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Category:Meeting Briefing Package/Handouts
MONTHYEARML24310A2262024-11-0606 November 2024 NEI Preliminary Perspectives on NRC Draft Noak Microreactor White Paper ML24303A2212024-10-29029 October 2024 NEI SDP Realism Presentation for October 30, 2024 Public Meeting ML24291A0062024-10-17017 October 2024 NEI Slide Presentation: ACRS Regulatory Policies and Practices - Draft White Paper on Nth-of-a-Kind (Noak) Micro-Reactor Licensing and Deployment Considerations - Sc - October 17, 2024 ML24267A0032024-09-25025 September 2024 NEI Slides for ROP Public Meeting Sept 2024 ML24263A2592024-09-17017 September 2024 06 Jim Slider NEI September 2024 NRC Ai Public Workshop 09-17-2024 ML24249A2012024-09-0909 September 2024 NEI Presentation - Sept 9 Public Meeting - Flooding DGs - Final ML24249A1152024-09-0505 September 2024 Power Uprate September 5, 2024 Public Meeting Slides ML24243A1612024-08-30030 August 2024 Slide Presentations for High Burnup (Hbu) Workshop V ML24228A2102024-08-20020 August 2024 2024 NEI Early Warning System (EWS) Presentation - NEI Slides ML24229A0012024-08-19019 August 2024 NEI - Spent Fuel Management: Safety and Efficiency Improvements Through Technology and Performance Margins - NRC PIRTs Public Meeting Rev. 8.15.2024 Final ML24218A1832024-07-30030 July 2024 NEI 7-30-24 Trial Use RG 1.247 Path Forward Final ML24172A1952024-06-27027 June 2024 NEI Slides for 06-27-2024 Public Meeting Structures as IROFS at Fuel Cycle Facilities ML24178A0372024-06-26026 June 2024 NRC Power Uprate Review Preparation June 26, 2024 Public Meeting Slides ML24164A1972024-06-17017 June 2024 Public Meeting Slides - NRC Staff Comments and Observations on NEI 10-01, Rev 2 Industry Guideline for Developing a Plant Parameter Envelope in Support of an Early Site Permit ML24129A1382024-05-0808 May 2024 NEI Slides on Centralized Inspections for May 9, 2024 Public Workshop ML24103A1532024-04-12012 April 2024 NEI Supplemental Information on NRC Comments of NEI 20-07 Rev E (Non-Proprietary) - Slides ML24088A2252024-03-26026 March 2024 NEI Slides for Centralized Inspections March 2024 ROP Public Meeting ML24075A2092024-03-14014 March 2024 NEI Advanced Reactor Di&C Task Force Slides - Accident Monitoring Instrumentation ML24075A2102024-03-14014 March 2024 NEI Alan Campbell Slides - Non-Safety-Related with Special Treatment – Digital Considerations ML24086A5342024-03-14014 March 2024 RIC 2024 TH23 Slides - the Industry’S Innovation Imperative ML24067A0062024-03-0808 March 2024 1 - NRC - Workshop3 - Non-LOCA Release Fractions Feedback - Final ML24067A0072024-03-0808 March 2024 2 - NRC - Workshop3 - Non-LOCA - FFRD - Final ML24067A0092024-03-0808 March 2024 3 - NRC - Worshop3 - CR Dose Presentation - Final ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24067A0122024-03-0808 March 2024 6 - NRC - Workshop3 - Best Estimate Dose ML24067A0132024-03-0808 March 2024 7 - NRC - Workshop3 - Closing Remarks ML24067A2882024-03-0808 March 2024 1 (Revised)-NRC_Workshop3_Non-LOCA Release Fraction Feedback-Final ML24043A1202024-02-13013 February 2024 2- CR Dose Presentation Workshop 2 ML24043A1162024-02-13013 February 2024 3- EQ Presentation Workshop 2 ML24043A1192024-02-13013 February 2024 1- Impacts on RG 1.183 for Workshop2 ML24016A2372024-01-17017 January 2024 NEI Environmental Reviews Slides Public Meeting 1-17-24 ML24008A0442024-01-0909 January 2024 NEI - Slides for NRC Workshop 1 on Revision to RG 1.183 R1 - Final - ML24008A044 ML23342A0262023-12-14014 December 2023 December 14, 2023, Presentation on NEI 23-01 Operator Cold Licensing Training Plan for Advanced Nuclear Reactors ML23347A1782023-12-13013 December 2023 12-14 NEI EPRI Presentation NRC Public Meeting 16-03 R1 ML23303A1922023-10-30030 October 2023 NEI Slides for SLR Public Meeting - Oct 31 2023 ML23324A2392023-10-24024 October 2023 S1P6 - Hilary Lane - NRC AMT Workshop - Oct. 2023 ML23258A1992023-09-20020 September 2023 NEI 99-02 Draft Rev. 8 Update for Sept 2023 ROP Public Meeting ML23242A0782023-08-30030 August 2023 Hbu Workshop IV Industry Presentation: Drive to Deploy ATF with Increased Enrichment and Higher Burnup ML23230A0142023-08-22022 August 2023 Industry Slide Presentation for 8-22-23 Meeting on ARCAP-TICAP and DG-1404 Guidance Documents ML23191A0632023-07-0707 July 2023 NEI Cybersecurity Presentation for July 2023 ROP Public Meeting ML23191A0662023-07-0707 July 2023 NEI 99-02 Draft Rev. 8 Update for July 2023 ROP Public Meeting ML23160A1512023-06-15015 June 2023 25 - Industry - Industry Perspectives on ASME III and XI Pre-Service Inspection ML23160A1422023-06-15015 June 2023 20 - Industry - Industry Perspective on Performance Monitoring ML23116A1892023-05-31031 May 2023 Industry Observations of NRC Licensing Program (NEI Slides May 2023) ML23136A5912023-05-18018 May 2023 NEI Safety Culture Presentation for May 2023 ROP Public Meeting ML23125A3192023-05-0909 May 2023 NEI Presentation for May 9, 2023, Public Meeting on NEI 22-05, Revision a ML23115A0302023-04-27027 April 2023 NEI Perspective on Performance Monitoring in Use of Probabilistic Fracture Mechanics for Optimizing Inspections of Non-RPV Pressure Vessels, April 27, 2023 ML23088A0822023-03-30030 March 2023 NEI Presentation - March 30, 2023 PRA Configuration Control Public Meeting ML23082A0572023-03-28028 March 2023 Proposal to Establish Alternate Requirements for Components Commensurate with Safety and Risk ML23079A2642023-03-23023 March 2023 General Visual Examination of Containment Surfaces Covered by Insulation - March 23, 2023 Public Meeting Slides from NEI 2024-09-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24310A2262024-11-0606 November 2024 NEI Preliminary Perspectives on NRC Draft Noak Microreactor White Paper ML24303A2212024-10-29029 October 2024 NEI SDP Realism Presentation for October 30, 2024 Public Meeting ML24291A0062024-10-17017 October 2024 NEI Slide Presentation: ACRS Regulatory Policies and Practices - Draft White Paper on Nth-of-a-Kind (Noak) Micro-Reactor Licensing and Deployment Considerations - Sc - October 17, 2024 ML24267A0032024-09-25025 September 2024 NEI Slides for ROP Public Meeting Sept 2024 ML24263A2592024-09-17017 September 2024 06 Jim Slider NEI September 2024 NRC Ai Public Workshop 09-17-2024 ML24249A2012024-09-0909 September 2024 NEI Presentation - Sept 9 Public Meeting - Flooding DGs - Final ML24249A1152024-09-0505 September 2024 Power Uprate September 5, 2024 Public Meeting Slides ML24243A1612024-08-30030 August 2024 Slide Presentations for High Burnup (Hbu) Workshop V ML24228A2102024-08-20020 August 2024 2024 NEI Early Warning System (EWS) Presentation - NEI Slides ML24229A0012024-08-19019 August 2024 NEI - Spent Fuel Management: Safety and Efficiency Improvements Through Technology and Performance Margins - NRC PIRTs Public Meeting Rev. 8.15.2024 Final ML24218A1832024-07-30030 July 2024 NEI 7-30-24 Trial Use RG 1.247 Path Forward Final ML24197A0652024-07-17017 July 2024 SDP Realism Public Meeting NEI Presentation ML24172A1952024-06-27027 June 2024 NEI Slides for 06-27-2024 Public Meeting Structures as IROFS at Fuel Cycle Facilities ML24178A0372024-06-26026 June 2024 NRC Power Uprate Review Preparation June 26, 2024 Public Meeting Slides ML24164A1972024-06-17017 June 2024 Public Meeting Slides - NRC Staff Comments and Observations on NEI 10-01, Rev 2 Industry Guideline for Developing a Plant Parameter Envelope in Support of an Early Site Permit ML24130A1972024-05-0909 May 2024 NEI Presentation Slides on Rapid and Large-Scale Nuclear Reactor Deployments for Remote Industrial Applications - May 14 2024 Public Meeting ML24129A1382024-05-0808 May 2024 NEI Slides on Centralized Inspections for May 9, 2024 Public Workshop ML24114A1142024-04-18018 April 2024 NEI Supplemental Information on NRC Comments on NEI 20-07, Draft Revision E - April 18 Meeting (Non-Proprietary) ML24103A1532024-04-12012 April 2024 NEI Supplemental Information on NRC Comments of NEI 20-07 Rev E (Non-Proprietary) - Slides ML24092A3132024-04-0303 April 2024 Public Mtg_2024-04-03 Pre-submittal Meeting with the Nuclear Energy Institute (NEI) to Discuss an Update to NEI 03-12, Security Plan Template (Revision 8)_NEI Slides ML24088A2252024-03-26026 March 2024 NEI Slides for Centralized Inspections March 2024 ROP Public Meeting ML24075A2092024-03-14014 March 2024 NEI Advanced Reactor Di&C Task Force Slides - Accident Monitoring Instrumentation ML24075A2102024-03-14014 March 2024 NEI Alan Campbell Slides - Non-Safety-Related with Special Treatment – Digital Considerations ML24082A1792024-03-14014 March 2024 RIC-2024 TH18 True Slides ML24086A5342024-03-14014 March 2024 RIC 2024 TH23 Slides - the Industry’S Innovation Imperative ML24067A2592024-03-13013 March 2024 RIC-2024 W14 Slides - NEI-BHoltzman an Industry Perspective on Advanced Reactor Construction Oversight ML24067A0062024-03-0808 March 2024 1 - NRC - Workshop3 - Non-LOCA Release Fractions Feedback - Final ML24067A0072024-03-0808 March 2024 2 - NRC - Workshop3 - Non-LOCA - FFRD - Final ML24067A0092024-03-0808 March 2024 3 - NRC - Worshop3 - CR Dose Presentation - Final ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24067A0122024-03-0808 March 2024 6 - NRC - Workshop3 - Best Estimate Dose ML24067A0132024-03-0808 March 2024 7 - NRC - Workshop3 - Closing Remarks ML24067A2882024-03-0808 March 2024 1 (Revised)-NRC_Workshop3_Non-LOCA Release Fraction Feedback-Final ML24043A1162024-02-13013 February 2024 3- EQ Presentation Workshop 2 ML24043A1192024-02-13013 February 2024 1- Impacts on RG 1.183 for Workshop2 ML24043A1202024-02-13013 February 2024 2- CR Dose Presentation Workshop 2 ML24016A2372024-01-17017 January 2024 NEI Environmental Reviews Slides Public Meeting 1-17-24 ML24010A0202024-01-11011 January 2024 Public Meeting on SLR Efficiencies - NEI Presentation ML24008A0442024-01-0909 January 2024 NEI - Slides for NRC Workshop 1 on Revision to RG 1.183 R1 - Final - ML24008A044 ML23342A0262023-12-14014 December 2023 December 14, 2023, Presentation on NEI 23-01 Operator Cold Licensing Training Plan for Advanced Nuclear Reactors ML23347A1782023-12-13013 December 2023 12-14 NEI EPRI Presentation NRC Public Meeting 16-03 R1 ML23303A1922023-10-30030 October 2023 NEI Slides for SLR Public Meeting - Oct 31 2023 ML23324A2392023-10-24024 October 2023 S1P6 - Hilary Lane - NRC AMT Workshop - Oct. 2023 ML23261C3792023-09-27027 September 2023 NEI 22-04 Pre-Submittal Meeting with NRC - September 27, 2023 ML23258A1992023-09-20020 September 2023 NEI 99-02 Draft Rev. 8 Update for Sept 2023 ROP Public Meeting ML23242A0782023-08-30030 August 2023 Hbu Workshop IV Industry Presentation: Drive to Deploy ATF with Increased Enrichment and Higher Burnup ML23242A1662023-08-30030 August 2023 The Future of Nuclear Power: 2023 Baseline Survey (Slides) ML23230A0142023-08-22022 August 2023 Industry Slide Presentation for 8-22-23 Meeting on ARCAP-TICAP and DG-1404 Guidance Documents ML23228A0042023-08-18018 August 2023 NEI Slides for Public Meeting to Discuss Possible Efficiencies on the Subsequent License Renewal Review - August 18, 2023 ML23191A0162023-07-11011 July 2023 NEI Comments on Risk-Informed Process for Evaluation (RIPE) DORL TSG - 7/11/23 Public Meeting Slides from NEI 2024-09-09
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Text
Response Requirements and Credit for Early Warning Systems
August 20, 2024
©2024 Nuclear Energy Institute Presentation Overview
- Questions on Required Systems
- Questions on Voluntary Systems
©2024 Nuclear Energy Institute 2 Terminology
The term early warning system (EWS) was used dating back to the mid-2010s to describe a system beyond the protected area barrier, which would be used to provide early engagement opportunities for some licensees protective strategies and would be the point needed to effectively implement other licensees response to ensure interdiction.
In 2016 the NRC and industry used the terms voluntary system and required system to differentiate between the two systems with different objectives.
©2024 Nuclear Energy Institute 3 Terminology
For purposes of this presentation the terms voluntary system and required system will be used to ensure a common understanding of the system being discussed, however these terms are not defined in the 10 CFR and do not adequately represent the description of each system in meeting the specific objective for the system.
The industry proposes new terms be developed that more closely represent the intend function of the systems.
©2024 Nuclear Energy Institute 4 Analysis of 10 CFR 73.55 related to Required and Voluntary Systems Analysis
An excel spreadsheet (crosswalk) containing each section of 73.55 was reviewed to determine the minimum requirements as well as additional requirements a licensee may need to meet the specific objective of the sites required or voluntary system.
©2024 Nuclear Energy Institute 6 Benefits of using the Crosswalk
The crosswalk allows for:
- A clear indication of the licensees system objective related to existing regulations
- A basis for system design and capabilities
- A tie to existing inspection criteria
- A foundation to develop a Security Plan summary
- Evaluation of when a licensing action may be required
©2024 Nuclear Energy Institute 7 Analysis
In 2016, the NRC proposed descriptions in the Security Plan as the method to inspect a required or voluntary system.
Although the description would still be required, the crosswalk eliminates ambiguity in the Licensees description of the plan and Physical provides direct ties to inspectable Security criteria based on the systems Plan specific objective.
©2024 Nuclear Energy Institute 8 Required Systems Federal Register / Vol. 44, No. 230 / Wednesday, November 28,1979
10 CFR 73.55(h)(4) (1979)
(4) Upon detection of abnormal presence of activity of persons or vehicles within an isolation zone, a protected area, or a vital area, or upon evidence of intrusion into a protected area or a vital area, the facility security organization shall:
(i) Determine whether or not a threat exists, (ii) Assess the extent of the threat, if any, (iii) Inform local law enforcement agencies of the threat and request assistance, if necessary.
(iv) Require guards or other armed response personnel to interpose themselves between vital areas and any adversary attempting entry for purposes of industrial sabotage, and -
(v) Instruct guards or other armed response personnel to prevent or delay an act of industrial sabotage by applying a sufficient degree of force to counter that degree of force directed at them, including the use of deadly force when there is a reasonable belief it is necessary in self -
defense or in the defense of others.
©2024 Nuclear Energy Institute 10 10 CFR 73.55(b)
(3) The physical protection program must be designed to prevent significant core damage and spent fuel sabotage. Specifically, the program must:
(i) Ensure that the capabilities to detect, assess, interdict, and neutralize threats up to and including the design basis threat of radiological sabotage as stated in §73.1, are maintained at all times.
(ii) Provide defense-in-depth through the integration of systems, technologies, programs, equipment, supporting processes, and implementing procedures as needed to ensure the effectiveness of the physical protection program.
Required systems are designed to ensure one specific aspect of 10 CFR 73.55(b)(3) can be achieved. Specifically, the ability to interdict.
©2024 Nuclear Energy Institute 11 Required system vs. Protected Area
Objectives Required System Protected Area Barrier Access Control X Detection X X Assessment X* X Initiate response X X Storage for SNM X Unescorted Access X First barrier for Vital Area X
- May be needed based on site specific design
©2024 Nuclear Energy Institute 12 Minimum Requirements of a Required System
The minimum requirements for a required system are appropriate sections of:
- 73.55(i), Detection and assessment systems
- 73.55(n), Maintenance, testing, and calibration, and
- 73.55(o), Compensatory measures
Additional section of 10 CFR 73.55 may be applicable depending on the site capability to meet the specific objective of interdiction.
©2024 Nuclear Energy Institute 13 Additional Requirements as Applicable
In addition to 73.55(i), 73.55(n), and 73.55(o), licensees may need to meet additional sections of 10 CFR 73.55 depending on the sites capability to detect, assess, and interdict. These sections may include, as applicable:
- 73.55(e)(1)-(4), Physical barriers
- 73.55(e)(6), Owner controlled area
- 73.55(e)(7), Isolation zone
- 73.55(g), Access controls
- 73.55(h), Search programs
©2024 Nuclear Energy Institute 14 Alternative Measures and Exemptions
In certain circumstances a licensee may need a licensing action to meet the limited scope objective. In these instances, justification should be provided for NRC approval, as to how the system meets or exceeds the specific performance objective of which it was designed for.
Possible licensing actions include:
- 73.55(r), Alternative measures
- 73.5, Specific exemptions
©2024 Nuclear Energy Institute 15 Documentation of a Required System
The crosswalk provides the appropriate sections of the existing 10 CFR 73.55 requirements the system is designed to meet. This crosswalk is essential for the licensee and regulator to have a common understanding of the design basis and intended capabilities of the required system.
This crosswalk can be used to develop a description in the security plan consistent with design and intended capabilities of the system.
Inspection criteria is already available for each section of the code credited. NEI 03-12, Revision 8, will contain a section to document the description and design requirements of the sites required system.
©2024 Nuclear Energy Institute 16 Questions?
©2024 Nuclear Energy Institute 17 Voluntary Systems Minimum Requirements of a Voluntary System
Unlike a required system, voluntary systems are not needed to meet the performance objective of 73.55 and therefore have no minimum requirements, however, in addition to the specific sections the licensee identifies based on the sites enhancement, the following sections as applicable would apply to receive credit during inspections:
- 73.55(n), Maintenance, testing, and calibration, and
- 73.55(o), Compensatory measures
73.55(n) and 73.55(o) provides reasonable assurance that the system is adequately maintained and reliable.
©2024 Nuclear Energy Institute 19 Example of Voluntary System
In this example a licensee selected certain aspects that meet the design and objectives for the system that was installed.
These 73.55(i) requirements combined with applicable sections of 73.55(n) and (o) comprise the requirements of the licensee voluntary system to be inspected and therefore given credit during inspections.
©2024 Nuclear Energy Institute 20 Example of Voluntary System
©2024 Nuclear Energy Institute 21 Documentation of a Voluntary System
The crosswalk used in the previous slide provides the appropriate sections of the existing 10 CFR 73.55 requirements the system is designed to meet. This crosswalk is essential for the licensee and regulator to have a common understanding of the design basis and intended capabilities of a voluntary system.
This crosswalk can be used to develop a description in the security plan consistent with design and intended capabilities of the system.
Inspection criteria is already available for each section of the code credited. NEI 03-12, Revision 8, will contain a section to document the description and design requirements of the sites voluntary system.
©2024 Nuclear Energy Institute 22 Documentation of a Voluntary System
There could be cases where the code does not provide a requirement applicable to system design.
Example: Alarms are received at a static post other than an alarm station.
In this case the licensee would describe the design feature in the security plan without citing a specific section of 10 CFR 73.55.
©2024 Nuclear Energy Institute 23 Questions?
©2024 Nuclear Energy Institute 24