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{{#Wiki_filter:Regulatory Guide 1.244 Control of Heav y Loads at Nuclear Facilities Presentation to EPRI Hoisting , Rigging and Crane Users Group
{{#Wiki_filter:Regulatory Guide 1.244 Control of Heavy Loads at Nuclear Facilities Steven Jones Containment and Plant Systems Branch Office of Nuclear Reactor Regulation June 16, 2022 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
Agenda


===1. Introduction===
===1. Introduction===


===2. Continuing Guidance===
===2. Continuing Guidance===


===3. New Guidance===
===3. New Guidance===
Line 28: Line 28:


===5. Public Comments===
===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
===6. Conclusion===


*                                                                                         These consensus standards provide updated guidance:
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


-                                                                            methods to  assure safety functions are  accomplished
Continuing NRC Guidance
      -                                                                            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  
*                                                                                             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


-                                                                           Provides criteria for protection of safety functions
RG 1.244 Endorsed Standards
        -                                                                             Specifies  good practices for the  handling of heavy loads
* American Society of Mechanical Engineers (ASME) Standard NML-1-2019, Rules for the Movement of Loads Using Overhead Handling Equipment in Nuclear Facilities
*                                                                                             NUREG-0554, Single Failure                    -Proof Cranes  for Nuclear Power Plants
- 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


-                                                                              Provides criteria for crane design, fabrication, and testing
Endorsed Standards (cont.)
        -                                                                            Specifies features to control load following challenges
* ASME Std. NOG-1-2020, Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder)  
*                                                                                            ANSI N14.6, Radioactive Materials                                                                                                Special Lifting Devices for Shipping Containers Weighing 10 000 Pounds (4500 kg)
- Replacement for NUREG-0554
      or More for Nuclear  Materials
- Reflects current top-running overhead crane technologies
        -                                                                              Provides criteria for lifting device design and testing
* ASME Std. BTH-1-2017, Design of Below-the-Hook Lifting Devices, Chapters 1-3 (mechanical devices)
        -                                                                            Specifies inspection and testing to verify continued compliance RG 1.244 Endorsed Standards
- Provides criteria for the design and fabrication of special lifting devices and load lifting attachments  
*                                                                                            American  Society of  Mechanical Engineers (ASME) Standard NML -1-2019, Rules for  the Movement of Loads Using Overhead Handling Equipment in Nuclear Facilities
- NML-1 and BTH-1 combined address scope of ANSI N14.6
        -                                                                              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
Significant Changes in Guidance
        -                                                                             Administratively restricts sling usage for nuclear safety critical lifts
* 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


*                                                          Straight connections between specially designed attachment points
Changes in Guidance (Cont)
                *                                                         Basket configurations around large diameter rounded objects
* Flexible lifting system design guidance included for special conditions:
        -                                                                             Reduced  burden for design, fabrication, and testing  of special lifting devices
- Large component replacement (e.g., steam generator replacement)
- Space/structural limitations
- Outside nuclear power plant structures (e.g., ISFSI
operations)


*                                                                                             Supports standardization of programs
Safety Significance
        -                                                                             Lifts conducted  by contracted  personnel during refueling o u ta ge s
* 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


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


*                                                                                     Flexible lifting  system design guidance included  for special conditions:
Comment Response
      -                                                                     Large component replacement (e. g., steam generator replacement)
* Background
      -                                                                 Space/structural limitations
- Explained ANSI-N14.6 and ASME BTH-1 relationship
      -                                                                     Outside  nuclear power plant structures  (e. g., ISFSI
- Clarified that controlled ranges of motion and enhanced safety handling systems constitute complete acceptable methods of evaluation
        operations)
- Explained basis for sling restrictions during critical lifts
                            Safety Significance
* 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


*                                                                                          Standard nuclear overhead handling  systems provide reliable performance
Conclusion
      -                                                                            Reasonably low  frequency of  uncontrolled load motion  based on  nuclear plant operating experience
* The staff endorsed three consensus standards
      -                                                                              Acceptable when  safety function  accomplishment would not be challenged by handling system problems
* The NRC staff expects the revised guidance to provide safety and efficiency benefits
      -                                                                        NML-1 provides controls for standard and special lifts
* The NRC staff expects substantial adoption of NML-1 control of heavy loads program guidance through the provisions of licensing basis change control regulations}}
*                                                                                          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}}


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Latest revision as of 17:11, 27 November 2024

Control of Heavy Loads at Nuclear Facilities; Presentation to EPRI Hoisting, Rigging and Cranes User Group, Lexington, Ky
ML22130A563
Person / Time
Issue date: 06/16/2022
From: Steve Jones
NRC/NRR/DSS/SCPB
To:
Steve Jones NRR/DSS 301-415-2712
Shared Package
ML22152A146 List:
References
RG-1.244
Download: ML22130A563 (12)
v • d • e


Regulatory Guide 1.244 Control of Heavy Loads at Nuclear Facilities Steven Jones Containment and Plant Systems Branch Office of Nuclear Reactor Regulation June 16, 2022 Presentation to EPRI Hoisting, Rigging and Crane Users Group

Agenda

1. Introduction

2. Continuing Guidance

3. New Guidance

4. Safety Significance

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

- 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


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