptable methods of evaluation

- Explained basis for sling restrictions during critical lifts

• Regulatory guidance

- Seismic qualification of cranes used for nuclear safety critical lifts with controlled range of motion

- Clarified alternative enhanced safety crane design criteria

- Clarification of sling restrictions for critical lifts Conclusion

• The staff endorsed three consensus standards

• The NRC staff expects the revised guidance to provide safety and efficiency benefits

• The NRC staff expects substantial adoption of NML- 1 control of heav y loads program guidance through the provisions of licensing basis change control regulations