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 Heavy 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

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 MaterialsSpecial 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 outages

- Adds riggers 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

• Two individuals provided additional comments that overlapped with NEI comments.

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 heavy loads program guidance through the provisions of licensing basis change control regulations