SRM-M190124A: Affirmation Session-SECY-16-0142: Final Rule: Mitigation of Beyond-Design-Basis Events (Rin 3150-AJ49) - Separate Views of Commissioner BurnsML19023A354 |
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secy-16-0142 |
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Category:Commission Voting Record (CVR)
MONTHYEARML24204A0352024-07-19019 July 2024 VR-COMCTH-24-0003: License Renewal and Subsequent License Renewal Review Expectations (Crowell) ML24204A0332024-07-19019 July 2024 VR-COMCTH-24-0003: License Renewal and Subsequent License Renewal Review Expectations (Wright) ML24204A0342024-07-16016 July 2024 VR-COMCTH-24-0003: License Renewal and Subsequent License Renewal Review Expectations (Caputo) ML24170A3952024-06-11011 June 2024 VR-SECY-23-0033: Interim Enforcement Policy for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Radioactive Material at Power Reactor Facilitie ML24170A3982024-06-11011 June 2024 VR-SECY-23-0033: Interim Enforcement Policy for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Radioactive Material at Power Reactor Facilitie VR-COMSECY-24-0008, Request to Solicit for the Appointment of Two New Members on the Advisory Committee on Reactor Safeguards (Hanson)2024-06-10010 June 2024 VR-COMSECY-24-0008: Request to Solicit for the Appointment of Two New Members on the Advisory Committee on Reactor Safeguards (Hanson) ML24159A0052024-06-0606 June 2024 VR-COMDAW-24-0001: Revising the Duration of Design Certifications (Caputo) ML24159A0062024-06-0404 June 2024 COMDAW-24-0001: Revising the Duration of Design Certifications ML24204A0322024-05-30030 May 2024 VR-COMCTH-24-0003: License Renewal and Subsequent License Renewal Review Expectations (Hanson) SECY-17-0100, VR-COMSECY-19-0006: Revised Security Inspection Program Framework (Option 3) in Response to SRM-SECY-17-0100 (Wright)2024-05-14014 May 2024 VR-COMSECY-19-0006: Revised Security Inspection Program Framework (Option 3) in Response to SRM-SECY-17-0100 (Wright) VR-SECY-24-0024, Rulemaking Plan for Freedom of Information Act Regulations, 10 CFR Part 9, Subpart a (Caputo)2024-04-23023 April 2024 VR-SECY-24-0024: Rulemaking Plan for Freedom of Information Act Regulations, 10 CFR Part 9, Subpart a (Caputo) VR-COMSECY-19-0006, Revised Security Inspection Program Framework (Option 3) in Response to SRM-SECY-17-0100 (Caputo)2024-04-23023 April 2024 VR-COMSECY-19-0006: Revised Security Inspection Program Framework (Option 3) in Response to SRM-SECY-17-0100 (Caputo) VR-SECY-21-0098, Proposed Rule: Advanced Nuclear Reactor Generic Environmental Impact Statement (Rin 3150-AK55;NRC-2020-0101) (Caputo)2024-02-0808 February 2024 VR-SECY-21-0098: Proposed Rule: Advanced Nuclear Reactor Generic Environmental Impact Statement (Rin 3150-AK55;NRC-2020-0101) (Caputo) VR-SECY-24-0006, Denial of Request 11 in PRM 72-6 as Part of Notice Discontinuing Independent Spent Fuel Storage Installation Security Requirements Rulemaking (Crowell)2024-01-24024 January 2024 VR-SECY-24-0006: Denial of Request 11 in PRM 72-6 as Part of Notice Discontinuing Independent Spent Fuel Storage Installation Security Requirements Rulemaking (Crowell) VR-COMSECY-23-0016, Renewal of Advisory Committee on the Medical Uses of Isotopes (ACMUI) Charter (Wright)2023-12-14014 December 2023 VR-COMSECY-23-0016: Renewal of Advisory Committee on the Medical Uses of Isotopes (ACMUI) Charter (Wright) COMSECY-23-0016, VR-COMSECY-23-0016: Renewal of Advisory Committee on the Medical Uses of Isotopes (ACMUI) Charter (Caputo)2023-12-14014 December 2023 VR-COMSECY-23-0016: Renewal of Advisory Committee on the Medical Uses of Isotopes (ACMUI) Charter (Caputo) VR-SECY-23-0095, Recommendation to Discontinue the Mississippi Agreement State Programs Probationary Period (Wright)2023-11-27027 November 2023 VR-SECY-23-0095: Recommendation to Discontinue the Mississippi Agreement State Programs Probationary Period (Wright) VR-SECY-23-0072, Final Agency Decision to Implement the Flexible Work Model (Wright)2023-10-30030 October 2023 VR-SECY-23-0072: Final Agency Decision to Implement the Flexible Work Model (Wright) SECY-23-0021, VR-SECY-23-0021: Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (Rin 3150-AK31) (Wright)2023-10-0202 October 2023 VR-SECY-23-0021: Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (Rin 3150-AK31) (Wright) VR-SECY-22-0098, Rulemaking Options for Revising Security Requirements for Facilities Storing Spent Nuclear Fuel and High-Level Radioactive Waste (Wright)2023-09-21021 September 2023 VR-SECY-22-0098: Rulemaking Options for Revising Security Requirements for Facilities Storing Spent Nuclear Fuel and High-Level Radioactive Waste (Wright) VR-SECY-23-0075, Wyomings Proposal to Amend the Existing Agreement to Regulate the Processing of Source Material to Extract Mineral Resources Other than the Uranium or Thorium Content (Wright)2023-09-19019 September 2023 VR-SECY-23-0075: Wyomings Proposal to Amend the Existing Agreement to Regulate the Processing of Source Material to Extract Mineral Resources Other than the Uranium or Thorium Content (Wright) VR-SECY-23-0010, Recommendation for Approval to Retire the Reactor Oversight Process Performance Indicator for Licensee Alert and Notification System Availability and to Develop a Performance Indicator for Emergency Response Facility and E2023-09-0101 September 2023 VR-SECY-23-0010 - Recommendation for Approval to Retire the Reactor Oversight Process Performance Indicator for Licensee Alert and Notification System Availability and to Develop a Performance Indicator for Emergency Response Facility and E VR-SECY-22-0072, Proposed Rule: Alternative Physical Security Requirements for Advanced Reactors (Rin 3150-AK19) (Caputo)2023-08-22022 August 2023 VR-SECY-22-0072: Proposed Rule: Alternative Physical Security Requirements for Advanced Reactors (Rin 3150-AK19) (Caputo) ML23207A1802023-07-26026 July 2023 VR-COMJMB-23-0001: Establishing Commission Expectations for the Effectiveness, Efficiency, and Timeliness of New Reactor Reviews (Crowell) SECY-23-0055, VR-SECY-23-0055: Options for Licensing Emerging Technologies Used for Remediation of Mine Waste (Wright)2023-07-21021 July 2023 VR-SECY-23-0055: Options for Licensing Emerging Technologies Used for Remediation of Mine Waste (Wright) ML23158A2382023-06-0202 June 2023 VR-COMAXC-23-0001: Enabling the Mission - a Measured Approach to the Future of Work (Hanson) VR-COMSECY-23-0008, Request to Solicit for the Appointment of Two New Members on the Advisory Committee on Reactor Safeguards (Hanson)2023-05-24024 May 2023 VR-COMSECY-23-0008: Request to Solicit for the Appointment of Two New Members on the Advisory Committee on Reactor Safeguards (Hanson) SRM-COMSECY-23-0008, VR-COMSECY-23-0008: Request to Solicit for the Appointment of Two New Members on the Advisory Committee on Reactor Safeguards (Crowell)2023-05-24024 May 2023 VR-COMSECY-23-0008: Request to Solicit for the Appointment of Two New Members on the Advisory Committee on Reactor Safeguards (Crowell) ML23158A2412023-05-19019 May 2023 VR-COMAXC-23-0001: Enabling the Mission - a Measured Approach to the Future of Work (Crowell) ML23158A2402023-05-18018 May 2023 VR-COMAXC-23-0001: Enabling the Mission - a Measured Approach to the Future of Work (Baran) ML24170A3962023-05-15015 May 2023 VR-SECY-23-0033: Interim Enforcement Policy for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Radioactive Material at Power Reactor Facilitie ML24170A3972023-05-11011 May 2023 VR-SECY-23-0033: Interim Enforcement Policy for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Radioactive Material at Power Reactor Facilitie VR-SECY-22-0112, Proposed Rule: Radioactive Source Security and Accountability (3150-AK83; NRC-2022-0103) (Crowell)2023-05-0101 May 2023 VR-SECY-22-0112: Proposed Rule: Radioactive Source Security and Accountability (3150-AK83; NRC-2022-0103) (Crowell) VR-SECY-23-0029, Rulemaking Plan for the Implementation of Changes to Reflect Advanced Reactor Export Licensing Considerations (Caputo)2023-04-28028 April 2023 VR-SECY-23-0029: Rulemaking Plan for the Implementation of Changes to Reflect Advanced Reactor Export Licensing Considerations (Caputo) ML23158A2392023-04-18018 April 2023 VR-COMAXC-23-0001: Enabling the Mission - a Measured Approach to the Future of Work (Wright) VR-SECY-22-0109, Proposed Rule: Renewing Nuclear Power Plant Operating Licenses - Environmental Review (Rin 3150-AK32; NRC-2018-0296) (Baran)2022-12-20020 December 2022 VR-SECY-22-0109: Proposed Rule: Renewing Nuclear Power Plant Operating Licenses - Environmental Review (Rin 3150-AK32; NRC-2018-0296) (Baran) VR-COMSECY-22-0012, Renewal of Licensing Support Network Advisory Review Panel Charter (Crowell)2022-10-12012 October 2022 VR-COMSECY-22-0012: Renewal of Licensing Support Network Advisory Review Panel Charter (Crowell) VR-SECY-22-0033, Proposed Rule - Alternatives to the Use of Credit Ratings (NRC-2017-0021; Rin 3150-AJ92) (Baran)2022-07-29029 July 2022 VR-SECY-22-0033: Proposed Rule - Alternatives to the Use of Credit Ratings (NRC-2017-0021; Rin 3150-AJ92) (Baran) VR-SECY-22-0062, Final Rule: NuScale Small Modular Reactor Design Certification (Rin 3150-AJ98; NRC-2017-0029) (Baran)2022-07-29029 July 2022 VR-SECY-22-0062: Final Rule: NuScale Small Modular Reactor Design Certification (Rin 3150-AJ98; NRC-2017-0029) (Baran) VR-SECY-22-0053, Recommendations for Modifying the Reactor Oversight Process Engineering Inspections Periodicity (Baran)2022-07-18018 July 2022 VR-SECY-22-0053: Recommendations for Modifying the Reactor Oversight Process Engineering Inspections Periodicity (Baran) VR-SECY-20-0045, Population Related Siting Considerations for Advanced Reactors (Baran)2022-06-28028 June 2022 VR-SECY-20-0045: Population Related Siting Considerations for Advanced Reactors (Baran) VR-SECY-22-0046, Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson)2022-06-27027 June 2022 VR-SECY-22-0046: Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson) VR-SECY-22-0036, Rulemaking Plan for Renewing Nuclear Power Plant Operating Licenses--10-year Environmental Regulatory Update (NRC-2022-0087) (Baran)2022-06-17017 June 2022 VR-SECY-22-0036: Rulemaking Plan for Renewing Nuclear Power Plant Operating Licenses--10-year Environmental Regulatory Update (NRC-2022-0087) (Baran) VR-SECY-22-0004, Proposed Rule: Items Containing Byproduct Material Incidental to Production (Rin 3150-AJ54; NRC-2015-0017)(Baran)2022-05-16016 May 2022 VR-SECY-22-0004: Proposed Rule: Items Containing Byproduct Material Incidental to Production (Rin 3150-AJ54; NRC-2015-0017)(Baran) COMSECY-22-0006, VR-COMSECY-22-0006: Request to Solicit for the Appointment of New Members on the Advisory Committee on Reactor Safeguards (Baran)2022-05-12012 May 2022 VR-COMSECY-22-0006: Request to Solicit for the Appointment of New Members on the Advisory Committee on Reactor Safeguards (Baran) VR-COMSECY-22-0006, Request to Solicit for the Appointment of New Members on the Advisory Committee on Reactor Safeguards (Wright)2022-05-12012 May 2022 VR-COMSECY-22-0006: Request to Solicit for the Appointment of New Members on the Advisory Committee on Reactor Safeguards (Wright) VR-SECY-22-0014, Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson)2022-04-29029 April 2022 VR-SECY-22-0014: Report to Congress on Abnormal Occurrences: Fiscal Year 2021 (Hanson) VR-SECY-22-0024, Rulemaking Plan for Renewing Nuclear Power Plant Operating Licenses - Environmental Review (Wright)2022-04-0505 April 2022 VR-SECY-22-0024: Rulemaking Plan for Renewing Nuclear Power Plant Operating Licenses - Environmental Review (Wright) VR-SECY-20-0098, Path Forward and Recommendations for Certain Low-Level Radioactive Waste Disposal Rulemaking (Baran)2022-04-0505 April 2022 VR-SECY-20-0098: Path Forward and Recommendations for Certain Low-Level Radioactive Waste Disposal Rulemaking (Baran) SECY-21-0066, VR-SECY-21-0066: Rulemaking Plan for Renewing Nuclear Power Plant Operating Licenses - Environmental Review (Rin 3150-AK32; NRC-2018-0296)2022-02-24024 February 2022 VR-SECY-21-0066: Rulemaking Plan for Renewing Nuclear Power Plant Operating Licenses - Environmental Review (Rin 3150-AK32; NRC-2018-0296) 2024-07-19
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Separate Views of Commissioner Burns The version of the final rule supported by the majority of the Commission will, in my view, significantly weaken what will be the agency's most enduring action as a result of lessons learned from the Fukushima Daiichi accident. In doing so, the Commission will have systematically and inexplicably unraveled a framework for addressing beyond
-design-basis external events carefully crafted as a collaborative effort between the NRC staff and our external stakeholders in the years since the accident occurred in March 2011
. I am chiefly concerned with the position the Commission majority has taken with respect to the reevaluated hazard analyses performed by licensees. This position is particularly disconcerting given that the accident at Fukushima was a direct result of the operator and regulator failing to take action to account for new scientific knowledge related to natural hazards, especially flooding hazards. In this regard, I believe that the majority has undermined the Commission's past position on these issues. In their edits to the statements of consideration for the final rule as well as to the supporting backfitting assessment, the majority has mischaracterized the Commission decision on COMSECY 0037. In its March 2015 Sta ff Requirements Memorandum on COMSECY 0037, the Commission approved the staff's recommendation "that licensees for operating nuclear power plants need to address the reevaluated flooding hazards within their mitigation strategies for beyond
-design-basis external events." The staff was explicit in COMSECY 0037 about what i t was asking of the Commission: The NRC staff is asking the Commission to support the planned approach by affirming that the MBDBE rulemaking needs to require mitigating strategies that are able to address the reevaluated flooding hazards developed in response to the § 50.54(f) letters in order to ensure reasonable assurance of adequate protection of the public health and safety
. (emphasis added)
The staff followed the Commission's unequivocal direction when it presented the proposed rulemaking on the Mitigation of Beyond
-Design Basis Events to the Commission in April 2015. In the draft proposed rule, the staff clearly stated that the proposed rulemaking would apply to power reactor applicants and licensees and include proposed "requirements for the reasonable protection of mitigation equipment for beyond
-design-basis external events that reflect the reevaluated hazards determined through regulatory efforts stemming from the 10 CFR 50.54(f) request issued on March 12, 2012." In the Commission paper transmitting the proposed rule (SECY-15-0065), the staff highlighted the fact that the proposed rule would "resolve and clarify the necessary actions a licensee must take to continue to show adequate protection of public health and safety, in light of the reevaluated hazards, as directed in SRM-COMSECY-14-0037." The Commission unanimously approved publication of the draft proposed rule and noted only two exceptions it was taking to the staff's proposals, neither of which involved the need for mitigation strategies to reflect the reevaluated hazards.
2 We should recall that, in the SRM for SECY 0124, "Recommended Actions to be Taken Without Delay from the Near
-Term Task Force Report," the Commission approved the staff's intent to issue a request for information to all operating reactor licensees to address, among other things, reevaluations of seismic and flooding hazards in accordance with Near
-Term Task Force (NTTF) Recommendation 2.1. The request for information, issued under the provisions of 10 CFR 50.54(f) on March 12, 2012, (§ 50.54(f) letter) stated that the hazard evaluation developed consistent with Recommendation 2.1 would be implemented in two phases. The first phase involved the reevaluation of the seismic and flooding hazards at all sites. In the second phase, the NRC staff was to determine, based upon the results of Phase 1, whether additional regulatory actions were necessary (e.g., updating the design basis and SSCs important to safety) to provide additional protection against the updated hazards.
As former Commissioner Apostolakis pointed out in his 2011 vote on the NTTF Report, "there is growing evidence that the historical record of tsunamis had not been used properly to determine the design basis at Fukushima Daiichi and, consequently, the protection of the plants was not sufficient." In the United States, there exists incontrovertible evidence that the current design bases for some plants do not address a flood hazard identified by the licensees' own analyses. Had the final rule been approved as proposed by the staff, the Commission's carefully crafted strategy would have dealt with this situation appropriately and effectively by requiring that the mitigation strategies for all sites be able to address the reevaluated hazards developed in response to the § 50.54(f) letters as a matter of adequate protection of the public health and safety. For plants with the most extreme exceedances from their current design basis, additional actions may have been necessary, but those decisions would only be made once their final flooding and/or seismic evaluations (e.g., integrated assessments or seismic PRAs) were completed. Absent a requirement in the MBDBE final rule to protect the mitigation strategies from the reevaluated hazard, the process for closing out NTTF Recommendation 2.1 and the § 50.54(f) letter for all plants will be made much more burdensome for both licensees and the NRC staff and the outcome with respect to protecting plants from beyond
-design-basis external events much more uncertain.
In addition, the majority's approach calls into question the degree to which the NRC will be able to give credit for the existence of the mitigation strategies in a number of risk
-informed regulatory initiatives like adaptation of alternative treatment requirements for SSCs under 10 CFR 50.69, "Risk
-informed categorization and treatment of structures, systems and components for nuclear power reactors," and risk
-informed technical specifications.
Licensees are also seeking credit for mitigation strategies in the Reactor Oversight Process and have expressed interest in pursuing credit for use of the strategies in the physical security program. The assessment of the degree to which credit for the mitigation strategies is possible will be much more complex now that the mitigation strategies will not be required to address the reevaluated hazards. Moreover, the decision to strip out the draft final rule requirements for an integrated response capability, as well as requirements for sufficient staffing levels, means of communication, and drills, also ignores primary lessons from the Fukushima Daiichi accident.
3 These requirements were approved by the Commission in the proposed rule, and nothing has occurred in the interceding years to change the need for these requirements to ensure a holistic approach to the response to beyond
-design basis accidents.
The decision of the Commission majority to reverse course now, when the lion's share of the actions that would be required under the rule have already been completed by industry, is baffling. It is difficult to understand how the arguments put forth of regulatory over
-reach are defensible with anyone who was at the agency when the accident occurred and has followed the activities of the agency, including the decisions made by the Commission, in the intervening years. It is equally baffling that some in the majority should lay the blame on the shoulders of the NRC staff for the perceived misapplication of the backfit r ule when the staff was merely following Commission direction in producing the draft final rule.
I would also point out that the changes reflected in the final rule are troubling in two other respects. First, the changes seem to be based in part on a presumption that the orders developed by staff and approved by the Commission in 2012 were a fully informed and complete regulatory solution to the Fukushima Daiichi accident. I do not mean to suggest that the Commission and the staff didn't implement thoughtful and effective solutions given what was known at the time. However, the orders were approved by the Commission just one year after the accident, and significant gaps still remained in the NRC's and industry's knowledge. To now suggest, as the majority has done, that the NRC could not improve upon the requirements of the orders or address these gaps in knowledge through this rulemaking makes little sense.
I am also troubled that the final rule eliminate s a substantial number of requirements that were included in the proposed rule for which no adverse public comments were received.
Finally, although I have long supported the NRC's pursuit of a rigorous application of its backfitting regulations and adherence to its Principles of Good Regulation, this pursuit must be rational. In defense of this rulemaking proposal, the staff produced appropriate backfitting and regulatory analyses, which were consistent with previous Commission direction. The majority has decided to reverse these previous Commission decisions and takes issue with the staff's supporting analysis based on little more than conclusory statements in Commission votes that some of the requirements in the draft final rule are not "necessary" or would not result in a "substantial increase in the overall protection of the public health and safety." Such a n approach is entirely inconsistent with the principles of clari ty, reliability, and openness that are supposed to drive this agency's work.
In the official report of the National Diet of Japan's Fukushima Nuclear Accident Independent Investigation Commission, Chairman Kiyoshi Kurokawa noted:
The earthquake and tsunami of March 11, 2011 were natural disasters of a magnitude that shocked the entire world. Although triggered by these cataclysmic events, the subsequent accident at the Fukushima Daiichi Nuclear Power Plant cannot be regarded as a natural disaster. It was a profoundly manmade disaster 4 - that could and should have been foreseen and prevented. And its effects could have been mitigated by a more effective human response.
The issuance of the NRC's final rule was meant to be the culmination of the agency's efforts to learn the lessons of the Fukushima Daiichi accident. Given the final form of the rule approved by the Commission majority, it will be difficult to convince others that the agency has learned those lessons well.