ML19008A094

01/23/2019 - Predecisional - Advisory Committee on Reactor Safeguards Sub-Committee Public Meeting Federal Register Notice for Non-Power Production or Utilization Facility License Renewal (Rin 3150-AI96, NRC-2011-0087)

ML19008A094
Person / Time
Issue date:	01/11/2019
From:	Annette Vietti-Cook NRC/SECY
To:
Beall, Robert
Shared Package
ML19008A088	List: ML19008A091 ML19008A092 ML19008A094 ML19008A095
References
NRC-2011-0087, RIN 3150-AI96
Download: ML19008A094 (76)

Text

This draft document is being released to support the January 23, 2019, Advisory Committee on Reactor Safeguards Sub-Committee public meeting. The NRC staff is not requesting or accepting public comments on this draft document. This draft document has not been subject to Commission, NRC management, and legal reviews and approvals, and its contents should not be interpreted as official agency positions.

Following the public meeting, the NRC staff plans to continue working on this document as well as other documents related to this rulemaking, and subsequently provide the documents to the Commission for approval in mid-2019.

[7590-01-P]

NUCLEAR REGULATORY COMMISSION 10 CFR Parts 2, 20, 26, 50, 51, 55, 73, 140, 170, and 171

[NRC-2011-0087]

RIN 3150-AI96 Non-Power Production or Utilization Facility License Renewal AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule and guidance; issuance.

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations that govern the license renewal process for certain production or utilization facilities. In this final rule, the NRC collectively refers to these facilities as non-power production or utilization facilities (NPUFs). In addition, this final rule revises the definitions of non-power reactor, research reactor, and testing facility. This final rule also eliminates license terms for licenses issued under the authority of Sections 104a or c of the Atomic Energy Act of 1954, as amended (AEA), other than for testing facilities; defines the license renewal process for licenses issued to testing facilities or under the authority of Section 103 of the AEA; requires all NPUF licensees to submit to the NRC final safety analysis report (FSAR) updates at intervals not to exceed 5 years; and provides an accident dose criterion of 1 Roentgen equivalent man (rem) (0.01 sievert

[Sv]) total effective dose equivalent (TEDE) for NPUFs other than testing facilities. This final rule also includes other changes, as described in Section II, Discussion, of this document.

DATES: This final rule is effective on [INSERT DATE 30 DAYS AFTER DATE OF PUBLICATION IN THE FEDERAL REGISTER].

ADDRESSES: Please refer to Docket ID NRC-2011-0087 when contacting the NRC about the availability of information for this action. You may obtain publicly-available information related to this action by any of the following methods:

• Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2011-0087. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415-3463; e-mail: Carol.Gallagher@nrc.gov. For technical questions, contact the individuals listed in the FOR FURTHER INFORMATION CONTACT section of this document.

• NRCs Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ADAMS Public Documents and then select Begin Web-based ADAMS Search. For problems with ADAMS, please contact the NRCs Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to pdr.resource@nrc.gov. For the convenience of the reader, instructions about obtaining materials referenced in this document are provided in the Availability of Documents section.

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• NRCs PDR: You may examine and purchase copies of public documents at the NRCs PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Robert Beall, Office of Nuclear Material Safety and Safeguards, telephone: 301-415-3874, e-mail: Robert.Beall@nrc.gov and Duane Hardesty, Office of Nuclear Reactor Regulation, telephone: 301-415-3724, e-mail: Duane.Hardesty@nrc.gov. Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION:

EXECUTIVE

SUMMARY

A. Need for the Regulatory Action In April 2008, the Commission issued Staff Requirements Memorandum (SRM)-M080317B, Briefing on State of NRC Technical Programs (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080940439),

which directed the staff to examine the license renewal process for non-power reactors and identify and implement efficiencies to streamline this process while ensuring that adequate protection of public health and safety are maintained. The need for improvement in the reliability and efficiency of the license renewal process was primarily driven by four issues: (1) historic NRC staffing and emergent issues; (2) limited licensee resources; (3) inconsistent existing license infrastructure; and (4) regulatory requirements and broad scope of the renewal process.

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B. Major Provisions The major provisions of this final rule include changes that:

• Create a definition for non-power production or utilization facility and revise the definitions for non-power reactor, testing facility, and research reactor;

• Eliminate license terms for facilities, other than testing facilities, licensed under title 10 of the Code of Federal Regulations (10 CFR) Section 50.21(a) or (c);

• Define the license renewal process for testing facilities licensed under

§ 50.21(c) and NPUFs licensed under § 50.22;

• Require all NPUF licensees to submit to the NRC an updated FSAR and subsequent FSAR updates at intervals not to exceed 5 years;

• Amend the current timely renewal provision under § 2.109, allowing NPUFs licensed under § 50.22 and testing facilities licensed under § 50.21(c) or § 50.22 to continue operating under an existing license past its expiration date if the facility submits a license renewal application at least 2 years (rather than 30 days) before the current license expiration date;

• Provide an accident dose criterion of 1 rem (0.01 Sv) TEDE for NPUFs other than testing facilities;

• Extend the applicability of § 50.59 to NPUFs regardless of their decommissioning status;

• Clarify an applicants requirements for meeting the existing provisions of § 51.45 for submitting an environmental report; and

• Eliminate the requirement for NPUFs to submit financial qualification information with license renewal applications under § 50.33(f)(2).

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Concurrent with this final rule, the NRC is issuing Regulatory Guide (RG) 2.7, Revision 0, Preparation of Updated Final Safety Analysis Reports for Non-power Production or Utilization Facilities.

C. Costs and Benefits The NRC prepared a final regulatory analysis to determine the expected quantitative costs and benefits of this final rule and the final implementing guidance, as well as qualitative factors to be considered in the NRCs rulemaking decision. Based on the analysis, the NRC concluded that this final rule will result in net savings to licensees and the NRC (i.e., be cost beneficial). The analysis examined the benefits and costs of the final rule requirements and the final implementing guidance compared to the baseline for the current license renewal process (i.e., the no action alternative).

Compared to the no action baseline, the NRC estimates that total net benefits to NPUFs (i.e., cost savings minus costs) will be $5.5 million ($2.6 million using a 7 percent discount rate and $3.9 million using a 3 percent discount rate) over a 20-year period.

The average NPUF will incur net benefits ranging from approximately $78,000 to

$166,000 over a 20-year period. The NRC will incur total net benefits of $12 million

($5.9 million using a 7 percent discount rate and $8.6 million using a 3 percent discount rate) over a 20-year period.

The final regulatory analysis also considered, in a qualitative fashion, additional benefits of this final rule and the final implementing guidance associated with regulatory efficiency, protection of public health and safety, promotion of the common defense and security, and protection of the environment.

The final regulatory analysis concluded that this final rule and the final implementing guidance are justified because of the cost savings incurred by both licensees and the NRC while public health and safety is maintained. For a detailed 5

discussion of the methodology and complete results, see Section VII, Regulatory Analysis, of this document.

TABLE OF CONTENTS:

I. Background II. Discussion III. Opportunity for Public Participation IV. Public Comment Analysis V. Section-by-Section Analysis VI. Regulatory Flexibility Certification VII. Regulatory Analysis VIII. Backfitting and Issue Finality IX. Cumulative Effects of Regulation X. Plain Writing XI. Environmental Assessment and Final Finding of No Significant Environmental Impact XII. Paperwork Reduction Act XIII. Congressional Review Act XIV. Criminal Penalties XV. Availability of Guidance XVI. Availability of Documents I. Background Sections 103 (for facilities used for commercial or industrial purposes) and 104a and c (for facilities used for medical therapy and useful for research and development activities, respectively) of the AEA establish the NRCs authority to license NPUFs. The section of the AEA that provides licensing authority for the NRC corresponds directly to the class of license issued to a facility (e.g., Section 104a of the AEA authorizes the issuance of a class 104a license). Sections 104a and c of the AEA require that the Commission impose only the minimum amount of regulation needed to promote the common defense and security; protect the health and safety of the public; and permit, under Section 104a, the widest amount of effective medical therapy possible and, under Section 104c, the conduct of widespread and diverse research and development.

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The NRC regulates 36 NPUFs, of which 31 are currently operating. Two of the other five facilities have been issued construction permits and the other three facilities are in the process of decommissioning (i.e., removing a facility or site safely from service and reducing residual radioactivity to a level that permits release of the site for unrestricted use or use under restricted conditions). Most NPUFs are located at universities or colleges throughout the United States. The NRC regulates one operating testing facility.

A. License Terms The AEA dictates an initial license term of no more than 40 years for class 103 facilities, which the NRC licenses under § 50.22, but the AEA does not specify license terms for class 104a or c facilities, which are licensed under § 50.21(a) or (c). The regulation that implements this statutory authority, § 50.51(a), currently specifies that the NRC may grant an initial license for NPUFs for no longer than a 40-year license term. If the NRC initially issues a license for a shorter period, then it may renew the license by amendment for a maximum aggregate period not to exceed 40 years. An NPUF license is usually renewed for a term of 20 years. If the requested renewal would extend the license beyond 40 years from the date of issuance, the original license may not be amended. Rather, the NRC issues a superseding renewed license.

Any application for license renewal or a superseding renewed license must include an FSAR describing: 1) changes to the facility or facility operations resulting from new or amended regulatory requirements, and 2) changes and effects of changes to the facility or procedures and new experiments. The FSAR must include the elements specified in § 50.34 and should be augmented by the guidance of NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Format and Content, Part 1 (ADAMS Accession No. ML042430055). The 7

NRC reviews NPUF initial and renewal license applications according to NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Standard Review Plan and Acceptance Criteria, Part 2 (ADAMS Accession No. ML042430048).

As a license term nears its end, a licensee must submit a license renewal application in order to continue operations. Per § 2.109(a), referred to as the timely renewal provision, if, at least 30 days before the expiration of an existing license, the licensee files an application for a renewal or for a new license for the authorized activity, the existing license will not be deemed to have expired until the application has been finally determined.

B. Need for Improvement in the License Renewal Process In 2008, the NRC recognized a need to identify and implement efficiencies in the NPUF license renewal process to streamline the process while ensuring that adequate protection of public health and safety is maintained. Four issues primarily drove this need for improvement in the reliability and efficiency of the process:

1. Historic NRC Staffing and Emergent Issues NPUFs were some of the first reactors licensed by the Atomic Energy Commission (AEC) and the first reactors to face license renewal. Most of these reactors were initially licensed in the late 1950s and 1960s for terms that varied from 10 to 40 years. The AEC started renewing these licenses in the 1960s. License renewal was primarily an administrative activity until 1976, when the NRC decided to also conduct a technical review which was equivalent to the initial licensing of the facility. The licenses with initial 20-year terms were due for renewal during this timeframe. As the NRC started developing methods for conducting these technical reviews, an accident occurred at the Three Mile Island (TMI) nuclear power plant.

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The NRCs focus on post-TMI activities resulted in a suspension of NPUF license renewal activities for several years. After license renewal activities were restarted, the NRC issued a number of renewals in a short period of time primarily by relying on generic evaluations. These were 20-year renewals that expired starting in the late 1990s. The original 40-year licenses also started expiring in the late 1990s. These two groups of renewals were coming due in a short period of time and created a new surge of license renewal applications.

In response to the security initiatives identified following the terrorist attacks of September 11, 2001, the NRC redirected its staff from processing the license renewal applications that were received in the late 1990s to addressing security items. In addition, the NRC was focused on implementing § 50.64 to convert non-power reactor licensees to the use of low-enriched uranium.

2. Limited Licensee Resources Many NPUF licensees have limited staff resources available for licensing support. The number of NPUF staff available for licensing can range from one part-time employee for some low-power facilities to four or five people for higher-power facilities.

The NPUF staff that perform the licensing function typically do so in addition to their normal organizational responsibilities, which often results in delays (particularly in responding to the NRCs requests for additional information (RAIs)) in the license renewal process.

3. Inconsistent Existing License Infrastructure The NPUFs licensed under § 50.21(a) or (c) primarily comprise college and university sites. Staff turnover and limited staffing resources at an NPUF often contribute to a lack of historical knowledge of the development of the licensees FSAR and changes to the FSAR. During the most recent round of license renewals, the NRC found that some of the submitted FSARs did not adequately reflect the current licensing 9

basis for the respective licensees. Because the only required FSAR submission comes at license renewal, which can be at 20-year or greater intervals, submitted FSARs often contain varying levels of completeness and accuracy. Consequently, the NRC must issue RAIs to obtain missing information, seek clarifications and corrections, and document the current licensing bases.

4. Regulatory Requirements and Broad Scope of the Renewal Process For power reactors, license renewal reviews have a defined scope, primarily focused on aging management, as described in 10 CFR part 54. For NPUFs, there are no explicit requirements on the scope of issues to be addressed during license renewal.

Therefore, the scope of review for license renewal was initially treated the same as that for an original license.

In response to Commission direction in the Staff Requirements Memorandum (SRM) to SECY-91-061, Separation of Non-Reactor and Non-Power Reactor Licensing Activities from Power Reactor Licensing Activities in 10 CFR Part 50, the NRC developed licensing guidance for the first time since many NPUF applicants were originally licensed. In that guidance (NUREG-1537, Parts 1 and 2), the NRC provides detailed descriptions of the scope, content, and format of FSARs and the NRCs process for reviewing initial license applications and license renewal applications. However, at the time of the first license renewals using NUREG-1537, some license renewal applications had varying levels of consistency with NUREG-1537. These licensees did not propose an acceptable alternative to the guidance.

C. NRC Response to These Issues As a result of these issues, a backlog of NPUF license renewal applications developed and persisted. The Commission and other stakeholders voiced concerns not only about the backlog, but also about the burdensome nature of the process itself. The 10

Commission issued SRM-M080317B, Briefing on State of NRC Technical Programs, in April 2008, which directed the NRC staff to examine the license renewal process for non-power reactors and identify and implement efficiencies to streamline this process while ensuring that adequate protection of public health and safety are maintained.

In October 2008, the NRC staff provided the Commission with plans to improve the review process for NPUF license renewal applications in SECY-08-0161, Review of Research and Test Reactor License Renewal Applications. In SECY-08-0161, the NRC staff discussed stakeholder feedback on the current process, including ways it could be improved and the options the NRC staff was considering for improving the review process. The NRC staff provided a detailed description of five options for streamlining the NPUF license renewal process:

• The alternate safety review approach would limit the review of license renewal applications to changes to the facility since the previous license review occurred, compliance with the current regulations, and the inspection process.

• The graded approach would base the areas of review on the relative risk associated with the facility applying for a renewed license. The graded approach would ensure safe operation by properly identifying the inherent risk associated with the facility and ensuring those risks are minimized.

• The generic analysis approach would require the NRC to review and approve a generic reactor design similar to the NRC topical report process. The NRC would rely on the previously approved generic analysis and would not reanalyze those items for each licensee.

• The generic siting analysis approach would require the NRC to develop a generic communication that contains information related to each of the licensee sites.

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The licensees could then reference this generic communication in their license renewal submittals.

• The extended license term approach would permit extended or indefinite terms for NPUF licenses. The NRC staff described this approach in SECY-08-0161:

In order to permit an extended term (including possibly an indefinite term),

the NRC staff would have to explain why it is appropriate and, more importantly, demonstrate that there are no aging concerns.

Environmental conditions such as temperature, pressure and radiation levels in most [research and test reactors (RTRs)] are not significant.

With surveillance, maintenance and repair, RTRs can have indefinite lives. For a facility to be eligible for an extended license term, the NRC staff would complete a detailed renewal with a licensing basis reviewed against NUREG-1537. To maintain the licensing basis over time, the NRC staff would propose a license condition or regulation that requires licensees to revise their SARs on a periodic basis such as every 2 years.

The inspection program would be enhanced to place additional focus on surveillance, maintenance and repair, and changes to the facility made under 10 CFR 50.59. The licensee would still be required to adhere to changes in the regulations.

The Commission issued SRM-SECY-08-0161, Review of Research and Test Reactor License Renewal Applications, in March 2009, which instructed the NRC staff to proceed with several actions. The Commission directed NRC staff to: 1) immediately implement short-term program initiatives to address the backlog of license renewal applications; 2) work with the regulated community and other stakeholders to develop an interim streamlining process to focus the review on the most safety-significant aspects of the license renewal application; and 3) streamline the review process to ensure that it becomes more efficient and consistent, thereby reducing uncertainties in the process while ensuring compliance with regulatory requirements.

As part of its direction to develop the program initiatives, the Commission instructed the NRC staff to implement a graded approach commensurate with the risk posed by each facility, incorporate elements of the alternate safety review approach, and use risk insights from security assessments to inform the dose threshold. In addition, 12

the Commission told the NRC staff to develop an interim staff guidance (ISG) document that employs the graded approach to streamline the license renewal application process.

Lastly, the Commission instructed the NRC staff to submit a long-term plan for an enhanced NPUF license renewal process. The Commission directed that the plan include development of a basis for redefining the scope of the process as well as a recommendation regarding the need for rulemaking and guidance development.

The NRC staff responded to Commission direction by implementing short-term actions to address the license renewal application backlog and developing ISG-2009-001, Interim Staff Guidance on the Streamlined Review Process for License Renewal for Research Reactors, hereafter referred to as the ISG. The ISG called for employing a graded approach to streamline the license renewal application process. Since October 2009, the NRC has reviewed license renewal applications according to the streamlined review process presented in the ISG. The ISG identified the three most safety-significant sections of an FSAR: reactor design and operation, accident analysis, and technical specifications. The NRC also has reviewed the licensees radiation protection and waste management programs, and compliance with financial requirements. The ISG divided facilities into two groups: 1) those facilities with licensed power of less than 2 megawatts thermal (MWt), which would undergo a limited review focusing on the safety-significant aspects, considering the decisions and precedents set by past NRC reviews; and 2) those facilities with licensed power of 2 MWt and greater, which would undergo a full review using NUREG-1537, Part 2. The process outlined in the ISG facilitated the NRCs review of license renewal applications and enabled the NRC to review applications in a more timely manner.

In addition, the NRC staff issued SECY-09-0095, Long-Term Plan for Enhancing the Research and Test Reactor License Renewal Process and Status of the Development and Use of the Interim Staff Guidance, in June 2009 to provide the 13

Commission with a long-term plan for enhancing the NPUF license renewal process. In the long-term plan, the NRC staff proposed to develop a draft regulatory basis to support proceeding with rulemaking to streamline and enhance the NPUF license renewal process. The Commission issued SRM-M090811, Briefing on Research and Test Reactor (RTR) Challenges, in August 2009, which directed NRC staff to accelerate the rulemaking to establish a more efficient, effective, and focused regulatory framework.

D. 2012 Regulatory Basis In August 2012, the NRC staff completed the Regulatory Basis to Support Proceeding with Rulemaking to Streamline and Enhance the Research and Test Reactor (RTR) License Renewal Process, hereafter referred to as the regulatory basis.1 The regulatory basis analyzed the technical, legal, and policy issues; impacts on public health, safety, and security; impacts on licensees; impacts on the NRC; stakeholder feedback; as well as other considerations, and concluded that a rulemaking was warranted. In developing the regulatory basis for rulemaking, the NRC staff considered lessons learned as a result of implementation of the streamlined review process outlined in the ISG. A public meeting was held on August 7, 2014, to discuss the regulatory basis and rulemaking options. The NRC held another public meeting on October 7, 2015, to afford stakeholders the opportunity to provide feedback and comment on preliminary proposed rule concepts. The participants provided comments and questions to the NRC that focused on the potential impacts of eliminating license terms, the scope of reviews under the new process, and how this new change in 1

At the time of publication of the regulatory basis, the rulemaking title was Non-Power Reactor (NPR)

License Renewal Rulemaking. During the development of the proposed rule, the scope of the rulemaking expanded to include recent license applicants (e.g., medical radioisotope irradiation and processing facilities) that are not reactors. In order to encompass all affected entities, the NRC has changed the title of the rulemaking to Non-power Production or Utilization Facility License Renewal Rulemaking.

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regulation would work compared to the current license renewal process. The NRC considered those comments in developing the proposed rule.

E. 2017 Proposed Rule On March 30, 2017, the NRC published a proposed rule, Non-Power Production or Utilization Facility License Renewal, in the Federal Register (82 FR 15643). The proposed rule included provisions to eliminate license terms for licenses issued under the authority of Sections 104a or c of the AEA, other than for testing facility licenses; define the license renewal process for licenses issued to testing facilities or under the authority of Section 103 of the AEA except for power reactor licenses; require all NPUF licensees to submit FSAR updates to the NRC every 5 years; and provide an accident dose criterion of 1 rem (0.01 Sv) TEDE for NPUFs other than testing facilities. The public comment period to review and comment on the proposed rule and associated guidance was 75 days.

II. Discussion This final rule: 1) creates a definition for non-power production or utilization facility, and revises the definitions for non-power reactor, research reactor, and testing facility; 2) eliminates license terms for facilities, other than testing facilities, licensed under § 50.21(a) or (c); 3) defines the license renewal process for testing facilities licensed under § 50.21(c) and all NPUFs licensed under § 50.22; 4) requires all NPUF licensees to submit to the NRC an updated FSAR and subsequent FSAR updates at intervals not to exceed 5 years; 5) amends the current timely renewal provision under

§ 2.109, allowing NPUFs licensed under § 50.22 and testing facilities licensed under § 50.21(c) or § 50.22 to continue operating under an existing license past its expiration date if the facility submits a license renewal application at least 2 years before the 15

current license expiration date; 6) provides an accident dose criterion of 1 rem (0.01 Sv)

TEDE for NPUFs other than testing facilities; 7) extends the applicability of § 50.59 to NPUFs regardless of their decommissioning status; 8) clarifies the requirements for NPUFs to meet the existing provisions of § 51.45; and 9) eliminates the requirement to submit financial qualification information with license renewal applications under § 50.33(f)(2).

This final rule enhances the effectiveness and efficiency of the NPUF license renewal process, consistent with the AEAs criterion for imposing minimum regulation on facilities of these types. This final rule:

1. Creates a definition for non-power production or utilization facility and revises the definitions for non-power reactor, research reactor, and testing facility.

This final rule addresses inconsistencies in definitions and terminology throughout 10 CFR Chapter I to improve clarity in determining the applicability of the regulations associated with NPUFs. For example, before this final rule, the existing definitions for non-power facilities (e.g., non-power reactor, research reactor, testing facility) did not adequately cover new entities like SHINE Medical Technologies, Inc.s (SHINEs) proposed accelerator-driven subcritical operating assemblies or other medical radioisotope irradiation and processing facilities. The final rule definition for non-power production or utilization facility is more inclusive and allows that not all NPUFs are non-power reactors.

The NRC received public comments on the proposed definition of non-power production or utilization facility. In reviewing the comments, the NRC identified that the proposed definition for non-power production or utilization facility was too broad for defining production facilities that are NPUFs. Previously, the definition excluded fuel reprocessing plants, but did not address a needed exclusion for a production facility designed or used primarily for the formation of plutonium or uranium-233 or designed or 16

used for the separation of the isotopes of plutonium. Accordingly, the NRC revised the definition for non-power production or utilization facility to exclude all production facilities as defined under paragraphs (1) and (2) of the definition of production facility in § 50.2. Production facilities of the type defined under paragraph (1) of the definition of production facility in § 50.2 are not considered NPUFs because these facilities have been owned by the U.S. Department of Energy and have not been NRC licensees. If such a facility were to be licensed by NRC, it would be licensed under §§ 50.21(c) or 50.22 consistent with the provisions of the AEA for production reactors. Production facilities as defined under paragraph (2) of the definition of production facility in § 50.2 are not NPUFs because these facilities have a higher potential radiological risk to the environment and the public than NPUFs (e.g., an inventory of high-level liquid radioactive wastes). This higher risk is evidenced by the applicability to these facilities of NRC regulations in appendix B to part 50, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants and appendix F to part 50, Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities. In response to these comments, the NRC revised the definition of non-power production or utilization facility to exclude production facilities designed or used primarily for the formation of plutonium or uranium-233 or the separation of the isotopes of plutonium.

The NRC also received a public comment from the National Institute of Standards and Technology (NIST) on the definition of testing facility in § 50.2 and research reactor in § 171.11(b)(2). The commenter recommended that the NRC revise the definitions of testing facility and research reactor to remove the arbitrary 10MW(t) threshold, and apply instead a risk-based approach to its regulation of a testing facility.

Further, the commenter stated, This risk is best quantified by accident analyses performed under a licensing safety analysis and linked the recommended definition to the NRCs accident dose criterion of 1 rem (0.01 Sv) in the proposed rule.

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The technical basis associated with the 10 MW(t) threshold under the current definition for testing facility, while generally based on safety significance, is not documented. Similarly, the technical basis for the 1 MW(t) threshold (coupled with specific design features) under the current definition for testing facility is also not documented. These prescriptive power thresholds do not account for the safety features that are engineered into the facility design and those barriers that must be breached during an accident before a release of radioactive material to the environment can occur.

Therefore, these thresholds do not accurately represent the risk associated with a particular facility. For these reasons, the use of a postulated accident dose is a more risk-informed, performance-based approach than using the power level of the reactor for distinguishing between types of NPUFs, such as research reactors and testing facilities.

As a result of this public comment, the NRC revised the definitions of testing facility and research reactor to reflect this risk-informed approach.

Additionally, the NRC made conforming changes to the definitions of testing facility, research reactor, and non-power reactor wherever these definitions appear throughout 10 CFR Chapter I. Before this final rule, the regulations referred to many types of facilities that are categorized as NPUFs in this final rule, such as non-power reactor, research reactor, training reactor, testing reactor, testing facility, and critical assembly. The NRC reviewed each instance of these various terms in 10 CFR Chapter I. Where appropriate, the NRC added, corrected, or standardized the terminology and definitions (e.g., replacing the term test reactor with testing facility in § 171.15).

However, the NRC did not change the definition of research reactor in § 170.11(a)(9) or 171.11(b)(2). The definition in § 171.11(b)(2) is based on the language of the Omnibus Budget Reconciliation Act of 1990 (OBRA-90), a statutory requirement imposed by Congress. Changing the definition of research reactor in § 171.11(b)(2) would require Congress to change the legislation. The definition of research reactor in 18

§ 170.11(a)(9) is not based on OBRA-90, but changing that definition would be more than just a conforming change and, as such, would be beyond the scope of this final rule.

Where appropriate, this final rule standardizes the terminology in other parts of the regulations to modify the intended scope of regulations citing research and test reactors to be either non-power reactors or non-power production or utilization facilities. For example, this final rule changes research and test reactors to non-power production or utilization facilities in appendix E to part 50, Emergency Planning and Preparedness for Production and Utilization Facilities, while in § 55.40 this final rule changes test and research reactors to non-power reactors. Also, where appropriate, the final rule changes the uses in other parts of the regulations for testing facility, research reactor, and non-power reactor to reference only one definition in the part where that definition is used most, unless the specific meaning is needed and different for a given part. In addition, the final rule adds the definition of non-power reactor as it is defined in § 50.2 to the definitions section in 10 CFR part 73 because the term is used many times throughout the part. These changes increase clarity by defining for all NPUF-related terms where used in the regulations, while removing the possibility of unintended consequences of possible errors caused by variations in definitions.

This final rule also revises the definition of non-power reactor to clarify the nomenclature used to distinguish between non-power reactors used for research and development activities and non-power reactors used for commercial or industrial purposes. Before this final rule, all non-power reactors were defined as either research or test reactors licensed under § 50.21(c) or § 50.22 for research and development. The final rule clarifies that a non-power reactor useful in the conduct of research and development activities of the types specified in section 31 of the AEA, and which is not a facility of the type specified in § 50.21(b) or in § 50.22, would be licensed as either a 19

research reactor or testing facility, as applicable, under § 50.21(c). Additionally, a non-power reactor used so that more than 50 percent of the annual cost of owning and operating the facility is devoted to the production of materials, products, or energy for sale or commercial distribution, or to the sale of services, other than research and development or education or training would be licensed as either a commercial or industrial reactor or a testing facility, as applicable, under § 50.22.

2. Eliminates license terms for facilities, other than testing facilities, licensed under § 50.21(a) or (c).

The final rule language in § 50.51(c) eliminates license terms for facilities, other than testing facilities, licensed under § 50.21(a) or (c). Before this final rule, § 50.51(a) stated, Each license will be issued for a fixed period of time to be specified in the license but in no case to exceed 40 years from date of issuance. This included all facility licenses issued under 10 CFR part 50, including for facilities, other than testing facilities, licensed under § 50.21(a) or (c). However, the AEA does not establish specific license terms nor the need for license terms for these types of facilities.

Historically, license renewal afforded both the NRC and the public the opportunity to re-evaluate the licensing basis of the NPUF. The purpose of license renewal was to assess the likelihood of continued safe operation of the facility to ensure the safe use of radioactive materials for beneficial civilian purposes while protecting people and the environment and ensuring the common defense and security. For several reasons that are unique to NPUFs, this objective can be achieved through existing oversight activities and review of updated FSARs and subsequent FSAR updates submitted pursuant to the new requirements in § 50.71(e) of the final rule language (see Section II.4. of this document). This approach is consistent with the NRCs overall program to make licensing more efficient and effective and will implement and reflect lessons learned from 20

decades of processing license renewal applications. The NRC reached this conclusion based on the following three considerations.

First, compared to power reactors, the NPUFs licensed under § 50.21(a) or (c),

other than testing facilities, operate at low power levels, temperatures, and pressures, and have a small inventory of fission products in the fuel. Therefore, these NPUFs present a lower potential radiological risk to the environment and the public.

Additionally, the consequences of the maximum hypothetical accidents (MHAs) for these facilities fall below the standards in 10 CFR part 20 for protecting the health and safety of the public.

Of the 30 currently licensed NPUFs eligible for non-expiring licenses, 262 have cores that are submerged in tanks or pools of water that provide sufficient passive decay heat removal to prevent overheating of the fuel. Of these 26 licensed facilities, 24 are not required to have emergency core cooling systems (ECCSs) because analysis has shown that air cooling is sufficient to remove decay heat if the water is not present.

These NPUFs do not generate enough decay heat, even after extended operation at maximum licensed power, to be a risk for overheating, failure of a fission product barrier, or posing a threat to public health and safety, even in a loss-of-coolant accident where water levels drop below the core. Additionally, many of the facilities monitor for leaks using routine inspections, tracking and trending water inventory, and performing surveillance on installed pool-level instrumentation and sensors. Licensees perform analyses for radioisotope identification of primary and, if applicable, secondary coolant by sampling the water periodically. Many facilities sample weekly for gross radioactive material content, which is also used to establish trends to quickly identify fuel or heat 2 The three Aerojet-General Nucleonics (AGN) reactors (University of New Mexico (Docket No. 50-252),

Idaho State University (Docket No. 50-284), and Texas A&M University (Docket No. 50-59)), each rated at 5-watts, and the University of Florida Argonaut reactor (Docket No. 50-83), rated at 100 kilowatts, are not considered tank or pool reactors but have similarly low risk profiles.

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exchanger failure. Most of these licensees analyze, in their FSARs, pool and heat exchanger failures and the potential consequences for the safety of the reactor, workers, and public. In general, the radioisotope concentrations in pool or tank water at NPUFs are within the effluent concentration limits specified in appendix B to 10 CFR part 20, and therefore are not radiologically significant.

Only two of the NPUFs eligible for non-expiring licenses are required by their safety analyses to have an ECCS to maintain core cooling in the highly unlikely case that a loss-of-coolant accident uncovers the core. For these NPUFs,3 the ECCS is needed only to direct flow into the top of the tank or pool to provide cooling for a limited time after reactor shutdown. This period of time depends on the recent operational history of the reactor, which determines the decay heat present at reactor shutdown.

After this relatively brief time, air cooling is adequate to remove decay heat without the ECCS. Additionally, required surveillance and testing of the ECCS at these facilities help ensure the performance of the system. Operation of the facility is not permitted if the ECCS has not been verified to be operable before reactor startup or if the system is deemed inoperable during reactor operation.

Second, these facilities simple design and operation yield a limited scope of aging-related concerns. The NRC has found no significant aging issues at the time of license renewal because the NRC currently imposes aging-related surveillance requirements on NPUFs via technical specifications, as needed. Aging of components is specifically addressed in the standard review plan and acceptance criteria used for evaluating license renewal applications (i.e., NUREG-1537, Part 2). Parts 1 and 2 of NUREG-1537 document lessons learned and known aging issues from prior reviews. Since NUREG-1537 was published in 1996, NRC reviews and assessments 3 The two facilities are Massachusetts Institute of Technology (MIT) (Docket No. 50-20) and the University of California/Davis (Docket No. 50-607).

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have not revealed any additional issues or need to update the NUREG. Specifically, based on operating experience over the past 60 years and review of license renewal applications over the past 40 years, and as documented in NUREG-1537, Parts 1 and 2, the NRC has determined that for NPUFs, two main areas related to aging could need surveillance because of potential safety concerns: 1) fuel cladding and 2) instrumentation and control features.

With regard to fuel cladding, the NRC currently requires NPUFs to perform periodic fuel inspections. Through years of operational experience, the NRC has found that aging-related fuel failures either do not occur or do not release significant amounts of fission products and are quickly detected by existing monitoring systems and surveillances. If fuel failures are detected, licensees are able to take the facility out of service without delay and remove any failed assemblies from service.

With regard to instrumentation and control, the NRC has found that failures in this area result in automatic facility shutdown. Failures reveal themselves to the licensee and do not prevent safe shutdown. Over the past 60 years of operation of these facilities, the potential occurrence of age-related degradation has been successfully mitigated through inspection, surveillance, monitoring, trending, recordkeeping, replacement, and refurbishment. In addition, licensees are required to report preventive and corrective maintenance activities in their annual reports, which are reviewed by the NRC. This allows the NRC to identify new aging issues if they occur.

Therefore, the NRC has concluded that existing requirements and facility design and operational features will address concerns over aging-related issues during a non-expiring license term.

Third, the design bases of these facilities evolve slowly over time, with approximately five license amendment requests from all NPUF licensees combined each 23

year and, on average, only five § 50.59 evaluations per facility per year for changes that do not require prior NRC approval.

Given these considerations, the elimination of license terms for NPUFs licensed under § 50.21(a) or (c), other than testing facilities, combined with the addition of requirements for periodic FSAR submittals, will have a positive effect on safety. The requirements in the final rule language in § 50.71(e) for licensees to submit updated FSARs and subsequent FSAR updates will ensure that facilities licensing bases are kept up-to-date, a major function previously provided by the license renewal process, while imposing significantly less burden on licensees. Eliminating license terms for these licensees will allow the NRC to focus its resources on oversight of these facilities, such as conducting routine inspection activities and reviewing annual reports and FSAR updates. Recurring FSAR updates by licensees and reviews by the NRC will provide for maintenance of the facilitys licensing basis and provide reasonable assurance that a facility will continue to operate without undue risk to public health and safety or to the environment and without compromising the facilitys security posture. Should the NRC identify potential issues with the facilitys continued safe operation in its reviews of FSAR updates, the Commission can undertake regulatory actions specified in § 2.202 to modify, suspend, or revoke a license. In addition, the public will remain informed about facility operations through the publicly available FSAR submittals and will continue to have opportunities for participation through licensing actions and the § 2.206 petition process. By eliminating license terms and requiring periodic FSAR update submittals coupled with existing oversight processes, the NRC will reduce the burden on the affected licensees and the NRC, which is consistent with the AEA and supports the NRCs efforts to make licensing more efficient and effective.

Licenses of existing NPUFs licensed under § 50.21(a) or (c), other than testing facilities, will be modified by order to remove the license term after the effective date of 24

this final rule (see Section II.4. of this document). Facilities licensed under § 50.21(a) or (c), other than testing facilities, that have undergone relicensing using the guidance in NUREG-1537, Part 2 will be eligible to receive a non-expiring license without again renewing the current license. The NPUF licensees that have not undergone the license renewal process using the guidance in NUREG-1537, Part 2, will each need to submit an application for license renewal if they wish to continue facility operation beyond the current license term. The NRC will review the application using NUREG-1537, Part 2, and the ISG, as appropriate. If the NRC concludes that a licensees application meets the standard for issuing a renewed license, then the licensee will receive a non-expiring renewed license.

This final rule made conforming changes to requirements for facilities that are decommissioning by revising § 50.82(b) and (c). These provisions address license termination applications and collection periods for shortfalls in decommissioning funding for NPUFs. This final rule clarifies that NPUFs licensed under § 50.22 and testing facilities licensed under § 50.21(c) are the only NPUFs with license terms, which the NRC uses to determine when an application for license termination is needed. The NPUFs licensed under § 50.21(a) or (c) will still need to submit an application for license termination within 2 years following permanent cessation of operations.

3. Defines the license renewal process for testing facilities and NPUFs licensed under § 50.22.

For all NPUF licenses issued under § 50.22 and testing facility licenses issued under § 50.21(c), the NRC establishes a set of regulations explicitly defining the license renewal process in § 50.135 that consolidates in one section existing regulatory requirements (i.e., requirements regarding written communications, application filing, application contents, and the issuance of renewed licenses) for current and future licensees. This final rule does not impose new regulations on these facilities. The NRC 25

also made a conforming change to § 50.8 to reflect the approved information collection requirement of § 50.135.

Section 103 of the AEA establishes a license term of no more than 40 years for

§ 50.22 facilities. Although the AEA does not establish a fixed license term for testing facilities, these facilities are currently subject to additional license renewal requirements (e.g., siting subject to 10 CFR part 100, Advisory Committee on Reactor Safeguards

[ACRS] review, and environmental impact statements) because of their design, operation, or use and the associated risk of testing facilities as compared to other class 104a or c licensees. Therefore, all NPUF licensees under § 50.22 and testing facility licensees under § 50.21(c) will continue to have fixed license terms and undergo license renewal.

The NRC is making renewed operating licenses for these facilities effective immediately upon the date of issuance, replacing the previous operating license. The applicant for the renewed license can propose a schedule for implementation of the renewed licensee to the extent that additional time is needed to make any necessary and conforming changes to the facility processes and procedures required by the applicable conditions of the renewed license. The NRC will review and, upon approval, make the schedule a condition of the renewed license. The immediate effectiveness of the renewed license is a change from the proposed rule, which would have made the renewed license effective 30 days after issuance. This final rule provides a substantively similar result as the proposed rule and allows the NRC to provide licensees additional flexibility in the timing of their implementation of the renewed license.

If administrative or judicial appeal affects the renewed license, then the previous operating license will be reinstated unless its term has expired and the facility has failed to submit a license renewal application in a timely manner according to § 50.135(c)(2).

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During the development of the final rule, the NRC recognized that § 50.135(e)(2) in the proposed rule could have unnecessarily restricted the license term for a renewed NPUF license to less than 40 years. Section 103 of the AEA allows for license terms of up to 40 years. To address this issue, the final rule clarifies that renewed licenses are issued for a fixed period of time, not to exceed 40 years.

4. Requires all NPUF licensees to submit to the NRC updated FSARs and subsequent FSAR updates at intervals not to exceed 5 years.

Maintaining up-to-date FSARs is important for licensees to manage their facilities safely, including changes in the licensing bases and training of personnel, and for the NRC to effectively fulfill its statutory obligations and regulatory responsibilities. The final rule requires all NPUF licensees to submit to the NRC updated FSARs and subsequent FSAR updates at intervals not to exceed 5 years according to § 50.71(e). The updated FSAR will incorporate the various supplements and amendments that may have been submitted either in response to NRC questions or on the licensees own initiative following the original submittal to create a single and complete updated document that can then serve as the baseline for future changes. By requiring periodic submittals of subsequent FSAR updates, the NRC anticipates that licensees will document changes in licensing bases as they occur, which will maintain the continuity of knowledge both for the licensee and the NRC and the understanding of changes and effects of changes on the facility. The NRC anticipates that these changes will result in minimal additional burden on licensees and the NRC, largely because licensees are currently required by § 50.59 to keep FSARs up to date and the number of changes per facility per year has been low historically.

This final rule requires licensees to submit, in accordance with § 50.4, a complete updated FSAR within 5 years of receipt of a facility operating license (§ 50.71(e)(3)(iv))

and subsequent FSAR updates at successive intervals not to exceed 5 years (§ 27

50.71(e)(4)(ii)). Existing facilities licensed under § 50.21(c) that have undergone the license renewal process using the guidance in NUREG-1537, Part 2, will receive licensee-specific orders to submit their updated FSARs, after which they will be subject to the new requirement in § 50.71(e)(4)(ii) to submit subsequent FSAR updates.

For the purpose of issuing the licensee-specific orders, the NRC will group the facilities by whether they have undergone license renewal using NUREG-1537 or, for more recent renewals, both NUREG-1537 and the ISG. The orders will dictate when the licensees initial updated FSAR will be due to the NRC and these dates will be staggered over a five-year period following the effective date of this final rule. The NRC will place existing NPUF licensees in three groups as follows:

1) Group 1 consists of licensees that completed the license renewal process using NUREG-1537, Part 2 and the ISG. The NRC will establish a due date for the updated FSAR that will be at least 1 year and no later than 3 years from the effective date of this final rule. The NRC will require these licensees to submit an updated FSAR first because, with a recent license renewal, the FSARs should require minimal updates.

2) Group 2 licensees are those for which the NRC reviewed the license renewal application using NUREG-1537, Part 2. The NRC will establish a due date for the updated FSAR that will be at least 2 years and no later than 5 years from the effective date of this final rule. The NRC will allow these licensees more time to submit an updated FSAR than Group 1 licensees because more time has passed since Group 2s most recent license renewals, so additional time may be needed to update their FSARs.

3) Group 3 consists of the remaining NPUF licensees that have not undergone license renewal using NUREG-1537 or NUREG-1537 and the ISG. The licenses for these facilities are all due to expire in less than 5 years from the effective date of this final rule. If these licensees choose to renew their facility operating licenses, they will be subject to the requirements in § 50.71(e) after issuance of the renewed license.

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The general approach will be to stagger the submittal dates within Groups 1 and 2 such that licensees that most recently completed license renewal will be the first to submit the updated FSAR. However, the licensee-specific orders will also consider facility-specific circumstances and NRC discretion.

This final rule also corrected a grammatical error in footnote 1 to § 50.71(e). The footnote previously stated, Effects of changes includes appropriate revisions of descriptions in the FSAR such that the FSAR (as updated) is complete and accurate.

This final rule changed includes to include so that the plural subject is followed by a plural verb.

5. Amends the current timely renewal provision under § 2.109, allowing NPUFs licensed under § 50.22 and testing facilities licensed under § 50.21(c) or § 50.22 to continue operating under an existing license past its expiration date if the facility submits a license renewal application at least 2 years before the current license expiration date.

The requirements in § 2.101(a) allow the NRC to determine the acceptability of an application for review by the NRC. However, before this final rule, § 2.109 allowed an NPUF licensee to submit its license renewal application as late as 30 days before the expiration of the existing license. Historical precedent indicates that 30 days is not a sufficient period of time for the NRC to adequately assess the sufficiency of a license renewal application for review. As a result, the NRC accepted license renewal applications and addressed their deficiencies through the license renewal process, largely through submitting RAIs to the licensee to supplement the application. This approach increased the burden of the license renewal process on both licensees and the NRC.

To address this issue, the NRC made revisions to the timely renewal provision for NPUFs licensed under § 50.22 and testing facilities licensed under § 50.21(c) or § 50.22 to establish a length of time adequate for the NRC to review the sufficiency of a 29

license renewal application. Specifically, the final rule amends § 2.109, allowing NPUFs licensed under § 50.22 and testing facilities licensed under § 50.21(c) or § 50.22 to continue operating under an existing license past its expiration date if the licensee submits a sufficient license renewal application at least 2 years before the current license expiration date. In such cases, the existing license will not be deemed to have expired until the application has been finally determined by the NRC. This final rule ensures that the NRC has adequate time to review the sufficiency of license renewal applications while the facility continues to operate under the terms of its current license.

The proposed rule eliminated this provision for facilities, other than testing facilities, licensed under § 50.21(a) or (c), as these facilities will no longer have license expiration dates. However, the final rule includes the timely renewal provision for facilities, other than testing facilities, licensed under § 50.21(a) or (c) because at least one of these facilities may submit a license renewal application after the effective date of this final rule.

6. Provides an accident dose criterion of 1 rem (0.01 Sv) TEDE for NPUFs other than testing facilities.

The standards in 10 CFR part 20 for protection against ionizing radiation provide a limit on the maximum yearly radiation dose a member of the public can receive from the operation of any NRC-licensed facility. Licensees are required to maintain programs and facility design features to ensure that these limits are met. In addition to the dose limits in 10 CFR part 20, accident dose criteria are also applied to determine the acceptability of the licensed facility. The accident dose criteria are not dose limits; they inform a licensees accident analyses and the development of successive safety measures (i.e., defense-in-depth) so that in the unlikely event of an accident, the NRC has reasonable assurance that no acute radiation-related harm will result to any member of the public. Before this final rule, the accident dose criterion for NPUFs other than 30

testing facilities was the 10 CFR part 20 dose limit to a member of the public. For testing facilities, accident dose criteria are still found in 10 CFR part 100.

Before January 1, 1994, the NRC had generally found acceptable accident doses for applicants applying for an initial or renewed NPUF license, other than for testing facilities, that were less than 0.5 rem (0.005 Sv) whole body and 3 rem (0.03 Sv) thyroid for members of the public. On May 21, 1991, the NRC amended 10 CFR part 20 to lower the dose limit to a member of the public to 0.1 rem (0.001 Sv) TEDE (56 FR 23360) with an implementation date of January 1, 1994. Since January 1, 1994, for applicants applying for an initial or renewed NPUF license, other than for testing facilities, the NRC has compared the results from the accident analyses submitted in initial or renewed license applications with the standards in 10 CFR part 20. In the proposed rule, the NRC misidentified the part 20 rulemaking date as January 1, 1994.

The NRC has determined that the public dose limit of 0.1 rem (0.001 Sv) TEDE in 10 CFR part 20 is unduly restrictive to be applied as accident dose criteria for NPUFs, other than those NPUFs subject to 10 CFR part 100. The NRC bases this determination on the NRC Atomic Safety and Licensing Appeal Boards decision that the standards in 10 CFR part 20 are unduly restrictive as accident dose criteria for research reactors (Trustees of Columbia University in the City of New York, ALAB-50, 4 AEC 849, 854-855 (May 18, 1972)). At the time of this decision, the 10 CFR part 20 public dose limit was 0.5 rem (0.005 Sv) whole body.

However, the NRC considers the accident dose criteria in 10 CFR part 100 (25 rem (0.25 Sv) whole body and 300 rem (3 Sv) to the thyroid) applicable to accident consequences for power reactors and testing facilities, for which an accident has greater potential consequences, to be too high for NPUFs other than testing facilities. For these reasons, this final rule modifies § 50.34 to add an accident dose criterion of 1 rem (0.01 Sv) TEDE for NPUFs not subject to 10 CFR part 100. The accident dose criterion of 1 31

rem (0.01 Sv) TEDE is based on the Environmental Protection Agencys (EPA)

Protection Action Guides (PAGs), which are dose guidelines to support decisions that trigger protective actions such as staying indoors or evacuating to protect the public during a radiological incident. The proposed rule stated that the 1 rem (0.01 Sv) TEDE accident dose criterion was based on the EPA PAGs published in EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents. In January 2017, the EPA published an update to its PAGs in EPA-400/R-17/001, PAG Manual: Protective Action Guides and Planning Guidance for Radiological Incidents.

This update to the EPA PAGs does not change the basis of the 1 rem (0.01 Sv) TEDE accident dose criterion.

The PAG is defined as the projected dose to an individual from a release of radioactive material at which a specific protective action to reduce or avoid that dose is recommended. Three principles considered in the development of the EPA PAGs include: 1) prevent acute effects; 2) balance protection with other important factors and ensure that actions result in more benefit than harm; and 3) reduce risk of chronic effects. In the early phase (i.e., the beginning of the radiological incident, which may last hours to days), if the sum of the projected dose from external radiation exposure and the inhalation of radioactive material is 1 rem (0.01 Sv) to 5 rem (0.05 Sv), the EPA PAG recommends the protective action of sheltering-in-place or evacuation of the public to avoid inhalation of gases or particulates in an atmospheric plume and to minimize external radiation exposures. The EPA PAG Manual does not provide a protective action recommendation for the public when the projected dose to an individual from an incident is less than 1 rem (0.01 Sv). In light of this understanding of the early phase EPA PAG, the NRCs accident dose criterion of 1 rem (0.01 Sv) TEDE for NPUFs, other than testing facilities, provides reasonable assurance of adequate protection of the public from unnecessary exposure to radiation.

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The NRC revised § 50.34(a)(1)(ii)(D)(2) of the proposed rule to replace postulated accidental release of licensed material with postulated accident. This final rule requires applicants and licensees to evaluate the potential dose from postulated accidents to include potential exposure from all radiological sources, such as direct or scattered radiation from an unshielded source inside the reactor building, in addition to potential exposure from a release of radioactive materials. This requirement is consistent with the evaluation methodology described in NUREG-1537, Part 1. Under this final rule, these evaluations need to demonstrate that the dose to any individual located in the unrestricted area will not be in excess of 1 rem (0.01 Sv) TEDE for the duration of the accident. Although the EPA PAGs were developed for radiological incidents that lead to the release or potential release of radioactive materials into the environment, the three principles considered in their development are not dependent on whether the dose received is due to exposure from a release of radioactive materials or from direct or scattered radiation.

To provide further clarification on the NRCs intent of the 1 rem (0.01 Sv) TEDE accident dose criterion for NPUFs, other than testing facilities, a footnote has been incorporated into the final rule text. The footnote clarifies that this 1 rem (0.01 Sv) TEDE accident dose criterion is not a dose limit, as explained in the preceding paragraphs.

In this final rule, the NRC moves proposed § 50.34(a)(1)(ii)(D)(2) to § 50.34(a)(1)(i) and leaves the rule language in § 50.34(a)(1)(ii)(D) unchanged. During the development of the final rule, the NRC recognized that the accident dose criterion more appropriately belongs in § 50.34(a)(1)(i) because the requirements in § 50.34(a)(1)(ii) apply to power reactor construction permit applicants, while the requirements in § 50.34(a)(1)(i) apply to all other construction permit applicants, such as NPUF applicants.

Similarly, proposed § 50.34(a)(1)(ii)(D)(2) would have imposed a requirement on applications for renewed NPUF operating licenses, which more appropriately belongs in 33

§ 50.34(b). Therefore, the NRC moved the requirement to new § 50.34(b)(13) in this final rule to clarify that an application for an operating license or a renewed operating license for an NPUF include a final evaluation of the applicable radiological consequences in 10 CFR 50.34(a)(1)(i).

7. Extends the applicability of § 50.59 to NPUFs regardless of their decommissioning status.

Section 50.59(b) of the Commissions regulations did not apply § 50.59 to NPUFs whose licenses were amended to reflect permanent cessation of operations and that no longer had fuel on site (e.g., they returned all of their fuel to the U.S. Department of Energy [DOE]). The former language stated that § 50.59 applied to licensees whose license has been amended to allow possession of nuclear fuel, but not operation of the facility. Therefore, § 50.59 did not apply to NPUF licensees that no longer possessed nuclear fuel. For these licensees, the NRC added license conditions identical to those of

§ 50.59 to allow the licensee to make changes to its facility or changes in its procedures that would not otherwise require obtaining a license amendment pursuant to § 50.90.

Because most NPUFs promptly return their fuel to the DOE after permanent shutdown, in contrast to decommissioning power reactors, these licensees had to request the addition of the license conditions, which imposed an administrative burden on the licensees and the NRC. This final rule eliminates this burden by revising the wording of

§ 50.59(b) to extend the applicability of § 50.59 to NPUFs regardless of their decommissioning status.

8. Clarifies an applicants requirements for meeting the existing provisions of § 51.45.

The NRC is required to prepare either an environmental impact statement or environmental assessment, as appropriate, for all licensing actions pursuant to 10 CFR part 51, unless a categorical exclusion applies as provided in § 51.22. For most types of 34

licenses, 10 CFR part 51 specifies that an applicant must submit environmental documentation in the form of an environmental report, or a supplement to a previously submitted environmental report, to assist the NRCs review and its compliance with the National Environmental Policy Act. However, before this final rule, the NRC did not have explicit requirements under 10 CFR part 51 with respect to the nature of the environmental documentation that must accompany applications for initial licenses and renewed licenses for NPUFs. This fact was highlighted in association with the NRCs review of SHINEs construction permit application for an NPUF to be licensed under the authority of Section 103 of the AEA.

This final rule added a new section to 10 CFR part 51 to clarify NPUF environmental reporting requirements. Section 51.56 clarifies an applicants existing requirements for meeting the provisions of § 51.45. This change improves consistency throughout 10 CFR part 51 with respect to environmental report submissions required from applicants for licensing actions. The NRC also made a conforming change to § 51.17 to reflect the approved information collection requirement of § 51.56.

9. Eliminates the requirement for NPUFs to submit financial qualification information with license renewal applications under § 50.33(f)(2).

This final rule eliminates license renewal financial qualification requirements for NPUFs. Before this final rule, § 50.33(f) required NPUF license applicants to provide information sufficient to demonstrate their financial qualifications to carry out the activities for which the license is sought. Because the regulatory requirements for the content of an application for a renewed NPUF license were the same as those for an original license, NPUF licensees that requested license renewal were required to submit the same financial information that was required in an application for an initial license. In addition, the NRC found that the financial qualification information did not meaningfully contribute to the NRCs determination on the license renewal application. The 35

elimination of NPUF license renewal financial qualification requirements reduces the burden associated with license renewal applications while still enabling the NRC to obtain the information necessary to conduct its review of license renewal applications.

Similar to the new approach for NPUFs, a 2004 rulemaking, Financial Information Requirements for Applications to Renew or Extend the Term of an Operating License for a Power Reactor, discontinued financial qualification reviews for power reactors at the license renewal stage except in very limited circumstances. The Commission stated that [t]he NRC believes that its primary tool for evaluating and ensuring safe operations at nuclear power reactors is through its inspection and enforcement programs. Further, the Commission stated that [t]he NRC has not found a consistent correlation between licensees poor financial health and poor safety performance. If a licensee postpones inspections and repairs that are subject to NRC oversight, the NRC has the authority to shut down the reactor or take other appropriate action if there is a safety issue.

At NPUF sites, the NRCs inspection and enforcement programs serve as important tools for evaluating licensee performance and ensuring safe operations. The NRC periodically inspects each operating NPUF using a graded approach that prioritizes higher-power facilities. The NRC completes an annual inspection of NPUFs licensed to operate at power levels of 2 MWt or greater. For NPUFs operating under 2 MWt, the inspection program is designed to be completed every two years, although inspector availability and licensee availability sometimes dictate that an inspection cycle is completed over more than two years. Inspections can include reviews of organizational structure, reactor operator qualifications, design and design control, radiation and environmental protection, maintenance and surveillance activities, transportation, material control and accounting, operational activities, review and audit functions, experiments, fuel handling, procedural controls, emergency preparedness, and security.

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The NRC also performs special and reactive inspections. In addition, the NRC manages the NPUF operator license examination program. The NRC also manages the review of NPUF emergency and security plans and develops and implements policy and guidance concerning the NPUF licensing program. These programs provide, in part, the NRCs safety oversight of these licensees.

The elimination of financial qualification requirements for power reactor licensees at the time of license renewal supports the NRCs basis for eliminating NPUF financial qualification requirements at the time of license renewal. The NRC is not aware of any connection between an NPUFs financial qualifications at license renewal and safe operation of the facility. Moreover, because NPUFs have significantly smaller fission product inventory and potential for radiological consequences than do power reactors, the NPUF financial qualification reviews are of less value in ensuring safety than reviews previously required of power reactors.

III. Opportunity for Public Participation The NRC staff hosted two public meetings to engage with external stakeholders on the proposed rule and associated draft guidance document during the public comment period. A public meeting was held on May 24, 2017, to discuss the proposed rule. A summary of the public meeting is available in ADAMS (ADAMS Accession No.

ML17170A066). A public meeting on the implementation schedule of the draft final rule was held on February XX, 2019. A summary of the public meeting is available in ADAMS (ADAMS Accession No. MLXXXXXXXXX). The feedback from these public meetings informed the development of this final rule.

IV. Public Comment Analysis 37

The NRC staff prepared a summary and analysis of public comments received on the 2017 proposed rule and draft regulatory guide, which, as described in the Availability of Documents section, is available in ADAMS under Accession No.

ML18031A005. In response to the proposed rule and draft regulatory guide, the NRC received 16 comment submissions.

The public comment submittals are available from the Federal e-Rulemaking Web site at http://www.regulations.gov under Docket ID NRC-2011-0087. Responses to the public comments, including a summary of how the final rule text or guidance changed as a result of the public comments, can be found in the public comment analysis document.

For more information about the associated guidance document see the Availability of Guidance section of this final rule.

V. Section-by-Section Analysis.

The following paragraphs describe the specific changes within this final rule.

Section 2.109 Effect of timely renewal application.

In § 2.109, this final rule revises paragraph (a) to exclude NPUFs licensed under

§ 50.22 and testing facilities licensed under § 50.21(c) or § 50.22, from the 30-day timely renewal provision and adds paragraph (e) to require these same licensees to submit a license renewal application at least 2 years before license expiration.

Section 20.1905 Exemptions to labeling requirements.

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In § 20.1905, this final rule revises paragraph (g) to standardize terminology by replacing the term reactors with the phrase production or utilization facilities.

Section 26.3 Scope.

In § 26.3, this final rule revises paragraph (e) to standardize terminology by replacing the term reactor with the phrase production or utilization facility.

Section 50.2 Definitions.

In § 50.2, this final rule adds a definition for Non-power production or utilization facility and revises the definitions for Non-power reactor and Testing facility.

Section 50.8 Information collection requirements: OMB approval.

In § 50.8, this final rule revises paragraph (b) to include new § 50.135 as an approved information collection requirement in 10 CFR part 50.

Section 50.33 Contents of applications; general information.

In § 50.33, this final rule revises paragraph (f)(2) to remove the phrase for a power reactor from the fourth sentence and to remove the fifth sentence, which required a non-power reactor applicant to submit with license renewal applications the same financial information that is required for initial license applications. It also redesignates the footnote to conform to the Office of the Federal Registers requirements.

Section 50.34 Contents of applications; technical information.

In § 50.34, this final rule revises paragraph (a)(1)(i) to include an accident dose criterion for applicants for construction permits for NPUFs not subject to 10 CFR part 100 and new footnote 2. It also redesignates the footnotes to conform to the Office of 39

the Federal Registers requirements. This final rule also adds paragraph (b)(13) to require an applicant for an operating or a renewed operating license for an NPUF to include a final evaluation of the applicable radiological consequences in 10 CFR 50.34(a)(1)(i) in the FSAR.

Section 50.36 Technical specifications.

In § 50.36, this final rule revises paragraph (c)(6) to standardize terminology by replacing the term non-power reactor with the phrase non-power production or utilization.

Section 50.51 Continuation of license.

In § 50.51, this final rule revises paragraph (a) to add the conditional phrase except as noted under § 50.51(c) and adds new paragraph (c) to clarify that NPUFs licensed under § 50.21(a) or (c), other than testing facilities, after the effective date of this final rule, will have non-expiring license terms.

Section 50.59 Changes, tests, and experiments.

In § 50.59, this final rule revises paragraph (b) to extend applicability to NPUFs that have permanently ceased operations and that no longer have fuel on site.

Section 50.71 Maintenance of records, making of reports.

In § 50.71, this final rule revises paragraph (e) to include NPUFs in the requirement and makes a tense correction to Footnote 1. It also revises paragraph (e)(3)(i) and redesignates paragraph (4) as paragraph (4)(i) to clarify that these paragraphs only apply to nuclear power reactors. New paragraphs (e)(3)(iv) and (e)(4)(ii) are added to include the requirements for NPUFs. This final rule also revises 40

paragraph (g) to standardize terminology by replacing the phrase non-power reactor with the phrase non-power production or utilization facility.

Section 50.75 Reporting and recordkeeping for decommissioning planning.

In § 50.75, this final rule also revises paragraphs (d)(1), (e)(1)(iv), and (f)(4) and (5) to standardize terminology by replacing the phrase non-power reactor(s) with the phrase non-power production or utilization facility(ies).

Section 50.82 Termination of license.

In § 50.82, this final rule revises paragraph (b) to standardize terminology by replacing the term reactor with the phrase production or utilization facility and revises paragraph (b)(1) to include testing facilities licensed under § 50.21(c) and holders of a license issued under § 50.22. Paragraph (c) is revised by moving the phrase for a facility that has permanently ceased operation before the expiration of its license to new paragraphs (c)(1) and (2) to clarify when the collection period for shortfalls in funding will be determined for NPUFs and licenses issued under § 50.21(b) or § 50.22, or a testing facility.

Section 50.135 Renewal of non-power production or utilization facility licenses issued under § 50.22 and testing facility licenses.

This final rule adds new § 50.135 to clearly define the license renewal process for NPUFs licensed under § 50.22 and testing facilities licensed under § 50.21(c).

Appendix C to Part 50A Guide for the Financial Data and Related Information Required To Establish Financial Qualifications for Construction Permits and Combined Licenses.

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In appendix C to part 50, this final rule revises paragraph III by replacing the reference to medical and research reactors with a reference to non-power production or utilization facilities of a type described in § 50.21(a) or (c), other than testing facilities.

Appendix E to Part 50Emergency Planning and Preparedness for Production and Utilization Facilities.

In appendix E to part 50, this final rule revises footnote 2 in paragraph I.3 to include the title of Regulatory Guide 2.6 and to replace the phrase research and test reactor with the phrase non-power production or utilization facility.

Section 51.17 Information collection requirements; OMB approval.

In § 51.17, this final rule revises paragraph (b) to add new § 51.56 as an approved information collection requirement in 10 CFR part 51.

Section 51.45 Environmental report.

In § 51.45, this final rule revises paragraph (a) to add a cross reference to new

§ 51.56.

Section 51.56 Environmental report - non-power production or utilization facility.

This final rule adds new § 51.56 to clarify existing requirements for the submittal and content of environmental reports by applicants seeking a permit to construct, or a license to operate, a non-power production or utilization facility.

Section 55.5 Communications.

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In § 55.5, this final rule revises paragraph (b)(1) to remove the conditional phrase except for test and research reactor facilities. It also revises paragraph (b)(3) to correct a division title and to clarify the applicability of this paragraph to utilization facilities licensed under 10 CFR part 50 that are not power reactors.

Section 55.40 Implementation.

In § 55.40, this final rule revises paragraph (d) to replace the phrase test and research reactors with the phrase non-power reactors.

Section 55.53 Conditions of licenses.

In § 55.53, this final rule revises paragraphs (e) and (f)(2) to replace the phrase test and research reactors with the phrase non-power reactors. It also revises paragraphs (j) and (k) to clarify that these paragraphs apply to utilization facilities licensed under 10 CFR part 50 that are not power reactors.

Section 55.59 Requalification.

In § 55.59, this final rule revises paragraph (c)(7) to clarify that this paragraph applies to utilization facilities licensed under 10 CFR part 50 that are not power reactors.

Section 55.61 Modification and revocation of licenses.

In § 55.61, this final rule revises paragraph (b)(5) to clarify that this paragraph applies to utilization facilities licensed under 10 CFR part 50 that are not power reactors.

Section 73.2 Definitions.

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In § 73.2, this final rule adds the definition of Non-power reactor as it is defined in

§ 50.2.

Section 73.21 Protection of safeguards information: performance requirements.

In § 73.21, this final rule revises paragraph (a)(1)(ii) to replace the phrase research and test reactors with the phrase non-power reactors.

Section 73.23 Protection of safeguards informationmodified handling: specific requirements.

In § 73.23, this final rule replaces the phrase research and test reactors with the phrase non-power reactors.

Section 73.60 Additional requirements for physical protection at non-power reactors.

In § 73.60, this final rule revises all instances of nonpower to read non-power.

Section 140.3 Definitions.

In § 140.3, this final rule removes the definition of Testing reactor and adds the definition of Testing facility as it is defined in § 50.2.

Section 140.11 Amounts of financial protection for certain reactors.

In § 140.11, this final rule revises paragraph (a)(3) to standardize terminology by replacing the term reactor with the term facility.

Section 170.3 Definitions.

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In § 170.3, this final rule revises the definition of Research reactor and revises the definition of Testing facility to align with the definition in § 50.2.

Section 171.5 Definitions.

In § 171.5, this final rule revises the definitions of Research reactor and Testing facility as they are defined in § 170.3 and § 50.2, respectively.

Section 171.15 Annual fees: Reactor licenses and independent spent fuel storage licenses.

In § 171.15, this final rule revises paragraphs (a) and (f) to standardize the terminology by replacing the phrase test reactor with the phrase testing facility and makes other conforming changes.

§ 171.17 Proration.

In § 171.17, this final rule revises paragraph (a)(1) to specify research reactors and testing facilities by removing the more generic non-power reactor phrase.

VI. Regulatory Flexibility Certification Under the Regulatory Flexibility Act (5 U.S.C. 605(b)), the NRC certifies that this rule does not have a significant economic impact on a substantial number of small entities. This final rule affects only the licensing and operation of NPUFs. The companies, universities, and government agencies that own and operate these facilities do not fall within the scope of the definition of small entities set forth in the Regulatory Flexibility Act or the size standards established by the NRC (10 CFR 2.810).

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VII. Regulatory Analysis The NRC has prepared a final regulatory analysis on this regulation and the implementation guidance. The analysis examines the costs and benefits of the alternatives considered by the NRC. The regulatory analysis is available as indicated in the Availability of Documents section of this document.

VIII. Backfitting and Issue Finality The NRCs backfitting provisions for reactors are found in 10 CFR 50.109. The regulatory basis for § 50.109 was expressed solely in terms of nuclear power reactors. For example, the NRCs Advanced Notice of Proposed Rulemaking, Policy Statement, Proposed Rule, and Final Rule for § 50.109 each had the same title:

Revision of Backfitting Process for Power Reactors. As a result, the NRC has not applied § 50.109 to research reactors, testing facilities, and other non-power facilities licensed under 10 CFR part 50 (e.g., Final Rule; Clarification of Physical Protection Requirements at Fixed Sites). In a 2012 final rule concerning non-power reactors, the NRC stated, The NRC has determined that the backfit provisions in § 50.109 do not apply to test, research, or training reactors because the rulemaking record for § 50.109 indicates that the Commission intended to apply this provision to only power reactors, and NRC practice has been consistent with this rulemaking record (Final Rule; Requirements for Fingerprint-Based Criminal History Records Checks for Individuals Seeking Unescorted Access to Non-Power Reactors).

Under § 50.2, non-power production or utilization facilities are defined to include non-power reactors or other production or utilization facilities licensed under §§ 50.21(a) or (c) (Section 104a or c of the AEA) or § 50.22 (Section 103 of the AEA) that are not 46

nuclear power reactors or production facilities as defined under paragraphs (1) and (2) of the definition of production facility in § 50.2. Because the term non-power production or utilization facility includes licensees that are excluded from the scope of § 50.109, NPUFs do not fall within the scope of § 50.109. Because § 50.109 does not apply to NPUFs, and this final rule applies exclusively to NPUFs, the NRC did not apply § 50.109 to this final rule.

Although § 50.109 does not apply to NPUF licensees, for those NPUFs licensed under the authority of Section 104 of the AEA, the Commission is directed to impose the minimum amount of regulation on the licensee consistent with its obligations under the AEA to promote the common defense and security, protect the health and safety of the public, and permit the conduct of widespread and diverse research and development and the widest amount of effective medical therapy possible. The NRC is meeting this standard by removing license renewal requirements for many entities licensed under Section 104 of the AEA, defining the license renewal process for testing facilities licensed under Section 104 of the AEA, and eliminating the requirement for testing facilities to submit financial qualification information at the time of license renewal.

IX. Cumulative Effects of Regulation Cumulative Effects of Regulation (CER) consists of the challenges licensees may face in addressing the implementation of new regulatory positions, programs, and requirements (e.g., rulemaking, guidance, generic letters, backfits, inspections). The CER may manifest in several ways, including the total burden imposed on licensees by the NRC from simultaneous or consecutive regulatory actions that can adversely affect the licensees capability to implement those requirements, while continuing to operate or construct its facility in a safe and secure manner.

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The goals of the NRCs CER effort were met throughout the development of this final rule. The NRC staff engaged external stakeholders at public meetings and by soliciting public comments on the proposed rule and associated draft guidance document. A public meeting was held on May 24, 2017 to discuss the proposed rule. A summary of the public meeting is available in ADAMS (ADAMS Accession No.

ML17170A066). A public meeting on implementation was held on February XX, 2019.

A summary of the public meeting is available in ADAMS (ADAMS Accession No.

MLXXXXXXXXX). The feedback from these public meetings informed the NRCs implementation schedule. The NRC also issued the draft guidance for public comment at the same time as the March 2017 proposed rule (March 30, 2017; 82 FR 15643).

Based upon input from the public and affected licensees, the NRC has specified that this final rule will take effect 30 days from the date of publication of this notice.

However, for the purposes of implementing the requirements of § 50.71(e), the NRC will be issuing orders to holders of operating licenses, as described in Section II.4.

Information on the effective and compliance dates for the various provisions of this final rule are found in the DATES section of this notice.

X. Plain Writing The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal agencies to write documents in a clear, concise, and well-organized manner. The NRC has written this document to be consistent with the Plain Writing Act as well as the Presidential Memorandum, Plain Language in Government Writing, published June 10, 1998 (63 FR 31883).

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XI. Environmental Assessment and Final Finding of No Significant Environmental Impact The Commission has determined under the National Environmental Policy Act of 1969, as amended, and the Commissions regulations in subpart A of 10 CFR part 51, that this rule, if adopted, will not be a major Federal action significantly affecting the quality of the human environment and, therefore, an environmental impact statement is not required. The rule to eliminate license terms for NPUFs, other than testing facilities, licensed under § 50.21(a) or (c) will result in no additional radiological or non-radiological impacts because of the minimal accident consequences of these facilities, existing surveillance and reporting by licensees, and NRC oversight. In addition, the implementation of the rulemaking will not affect the NEPA environmental review requirements of new facilities and facilities applying for license renewal. The NRC concludes that this final rule will not cause any additional radiological or non-radiological impacts on the human environment.

The NRC requested the views of the States on the environmental assessment for this rule. No States filed comments regarding the environmental assessment for this rule.

The determination of this environmental assessment is that there will be no significant offsite impact to the public from this action. The environmental assessment is available as indicated under the Availability of Documents section.

XII. Paperwork Reduction Act This final rule contains new or amended collections of information subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq). The collections of 49

information were approved by the Office of Management and Budget, approval numbers 3150-0011 and 3150-0021.

The new burden to the public for the information collections is estimated to average 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> per response for information collection requirements contained in part 50 and 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> per response for information collection requirements contained in part 51, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the information collections.

The information collections are being conducted to create a more efficient licensing process that continues to protect public health, safety, and the environment.

Information will be used by the NRC to ensure that licensing bases remain up-to-date and that adequate protection of public health and safety is maintained. Responses to these collections of information are mandatory under §§ 50.71(e) and 51.56.

Confidential and proprietary information submitted to the NRC is protected in accordance with NRC regulations at § 9.17(a) and § 2.390(b).

You may submit comments on any aspect of the information collections, including suggestions for reducing the burden, by the following methods:

• Federal rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2011-0087.

• Mail comments to: FOIA, Privacy, and Information Collections Branch, Office of Information Services, Mail Stop: T-5 F53, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 or to Matthew Oreska, Desk Officer, Office of Information and Regulatory Affairs (3150-AI96), NEOB-10202, Office of Management and Budget, Washington, DC 20503; telephone: 202-395-1741, e-mail: oira_submission@omb.eop.gov.

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Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.

XIII. Congressional Review Act This final rule is a rule as defined in the Congressional Review Act (5 U.S.C. 801-808). However, the Office of Management and Budget has not found it to be a major rule as defined in the Congressional Review Act.

XIV. Criminal Penalties For the purposes of Section 223 of the AEA, the NRC is issuing this final rule that amends 10 CFR 50.34, 50.36, 50.59, 50.71, 50.75, 50.82, 55.40, 55.53, 55.59, 73.21, 73.23, 73.57, 73.60, and 140.11 and creates § 50.135 under one or more of Sections 161b, 161i, or 161o of the AEA. Willful violations of these provisions would be subject to criminal enforcement.

XV. Availability of Guidance The NRC is issuing RG 2.7, Preparation of Updated Final Safety Analysis Reports for Non-power Production or Utilization Facilities, for the implementation of the requirements in § 50.71(e) of this rulemaking. The guidance is available in ADAMS under Accession No. ML18031A007. You may access information and public comment 51

submissions related to the guidance by searching on http://www.regulations.gov under Docket ID NRC-2011-0087.

XVI. Availability of Documents The documents identified in the following table are available to interested persons through one or more of the following methods, as indicated.

Document ADAMS Accession No. / Web link /

FEDERAL REGISTER CITATION NUREG-1537, Part 1, Guidelines for ML042430055 Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Format and Content NUREG-1537, Part 2, Guidelines for ML042430048 Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Standard Review Plan and Acceptance Criteria Interim Staff Guidance-2009-001, Interim ML092240244 Staff Guidance on the Streamlined Review Process for License Renewal for Research Reactors Non-Power Reactor License Renewal: 77 FR 38742; June 29, 2012 Preliminary Draft Regulatory Basis; Request for Comment Regulatory Basis to Support Proceeding with ML12240A677 Rulemaking to Streamline and Enhance the Research and Test Reactor (RTR) License Renewal Process Federal Register Notice: Final Regulatory ML12250A658 Basis for Rulemaking to Streamline Non-Power Reactor License Renewal; Notice of Availability of Documents SECY-08-0161, Review of Research and ML082550140 Test Reactor License Renewal Applications SRM-SECY-08-0161, Review of Research ML090850159 and Test Reactor License Renewal Applications SRM-M080317B, Briefing on State of NRC ML080940439 Technical Programs 52

SECY-09-0095, Long-Term Plan for ML092150717 Enhancing the Research and Test Reactor License Renewal Process and Status of the Development and Use of the Interim Staff Guidance SRM-SECY-91-061, Separation of Non- ML010050021 Reactor and Non-Power Reactor Licensing Activities from Power Reactor Licensing Activities in 10 CFR Part 50 SRM-M090811, Briefing on Research and ML092380046 Test Reactor (RTR) Challenges Draft Regulatory Guide DG-2006, ML17068A041 Preparation of Updated Final Safety Analysis Reports for Non-Power Production or Utilization Facilities Proposed Rule: Draft Regulatory and Backfit ML17068A038 Analysis Proposed Rule: Draft OMB Supporting ML17068A077 Statement Proposed Rule: Draft Environmental ML17068A035 Assessment SECY-16-0048, Proposed Rulemaking: Non- ML16019A048 Power Production or Utilization Facility License Renewal (RIN 3150-AI96)

Regulatory Guide RG 2.7, Preparation of ML18031A007 Updated Final Safety Analysis Reports for Non-Power Production or Utilization Facilities Final Rule: Regulatory Analysis for ML18031A003 Non-power Production or Utilization Facility License Renewal EPA 400-R-92-001, Manual of Protective https://www.epa.gov/sites/production/

Action Guides and Protective Actions for files/2016-03/documents/pags.pdf Nuclear Incidents EPA-400/R-17/001, PAG Manual: Protective https://www.epa.gov/sites/production/

Action Guides and Planning Guidance for files/2017-Radiological Incidents 01/documents/epa_pag_manual_final

_revisions_01 2017_cover_disclaimer_8.pdf Summary of August 7, 2014 Public Meeting to ML15322A400 Discuss the Rulemaking for Streamlining Non-power Reactor License Renewal Summary of October 7, 2015 Public Meeting ML15307A002 to Discuss the Rulemaking for Streamlining Non-Power Reactor License Renewal Standards for Protection Against Radiation 56 FR 23360; May 21, 1991 Federal Register Notice: Proposed Rule; 82 FR 15643; March 30, 2017 Non-Power Production or Utilization Facility License Renewal 53

SRM-SECY-16-0048, Staff Requirements-- ML17045A543 Proposed Rulemaking: Non-Power Production or Utilization Facility License Renewal (RIN 3150-AI96)

Final Rule: OMB Supporting Statement ML18031A006 Final Rule: Environmental Assessment ML18031A004 Final Rule; Financial Information 69 FR 4439; January 30, 2004 Requirements for Applications to Renew or Extend the Term of an Operating License for a Power Reactor Summary of May 24, 2017 Public Meeting to ML17170A066 Discuss the Proposed Non-Power Production or Utilization Facility License Renewal Rule Summary of February XX, 2019 Public MLXXXXXXXXX Meeting to Discuss the Implementation Schedule for the Non-Power Production or Utilization Facility License Renewal Final Rule NRC Response to Public Comment ML18031A005 Non-Power Production or Utilization Facility License Renewal SECY-19-00XX, Final Rulemaking: Non- MLXXXXXXXXX Power Production or Utilization Facility License Renewal (RIN 3150-AI96, NRC-2011-0087)

SRM-SECY-19-00XX, Final Rulemaking: MLXXXXXXXXX Non-Power Production or Utilization Facility License Renewal (RIN 3150-AI96)

Final Rule: 10 CFR Part 50 - Licensing of 33 FR 9704; July 4, 1968 Production and Utilization Facilities Final Rule: Elimination of Review of Financial 47 FR 13750; March 31, 1982 Qualifications of Electric Utilities in Licensing Hearings for Nuclear Power Plants Final Rule: Elimination of Review of Financial 49 FR 35747; September 12, 1984 Qualifications of Electric Utilities in Operating License Reviews and Hearings for Nuclear Power Plants Final Regulations; National Environmental 43 FR 55978; November 29, 1978 Policy ActRegulations Advanced Notice of Proposed Rulemaking; 48 FR 44217; September 28, 1983 Revision of Backfitting Process for Power Reactors Policy Statement; Revision of Backfitting 48 FR 44173; September 28, 1983 Process for Power Reactors Proposed Rule: Revision of Backfitting 49 FR 47034; November 30, 1984 Process for Power Reactors Final Rule: Revision of Backfitting Process for 50 FR 38097; September 20, 1985 Power Reactors Final Rule: Limiting the Use of Highly 51 FR 6514; February 25, 1986 Enriched Uranium in Domestically Licensed Research and Test Reactors 54

Final Rule: Clarification of Physical Protection 58 FR 13699; March 15, 1993 Requirements at Fixed Sites Final Rule: Requirements for Fingerprint- 77 FR 27561, 27572; May 11, 2012 Based Criminal History Record Checks for Individuals Seeking Unescorted Access to Non-Power Reactors Plain Language in Government Writing 63 FR 31885; June 10, 1998 55

List of Subjects 10 CFR Part 2 Administrative practice and procedure, Antitrust, Byproduct material, Classified information, Confidential business information; Freedom of information, Environmental protection, Hazardous waste, Nuclear energy, Nuclear materials, Nuclear power plants and reactors, Penalties, Reporting and recordkeeping requirements, Sex discrimination, Source material, Special nuclear material, Waste treatment and disposal.

10 CFR Part 20 Byproduct material, Criminal penalties, Hazardous waste, Licensed material, Nuclear energy, Nuclear materials, Nuclear power plants and reactors, Occupational safety and health, Packaging and containers, Penalties, Radiation protection, Reporting and recordkeeping requirements, Source material, Special nuclear material, Waste treatment and disposal.

10 CFR Part 26 Administrative practice and procedure, Alcohol abuse, Alcohol testing, Appeals, Chemical testing, Drug abuse, Drug testing, Employee assistance programs, Fitness for duty, Management actions, Nuclear power plants and reactors, Privacy, Protection of information, Radiation protection, Reporting and recordkeeping requirements.

10 CFR Part 50 Administrative practice and procedure, Antitrust, Classified information, Criminal penalties, Education, Fire prevention, Fire protection, Incorporation by reference, Intergovernmental relations, Nuclear power plants and reactors, Penalties, Radiation 56

protection, Reactor siting criteria, Reporting and recordkeeping requirements, Whistleblowing.

10 CFR Part 51 Administrative practice and procedure, Environmental impact statements, Hazardous waste, Nuclear energy, Nuclear materials, Nuclear power plants and reactors, Reporting and recordkeeping requirements.

10 CFR Part 55 Criminal penalties, Manpower training programs, Nuclear power plants and reactors, Penalties, Reporting and recordkeeping requirements.

10 CFR Part 73 Criminal penalties, Exports, Hazardous materials transportation, Incorporation by reference, Imports, Nuclear energy, Nuclear materials, Nuclear power plants and reactors, Penalties, Reporting and recordkeeping requirements, Security measures.

10 CFR Part 140 Criminal penalties, Extraordinary nuclear occurrence, Insurance, Intergovernmental relations, Nuclear materials, Nuclear power plants and reactors, Penalties, Reporting and recordkeeping requirements.

10 CFR Part 170 57

Byproduct material, Import and export licenses, Intergovernmental relations, Non-payment penalties, Nuclear energy, Nuclear materials, Nuclear power plants and reactors, Source material, Special nuclear material.

10 CFR Part 171 Annual charges, Byproduct material, Holders of certificates, registrations, approvals, Intergovernmental relations, Nonpayment penalties, Nuclear materials, Nuclear power plants and reactors, Source material, Special nuclear material.

For the reasons set out in the preamble and under the authority of the AEA, as amended; the Energy Reorganization Act of 1974, as amended; and 5 U.S.C. 552 and 553, the NRC is adopting the following amendments to 10 CFR parts 2, 20, 26, 50, 51, 55, 73, 140, 170, and 171:

PART 2 -- AGENCY RULES OF PRACTICE AND PROCEDURE

1. The authority citation for part 2 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 29, 53, 62, 63, 81, 102, 103, 104, 105, 161, 181, 182, 183, 184, 186, 189, 191, 234 (42 U.S.C. 2039, 2073, 2092, 2093, 2111, 2132, 2133, 2134, 2135, 2201, 2231, 2232, 2233, 2234, 2236, 2239, 2241, 2282);

Energy Reorganization Act of 1974, secs. 201, 206 (42 U.S.C. 5841, 5846); Nuclear Waste Policy Act of 1982, secs. 114(f), 134, 135, 141 (42 U.S.C. 10134(f), 10154, 10155, 10161); Administrative Procedure Act (5 U.S.C. 552, 553, 554, 557, 558);

National Environmental Policy Act of 1969 (42 U.S.C. 4332); 44 U.S.C. 3504 note.

Section 2.205(j) also issued under 28 U.S.C. 2461 note.

2. In § 2.109, revise paragraph (a) and add paragraph (e) to read as follows:

§ 2.109 Effect of timely renewal application.

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(a) Except for the renewal of an operating license for a nuclear power plant under

§ 50.21(b) or § 50.22, a non-power production or utilization facility under § 50.22, a testing facility under § 50.21(c) or § 50.22, an early site permit under subpart A of part 52 of this chapter, a manufacturing license under subpart F of part 52 of this chapter, or a combined license under subpart C of part 52 of this chapter, if at least 30 days before the expiration of an existing license authorizing any activity of a continuing nature, the licensee files an application for a renewal or for a new license for the activity so authorized, the existing license will not be deemed to have expired until the application has been finally determined.

• * * * *

(e) If the licensee of a non-power production or utilization facility licensed under 10 CFR 50.22, or testing facility, files a sufficient application for renewal at least 2 years before the expiration of the existing license, the existing license will not be deemed to have expired until the application has been finally determined.

PART 20 -- STANDARDS FOR PROTECTION AGAINST RADIATION

3. The authority citation for part 20 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 11, 53, 63, 65, 81, 103, 104, 161, 170H, 182, 186, 223, 234, 274, 1701 (42 U.S.C. 2014, 2073, 2093, 2095, 2111, 2133, 2134, 2201, 2210h, 2232, 2236, 2273, 2282, 2021, 2297f); Energy Reorganization Act of 1974, secs. 201, 202 (42 U.S.C. 5841, 5842); Low-Level Radioactive Waste Policy Amendments Act of 1985, sec. 2 (42 U.S.C. 2021b); 44 U.S.C. 3504 note.

§ 20.1905 [Amended]

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4. In § 20.1905(g), remove the word reactors and add in its place the phrase production or utilization facilities.

PART 26 - FITNESS FOR DUTY PROGRAMS

5. The authority citation for part 26 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 53, 103, 104, 107, 161, 223, 234, 1701 (42 U.S.C. 2073, 2133, 2134, 2137, 2201, 2273, 2282, 2297f); Energy Reorganization Act of 1974, secs. 201, 202 (42 U.S.C. 5841, 5842); 44 U.S.C. 3504 note.

§ 26.3 [Amended]

6. In § 26.3(e), remove the word reactor and add in its place the phrase production or utilization facility.

PART 50 -- DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES

7. The authority citation for part 50 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 11, 101, 102, 103, 104, 105, 108, 122, 147, 149, 161, 181, 182, 183, 184, 185, 186, 187, 189, 223, 234 (42 U.S.C. 2014, 2131, 2132, 2133, 2134, 2135, 2138, 2152, 2167, 2169, 2201, 2231, 2232, 2233, 2234, 2235, 2236, 2237, 2239, 2273, 2282); Energy Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Nuclear Waste Policy Act of 1982, sec. 306 (42 U.S.C. 10226); National Environmental Policy Act of 1969 (42 U.S.C.

4332); 44 U.S.C. 3504 note; Sec. 109, Pub. L.96-295, 94 Stat. 783.

8. In § 50.2, add in alphabetical order the definition for Non-power production or utilization facility, and revise the definitions for Non-power reactor and Testing facility to read as follows:

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§ 50.2 Definitions.

• * * *

• Non-power production or utilization facility means a production or utilization facility, licensed under § 50.21(a), § 50.21(c), or § 50.22, as applicable, that is not a nuclear power reactor or a production facility as defined under paragraphs (1) and (2) of the definition of production facility in § 50.2.

Non-power reactor means:

(1) A testing facility; or (2) A research reactor, which is a non-power production or utilization facility that is a nuclear reactor licensed under § 50.21(c):

(i) For which a safety assessment demonstrates accident radiation doses consistent with § 50.34(a)(1)(i); and (ii) That is not a testing facility; or (3) A commercial or industrial reactor, which is a non-power production or utilization facility that is a nuclear reactor licensed under § 50.22:

(i) For which a safety assessment demonstrates accident radiation doses consistent with § 50.34(a)(1)(i); and (ii) That is not a testing facility.

• * * *

• Testing facility means a non-power production or utilization facility that is a nuclear reactor licensed under § 50.21(c) or § 50.22 for which:

(1) Analyzed accident radiation doses are in excess of the dose criterion for facilities not subject to 10 CFR part 100 set forth in § 50.34(a)(1)(i); or 61

(2) The Commission determines that the design, operation, or use and the associated risk warrant classification as a testing facility.

• * * * *

§ 50.8 [Amended]

9. In § 50.8(b), add the number 50.135, in numerical order.

§ 50.33 [Amended]

10. In § 50.33:

a. Remove the phrase for a power reactor from the fourth sentence and remove the last sentence in paragraph (f)(2); and

b. Redesignate footnotes 4 and 5 as footnotes 1 and 2.

11. In § 50.34:

a. Redesignate footnote 5 as footnote 1;

b. Revise paragraph (a)(1)(i);

c. Redesignate footnotes 6 and 7 as footnotes 3 and 4;

d. Remove footnotes 8 and 9;

f. Redesignate footnotes 10 and 11 as footnotes 5 and 6; and

g. Add paragraph (b)(13).

The revision and addition read as follows:

§ 50.34 Contents of applications; technical information.

(a) * * *

(1) * * *

(i) A description and safety assessment of the site on which the facility is to be located, with appropriate attention to features affecting facility design. Special attention 62

should be directed to the site evaluation factors identified in part 100 of this chapter.

The assessment must contain an analysis and evaluation of the major structures, systems and components of the facility which bear significantly on the acceptability of the site under the site evaluation factors identified in part 100 of this chapter, assuming that the facility will be operated at the ultimate power level which is contemplated by the applicant. For non-power production or utilization facilities not subject to 10 CFR part 100, the assessment must provide an evaluation of the applicable radiological consequences that demonstrates with reasonable assurance that any individual located in the unrestricted area following the onset of a postulated accident, including consideration of experiments, would not receive a radiation dose in excess of 1 rem (0.01 Sv)2 TEDE for the duration of the accident. With respect to operation at the projected initial power level, the applicant is required to submit information prescribed in paragraphs (a)(2) through (a)(8) of this section, as well as the information required by this paragraph, in support of the application for a construction permit, or a design approval.

• * * * *

(b) * * *

(13) Non-power production or utilization facility applicants who apply for an initial or renewed operating license shall provide a final evaluation of the applicable radiological consequences in 10 CFR 50.34(a)(1)(i).

• * * *

• 2 The 1 rem accident dose criterion for non-power production or utilization facilities is not a dose limit; it informs the analysis of postulated accidents and the development of safety measures so that in the unlikely event of an accident, the NRC has reasonable assurance that no acute radiation-related harm will result to any member of the public.

§ 50.36 [Amended]

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12. Revise § 50.36(c)(6) to remove the phrase non-power reactor and add in its place the phrase non-power production or utilization.

13. In § 50.51, in the first sentence of paragraph (a) remove the word Each and add in its place the phrase Except as noted in § 50.51(c), each and add paragraph (c) to read as follows:

§ 50.51 Continuation of license.

• * * * *

(c) Each non-power production or utilization facility license issued under § 50.21(a) or (c), other than a testing facility license, after [INSERT EFFECTIVE DATE OF FINAL RULE] will be issued with no fixed license term.

§ 50.59 [Amended]

14. In § 50.59(b), remove the punctuation . at the end of the sentence and add in its place , or a non-power production or utilization facility that has permanently ceased operations.

15. In § 50.71:

a. In the first sentence of paragraph (e), add the phrase , or non-power production or utilization facility, after the word reactor, and in footnote 1, remove the word includes and add in its place the word include;

b. In paragraph (e)(3)(i), remove the article A at the beginning and add in its place For nuclear power reactor licensees, a and add paragraph (e)(3)(iv);

c. Redesignate paragraph (e)(4) as paragraph (e)(4)(i) and remove the word 64

Subsequent and add in its place For nuclear power licensees, subsequent; add paragraph (e)(4)(ii); and

d. In paragraph (g), remove the phrase non-power reactor and add in its place the phrase non-power production or utilization facility.

The additions and revisions read as follows:

§ 50.71 Maintenance of records, making of reports.

• * * * *

(e) * * *

(3) * * *

(iv) Holders of non-power production or utilization facility licenses issued after

[INSERT EFFECTIVE DATE OF FINAL RULE] shall file a revision of the original FSAR within 5 years of the date of issuance of the operating license. The revision must bring the FSAR up to date as of a maximum of 6 months before the date of filing the revision.

• * * * *

(4) * * *

(ii) Non-power production or utilization facility licensees shall file an FSAR update no more than 5 years from the date of the submittal of the updated FSAR required by § 50.71(e)(3)(iv) or order, and shall file subsequent updates no more than 5 years from the date of the previous submittal. Each submittal must reflect all changes made to the FSAR up to a maximum of 6 months prior to the date of filing the submittal.

• * * * *

16. In § 50.75:

a. Revise paragraph (d)(1);

b. In paragraphs (e)(1)(iv) and (f)(4), remove the phrase non-power 65

reactor and add in its place the phrase non-power production or utilization facility; and

c. In paragraph (f)(5), remove the phrase and non-power reactors and add in its place the phrase reactors and non-power production or utilization facilities.

The revision reads as follows:

§ 50.75 Reporting and recordkeeping for decommissioning planning.

• * * * *

(d)(1) Each applicant for or holder of an operating license for a non-power production or utilization facility shall submit a decommissioning report as required by

§ 50.33(k) of this part.

• * * * *

17. In § 50.82, revise paragraphs (b) introductory text, (b)(1), and (c) to read as follows:

§ 50.82 Termination of license.

• * * * *

(b) For non-power production or utilization facility licensees (1) A licensee that permanently ceases operations must make application for license termination within 2 years following permanent cessation of operations, and for testing facilities licensed under § 50.21(c) or holders of a license issued under § 50.22, in no case later than 1 year prior to expiration of the operating license. Each application for termination of a license must be accompanied or preceded by a proposed decommissioning plan. The contents of the decommissioning plan are specified in 66

paragraph (b)(4) of this section.

• * * * *

(c) The collection period for any shortfall of funds will be determined, upon application by the licensee, on a case-by-case basis taking into account the specific financial situation of each holder of the following licenses:

(1) A non-power production or utilization facility license issued under § 50.21(a) or (c), other than a testing facility, that has permanently ceased operations.

(2) A license issued under § 50.21(b) or § 50.22, or a testing facility, that has permanently ceased operation before the expiration of its license.

18. Add § 50.135 to read as follows:

§ 50.135 Renewal of non-power production or utilization facility licenses issued under § 50.22 and testing facility licenses.

(a) Applicability. The requirements in this section apply to applicants for renewed non-power production or utilization facility operating licenses issued under § 50.22 and to applicants for renewed testing facility operating licenses issued under § 50.21(c).

(b) Written communications. All applications, correspondence, reports, and other written communications must be filed in accordance with applicable portions of § 50.4.

(c) Filing of application.

(1) The filing of an application for a renewed license must be in accordance with subpart A of 10 CFR part 2 and all applicable sections of this part.

(2) An application for a renewed license may not be submitted to the Commission earlier than 10 years before the expiration of the operating license currently in effect.

(d) Contents of application.

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(1) Each application must include the information specified in §§ 50.33, 50.34, and 50.36, as applicable.

(2) Each application must include conforming changes to the standard indemnity agreement, under 10 CFR part 140 to account for the expiration term of the proposed renewed license.

(3) Each application must include a supplement to the environmental report that complies with the requirements of 10 CFR 51.56.

(e) Issuance of a renewed license.

(1) A renewed license will be of the class for which the operating license currently in effect was issued.

(2) A renewed license will be issued for a fixed period of time. The term of any renewed license may not exceed 40 years.

(3) A renewed license will become effective immediately upon its issuance, thereby superseding the operating license previously in effect. If a renewed license is subsequently set aside upon further administrative or judicial appeal, the operating license previously in effect will be reinstated unless its term has expired and the renewal application was not filed in a timely manner.

(4) A renewed license may be subsequently renewed in accordance with all applicable requirements.

Appendix C to Part 50 [Amended]

19. In paragraph III of appendix C to part 50, remove the phrase for medical and research reactors and add in its place the phrase for non-power production or utilization facilities of a type described in § 50.21(a) or (c), other than testing facilities.

20. In paragraph I.3 to appendix E to part 50, revise footnote 2 to read as 68

follows:

APPENDIX E TO PART 50EMERGENCY PLANNING AND PREPAREDNESS FOR PRODUCTION AND UTILIZATION FACILITIES

• * * *

• 2 Regulatory Guide 2.6, Emergency Planning for Research and Test Reactors and Other Non-Power Production and Utilization Facilities, may be used as guidance for the acceptability of non-power production or utilization facility emergency response plans.

• * * *

• PART 51 -- ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND RELATED REGULATORY FUNCTIONS

21. The authority citation for part 51 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 161, 193 (42 U.S.C. 2201, 2243);

Energy Reorganization Act of 1974, secs. 201, 202 (42 U.S.C. 5841, 5842); National Environmental Policy Act of 1969 (42 U.S.C. 4332, 4334, 4335); Nuclear Waste Policy Act of 1982, secs. 144(f), 121, 135, 141, 148 (42 U.S.C. 10134(f), 10141, 10155, 10161, 10168); 44 U.S.C. 3504 note.

§ 51.17 [Amended]

22. In § 51.17(b), add the number 51.56, in numerical order.

§ 51.45 [Amended]

23. In § 51.45(a), add the number 51.56, in numerical order.

24. Add § 51.56 to read as follows:

§ 51.56 Environmental reportnon-power production or utilization facility.

69

Each applicant for a non-power production or utilization facility license or other form of permission, or renewal of a non-power production or utilization facility license or other form of permission issued pursuant to § 50.21(a) or (c) or § 50.22 of this chapter shall submit a separate document, entitled Applicant's Environmental Report or Supplement to Applicant's Environmental Report, as appropriate, with its application to:

ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation. The environmental report or supplement shall contain the information specified in § 51.45. If the application is for a renewal of a license or other form of permission for which the applicant has previously submitted an environmental report, the supplement, to the extent applicable, shall include an analysis of any environmental impacts resulting from operational experience or a change in operations, and an analysis of any environmental impacts that may result from proposed decommissioning activities. The supplement may incorporate by reference the previously submitted environmental report, or portions thereof.

PART 55 -- OPERATORS' LICENSES

25. The authority citation for part 55 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 107, 161, 181, 182, 183, 186, 187, 223, 234 (42 U.S.C. 2137, 2201, 2231, 2232, 2233, 2236, 2237, 2273, 2282); Energy Reorganization Act of 1974, secs. 201, 202 (42 U.S.C. 5841, 5842); Nuclear Waste Policy Act of 1982, sec. 306 (42 U.S.C. 10226); 44 U.S.C. 3504 note.

§ 55.5 [Amended]

26. In § 55.5:

a. In paragraph (b)(1) remove the phrase Except for test and research reactor facilities, the and add in its place the word The; and

b. In paragraph (b)(3) remove the phrase a test and research reactor or non-power reactor facility licensed under 10 CFR part 50 and add in its place a 70

utilization facility licensed under part 50 of this chapter that is not a power reactor, and remove the phrase Division of Policy and Rulemaking and add in its place the phrase Division of Licensing Projects.

§ 55.40 [Amended]

27. In § 55.40(d), remove the phrase all test and research reactors and add in its place the phrase all non-power reactors.

§ 55.53 [Amended]

28. In § 55.53:

a. In paragraphs (e) and (f)(2), remove the phrase test and research reactor and add in its place the phrase non-power reactors; and

b. In paragraphs (j) and (k), remove the phrase non-power reactors and add in its place the phrase utilization facilities licensed under 10 CFR part 50 that are not power reactors, and also in paragraph (k) remove the term non-power at the end of the paragraph.

§ 55.59 [Amended]

29. In § 55.59(c)(7), in the paragraph heading remove the phrase research and test reactor facilities and add in its place the phrase utilization facilities licensed under 10 CFR part 50 that are not power reactors, and in the paragraph remove the phrase research reactor or test reactor facility and add in its place utilization facility licensed under 10 CFR part 50 that is not a power reactor.

§ 55.61 [Amended]

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30. In § 55.61(b)(5), remove the phrase non-power reactors and add in its place the phrase utilization facilities licensed under 10 CFR part 50 that are not power reactors.

PART 73 PHYSICAL PROTECTION OF PLANTS AND MATERIALS

31. The authority citation for part 73 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 53, 147, 149, 161, 170D, 170E, 170H, 170I, 223, 229, 234, 1701 (42 U.S.C. 2073, 2167, 2169, 2201, 2210d, 2210e, 2210h, 2210i, 2273, 2278a, 2282, 2297f); Energy Reorganization Act of 1974, secs. 201, 202 (42 U.S.C. 5841, 5842); Nuclear Waste Policy Act of 1982, secs. 135, 141 (42 U.S.C. 10155, 10161); 44 U.S.C. 3504 note. Section 73.37(b)(2) also issued under Sec. 301, Public Law 96-295, 94 Stat. 789 (42 U.S.C. 5841 note).

32. In § 73.2, add in alphabetical order the definition for Non-power reactor.

§ 73.2 Definitions.

• * * *

• Non-power reactor is defined at 10 CFR 50.2.

• * * * *

§ 73.21 [Amended]

33. In § 73.21(a)(1)(ii), remove the phrase Research and test reactors and add in its place the phrase non-power reactors.

§ 73.23 [Amended]

34. In § 73.23, remove the phrase research and test reactors and add in its place the phrase non-power reactors.

§ 73.60 [Amended]

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35. In § 73.60, wherever it may appear, remove the word nonpower and add in its place the word non-power.

PART 140 FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS

36. The authority citation for part 140 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 161, 170, 223, 234 (42 U.S.C.

2201, 2210, 2273, 2282); Energy Reorganization Act of 1974, secs. 201, 202 (42 U.S.C.

5841, 5842); 44 U.S.C. 3504 note.

37. In § 140.3, remove the definition for Testing reactor and revise the definition for Testing facility to read as follows:

§ 140.3 Definitions.

• * * *

• Testing facility is defined at 10 CFR 50.2.

• * * * *

§ 140.11 [Amended]

38. In § 140.11(a)(3), remove the phrase testing reactor and add in its place the phrase testing facility.

PART 170 FEES FOR FACILITIES, MATERIALS, IMPORT AND EXPORT LICENSES, AND OTHER REGULATORY SERVICES UNDER THE ATOMIC ENERGY ACT OF 1954, AS AMENDED

39. The authority citation for part 170 continues to read as follows:

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Authority: Atomic Energy Act of 1954, secs. 11, 161(w) (42 U.S.C. 2014, 2201(w)); Energy Reorganization Act of 1974, sec. 201 (42 U.S.C. 5841); 42 U.S.C.

2214; 31 U.S.C. 901, 902, 9701; 44 U.S.C. 3504 note.

40. In § 170.3, revise the definitions for Research reactor and Testing facility to read as follows:

§ 170.3 Definitions.

• * * *

• Research reactor means a non-power production or utilization facility, as defined in 10 CFR 50.2, that is a nuclear reactor licensed under 10 CFR 50.21(c):

(i) For which a safety assessment demonstrates accident radiation doses consistent with 10 CFR 50.34(a)(1)(i); and (ii) That is not a testing facility.

• * * *

• Testing facility is defined at 10 CFR 50.2.

• * * *

• PART 171ANNUAL FEES FOR REACTOR LICENSES AND FUEL CYCLE LICENSES AND MATERIALS LICENSES, INCLUDING HOLDERS OF CERTIFICATES OF COMPLIANCE, REGISTRATIONS, AND QUALITY ASSURANCE PROGRAM APPROVALS AND GOVERNMENT AGENCIES LICENSED BY THE NRC

41. The authority citation for part 171 continues to read as follows:

Authority: Atomic Energy Act of 1954, secs. 11, 161(w), 223, 234 (42 U.S.C.

2014, 2201(w), 2273, 2282); Energy Reorganization Act of 1974, sec. 201 (42 U.S.C.

5841); 42 U.S.C. 2214; 44 U.S.C. 3504 note.

74

42. In § 171.5, revise the definitions for Research reactor and Testing facility to read as follows:

§ 171.5 Definitions.

• * * *

• Research reactor is defined at 10 CFR 170.3.

• * * *

• Testing facility is defined at 10 CFR 50.2.

• * * * *

43. In § 171.15, revise paragraphs (a) and (f) to read as follows:

§ 171.15 Annual fees: Reactor licenses and independent spent fuel storage licenses.

(a) Each person holding an operating license for a power reactor, testing facility, or research reactor; each person holding a combined license under 10 CFR part 52 of this chapter after the Commission has made the finding under 10 CFR 52.103(g); each person holding a 10 CFR part 50 or part 52 power reactor license that is in decommissioning or possession only status, except those that have no spent fuel onsite; and each person holding a 10 CFR part 72 license who does not hold a 10 CFR part 50 or part 52 license and provides notification in accordance with 10 CFR 72.80(g), shall pay the annual fee for each license held during the Federal fiscal year in which the fee is due. This paragraph does not apply to testing facilities or research reactors exempted under §171.11(a).

• * * *

• 75

(f) The FY 2018 annual fees for licensees authorized to operate a research reactor or testing facility licensed under 10 CFR part 50, unless the reactor is exempted from fees under §171.11(a), are as follows Research reactor $81,300 Testing facility $81,300

§ 171.17 [Amended]

44. In § 171.17(a)(1), remove the phrase non-power reactors and add in its place the phrase research reactors, testing facilities.

Dated at Rockville, Maryland, this xxth day of Xxxxx, 201X.

For the Nuclear Regulatory Commission.

CONTACT DRM/RASB FOR DIGITAL SIGNATURE Annette L. Vietti-Cook, Secretary of the Commission.

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