82_FR_13827 82 FR 13778 - Regulatory Improvements for Power Reactors Transitioning to Decommissioning

82 FR 13778 - Regulatory Improvements for Power Reactors Transitioning to Decommissioning

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 82, Issue 49 (March 15, 2017)

Page Range13778-13781
FR Document2017-05141

The U.S. Nuclear Regulatory Commission (NRC) is requesting comments on a draft regulatory basis to support a rulemaking that would amend NRC's regulations for the decommissioning of nuclear power reactors. The NRC's goals in amending these regulations would be to provide for an efficient decommissioning process; reduce the need for exemptions from existing regulations; address other decommissioning issues deemed relevant by the NRC staff; and support the principles of good regulation, including openness, clarity, and reliability. The NRC plans to hold a public meeting to discuss the draft regulatory basis and facilitate public comment.

Federal Register, Volume 82 Issue 49 (Wednesday, March 15, 2017)
[Federal Register Volume 82, Number 49 (Wednesday, March 15, 2017)]
[Proposed Rules]
[Pages 13778-13781]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2017-05141]


========================================================================
Proposed Rules
                                                Federal Register
________________________________________________________________________

This section of the FEDERAL REGISTER contains notices to the public of 
the proposed issuance of rules and regulations. The purpose of these 
notices is to give interested persons an opportunity to participate in 
the rule making prior to the adoption of the final rules.

========================================================================


Federal Register / Vol. 82, No. 49 / Wednesday, March 15, 2017 / 
Proposed Rules

[[Page 13778]]



NUCLEAR REGULATORY COMMISSION

10 CFR Parts 26, 50, 52, 73, and 140

[NRC-2015-0070]
RIN 3150-AJ59


Regulatory Improvements for Power Reactors Transitioning to 
Decommissioning

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft regulatory basis; request for comment.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is requesting 
comments on a draft regulatory basis to support a rulemaking that would 
amend NRC's regulations for the decommissioning of nuclear power 
reactors. The NRC's goals in amending these regulations would be to 
provide for an efficient decommissioning process; reduce the need for 
exemptions from existing regulations; address other decommissioning 
issues deemed relevant by the NRC staff; and support the principles of 
good regulation, including openness, clarity, and reliability. The NRC 
plans to hold a public meeting to discuss the draft regulatory basis 
and facilitate public comment.

DATES: Submit comments by June 13, 2017. Comments received after this 
date will be considered if it is practical to do so, but the NRC is 
only able to ensure consideration of comments received on or before 
this date.

ADDRESSES: You may submit comments by the following method:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0070. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions contact 
the individuals listed in the FOR FURTHER INFORMATION CONTACT section 
of this document.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Alysia G. Bone, telephone: 301-415-
1034, email: [email protected]; or Jennifer C. Tobin, telephone: 301-
415-2328, email: [email protected]. Both are staff of the Office 
of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION: 

Table of Contents

I. Obtaining Information and Submitting Comments
II. Discussion
III. Specific Requests for Comments
IV. Cumulative Effects of Regulation
V. Availability of Documents
VI. Plain Writing

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2015-0070 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-2015-0070.
     NRC's 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 NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to [email protected]. The 
draft regulatory basis document is available in ADAMS under Accession 
No. ML17047A413.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

    Please include Docket ID NRC-2015-0070 in your comment submission. 
If you cannot submit your comments on the Federal rulemaking Web site, 
www.regulations.gov, then contact one of the individuals listed in the 
FOR FURTHER INFORMATION CONTACT section of this document.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons to not 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS. Please note that the 
NRC will not provide formal written responses to each of the comments 
received on the draft regulatory basis. However, the NRC staff will 
consider all comments received in the development of the final 
regulatory basis.

II. Discussion

    On December 30, 2014, in the staff requirements memorandum (SRM) 
for SECY-14-0118, ``Request by Duke Energy Florida, Inc., for 
Exemptions from Certain Emergency Planning Requirements'' (ADAMS 
Accession No. ML14364A111), the Commission directed the NRC staff to 
proceed with a rulemaking on power reactor decommissioning. The 
Commission also stated that the rulemaking should address: Issues 
discussed in SECY-00-0145, ``Integrated Rulemaking Plan for Nuclear 
Power Plant Decommissioning'' (ADAMS Accession No. ML003721626), such 
as the graded approach to emergency preparedness (EP); lessons learned 
from the plants that have already (or are currently) going through the 
decommissioning process; the

[[Page 13779]]

advisability of requiring a licensee's Post-Shutdown Decommissioning 
Activities Report (PSDAR) to be approved by the NRC; the 
appropriateness of maintaining the three existing options for 
decommissioning and the timeframes associated with those options; the 
appropriate role of state and local governments and non-governmental 
stakeholders in the decommissioning process; and any other issues 
deemed relevant by the NRC.
    The NRC issued an advance notice of proposed rulemaking (ANPR) in 
the Federal Register (80 FR 72358; November 19, 2015) to obtain 
stakeholder feedback on the regulatory issues included in the SRM for 
SECY-14-0118. The NRC received public comments related to each of the 
regulatory issues outlined in the ANPR. Most public feedback pertained 
to the level of public involvement in the decommissioning process, the 
60-year limit for power reactor decommissioning, whether the NRC should 
approve the PSDAR, EP considerations, and the use of the 
decommissioning trust funds (DTFs). The NRC reviewed the comments and 
used input received from the comments to develop the options presented 
in the draft regulatory basis.
    In the draft regulatory basis, the NRC staff concludes that it has 
sufficient justification to proceed with rulemaking in the areas of EP, 
physical security, DTFs, offsite and onsite financial protection 
requirements and indemnity agreements, and application of the backfit 
rule. As stated previously, the NRC staff included all of these areas 
in the ANPR and received stakeholder feedback. Further, the NRC staff 
is recommending rulemaking to: (1) Require that the PSDAR contain a 
description of how the spent fuel stored under a general independent 
spent fuel storage installation license will be removed from the 
reactor site in accordance with the regulatory requirements in Sec.  
50.82 of title 10 of the Code of Federal Regulations (10 CFR), 
``Termination of License,'' 10 CFR 50.54(bb), ``Conditions of 
Licenses,'' 10 CFR 52.110, ``Termination of License,'' and/or 10 CFR 
72.218, ``Termination of Licenses;'' and (2) amend 10 CFR 51.53, 
``Postconstruction Environmental Reports,'' and 10 CFR 51.95, 
``Postconstruction Environmental Impact Statements,'' to clarify that 
the requirements for a license amendment before decommissioning 
activities may commence applies only to non-power reactors, as 
specified in 10 CFR 50.82(b), ``Termination of License,'' in accordance 
with the 1996 final rule that amended the NRC's decommissioning 
regulations (61 FR 39278).
    At this time, the NRC staff has determined that additional 
stakeholder input is needed prior to finalizing recommendations related 
to cyber security, drug and alcohol testing, certified fuel handler 
training and minimum staffing, aging management, and fatigue 
management. The NRC received comments in these areas from the ANPR and 
intends to seek specific public input on these topics as part of the 
public comment request on the entire draft regulatory basis.
    In the draft regulatory basis, the NRC staff concludes that 
regulatory activities other than rulemaking--such as guidance 
development--should be used to address concerns expressed in comments 
received on the ANPR regarding the appropriate role of State and local 
governments in the decommissioning process, the level of NRC review and 
approval of the PSDAR, and the 60 year limit for power reactor 
decommissioning. The NRC is requesting public comment on the draft 
regulatory basis and its associated appendices. To supplement the draft 
regulatory basis, the NRC is preparing a preliminary draft regulatory 
analysis, which will be made available for public comment in the near 
future.

III. Request for Comment

    The NRC is requesting comment on the draft regulatory basis, 
``Regulatory Improvements for Reactors Transitioning to 
Decommissioning.'' As you prepare your comments, consider the following 
general questions:
    1. Is the NRC considering appropriate options for each regulatory 
area described in the draft regulatory basis?
    2. Are there additional factors that the NRC should consider in 
each regulatory area? What are these factors?
    3. Are there any additional options that the NRC should consider 
during development of the proposed rule?
    4. Is there additional information concerning regulatory impacts 
that NRC should include in its regulatory basis for this rulemaking?

Specific Regulatory Issues

    In addition to these general questions, the NRC has identified 
additional areas of consideration that either could be included in the 
scope of the power reactor decommissioning rulemaking or addressed 
through other actions. The NRC may include additional discussion of 
these issues in the final regulatory basis, and if included, will use 
any public comments received regarding these issues to inform the 
development of the final regulatory basis. The NRC requests that 
members of the public answer the following specific questions regarding 
these additional regulatory issues.

Foreign Ownership, Control, or Domination (FOCD) Exemptions for 
Facilities in Decommissioning

    A licensee in decommissioning may desire to transfer their license 
under 10 CFR part 50, ``Domestic Licensing of Production and 
Utilization Facilities,'' to another entity to perform the 
decommissioning activities described in the licensee's PSDAR. However, 
pursuant to Sec.  50.38, ``Ineligibility of Certain Applicants,'' the 
receiving entity is ineligible to obtain the license if it is a 
citizen, national, or agent of a foreign country or if it is any 
corporation or other entity which the Commission knows or has reason to 
believe is owned, controlled, or dominated by an alien, a foreign 
corporation, or a foreign government. The NRC has granted exemptions 
from this requirement for facilities that have been dismantled and 
removed, such that only independent spent fuel storage installations 
remained onsite (78 FR 58571; September 24, 2013).
    5. Should the NRC address the exemption to Sec.  50.38 for 
licensees of facilities in decommissioning on a generic basis as a part 
of this rulemaking? If so, why, and how should the NRC address this 
issue?

Potential Changes to 10 CFR Part 37

    Both operating and decommissioning power reactor licensees are 
subject to the physical protection programs contained in Sec.  73.55, 
``Requirements for physical protection of licensed activities in 
nuclear power reactors against radiological sabotage,'' of 10 CFR part 
73, ``Physical Protection of Plants and Materials;'' appendix B, 
``General Criteria for Security Personnel,'' to 10 CFR part 73; and 
appendix C, ``Licensee Safeguards Contingency Plans,'' to 10 CFR part 
73. These licensees are also subject to 10 CFR part 37, ``Physical 
Protection of Category 1 and Category 2 Quantities of Radioactive 
Material,'' if they possess category 1 and category 2 quantities of 
radioactive material. Therefore, these licensees are potentially 
subject to both 10 CFR part 73 and 10 CFR part 37 security regulations.
    The NRC issued the regulations in 10 CFR part 37 to establish 
security requirements for the use and transport of risk significant 
quantities of category 1 and category 2 radioactive material. Category 
1 and category 2 thresholds of radioactive materials in 10 CFR part 37 
are consistent with similar categories of

[[Page 13780]]

radioactive materials established by the International Atomic Energy 
Agency in its Code of Conduct on the Safety and Security of Radioactive 
Sources (available at http://www-ns.iaea.org/tech-areas/radiation-safety/code-of-conduct.asp (last visited on February 10, 2017)).
    The objective of 10 CFR part 37 is to provide reasonable assurance 
that licensees can prevent the theft or diversion of category 1 and 
category 2 quantities of radioactive material. The current 10 CFR part 
37 regulation is applicable to any licensee that possesses an 
aggregated category 1 or category 2 quantity of radioactive material, 
any licensee that transports these materials using ground 
transportation, and any licensee that transports small quantities of 
irradiated reactor fuel.
    To address the potential impact of redundant security regulations 
during decommissioning, the NRC is considering revising security 
regulations, including addressing the physical security requirements 
for category 1 and category 2 materials at facilities undergoing 
decommissioning.
    6. Are the physical security protection programs in 10 CFR part 37 
an area of regulation that the NRC should address in this rulemaking? 
If so, why, and how should the NRC address this issue?
    7. Should 10 CFR part 50 licensees transitioning from an operating 
status to decommissioning status be provided specific physical security 
requirements in 10 CFR part 37 for category 1 and category 2 materials, 
based on their decommissioning status (i.e., in DECON, SAFSTOR, and 
ENTOMB)?
    8. Should the NRC establish specific security requirements for the 
storage of category 1 and category 2 materials contained in large 
components, robust structures, and in other equipment that are not 
likely to be subject to theft and diversion due to their inherent self-
protecting features (i.e., large physical size and weight)?
    9. Is a clarification of the exemption in Sec.  37.11(b) needed 
with respect to facilities with 10 CFR part 73 security plans that are 
undergoing decommissioning?

Specific Questions Regarding Appendix F, ``Decommissioning Trust 
Funds,'' of the Draft Regulatory Basis

    In addition to the options proposed in Appendix F of the draft 
regulatory basis, the NRC is considering an option to amend the 
regulations in Sec.  50.75, ``Reporting and Recordkeeping for 
Decommissioning Planning,'' to require each power reactor licensee to 
provide and assure to a site-specific cost estimate that is reviewed by 
the NRC at initial licensing, throughout operations, and while in 
decommissioning. A future licensee would provide at licensing site-
specific decommissioning plans, including an initial site-specific cost 
estimate that captures the major assumptions, major decommissioning 
activities, references, and any other bases used to develop this 
estimate. Each plan would address how the cost estimate will be 
adjusted for future cost escalation, the mechanism to be established 
for funding, and a schedule for periodic contributions and assumptions 
about future decommissioning trust fund growth (e.g., 2 percent real-
rate of return). During operations, each licensee would update the 
initial site-specific cost estimate periodically to account for cost 
escalation and any changes in assumptions that may result in increased 
decommissioning costs (i.e., years 1-35 at 5 year intervals; annually 
thereafter). Should this option be considered, the NRC would recommend 
the following:
    a. The Table of Minimum Amounts in Sec.  50.75(b) would continue to 
require certification of a site-specific decommissioning cost estimate 
that meets, or exceeds, the NRC minimum formula amount.
    b. Implementation Period: The NRC would recommend that current 
licensees be provided the biennial (2 year) status report period with 
an additional year to provide and assure to the site-specific 
decommissioning plan referenced herein.
    10. Should this area of the regulations be addressed in this 
rulemaking? If so, why, and how should the NRC address this issue?

Onsite and Offsite Liability Insurance During Decommissioning

    The NRC staff is considering a proposal to adjust the amounts of 
primary liability insurance that power reactor licensees in 
decommissioning must maintain. The current practice is to exempt these 
licensees from the Sec.  140.11 requirements (for offsite insurance) 
and Sec.  50.54(w) (for onsite insurance) so that the amount of offsite 
and onsite insurance corresponds to the risks of a decommissioning 
plant. The NRC staff would use this rulemaking to establish regulations 
for licensees in decommissioning to preclude the need for these 
licensees to request exemptions. The NRC staff is considering using the 
amounts approved in several previous exemption actions and adjusting 
those amounts for inflation.
    11. If the NRC takes this approach, should the NRC apply this 
requirement to licensees who already have exemptions from insurance 
requirements and whose levels of insurance have not been adjusted for 
inflation?

Specific Question Regarding Security Plan Changes During 
Decommissioning

    Operating reactor licensees that are decommissioning may use the 
Sec.  50.54(p)(2) process to implement changes to their site security 
plans (e.g., removal of barriers, reduction of vital areas and armed 
response team members) that do not decrease the safeguards 
effectiveness of their plans. After the licensee has implemented the 
changes to their security plans and submitted the required report of 
the changes, the NRC staff practice is to review these reports to 
ensure that the licensee has properly adhered to the requirements of 
Sec.  50.54(p)(2) and not implemented a change that decreases the 
safeguards effectiveness of its security plans. Although not 
specifically required by regulation, licensees have typically included 
in their submitted reports information demonstrating that these changes 
do not constitute a decrease in safeguards effectiveness. However, 
submission of this additional information currently is not a regulatory 
requirement.
    The NRC staff further notes that the change process in Sec.  
50.54(p)(2) is complicated for both licensees and the NRC staff by the 
fact that the term ``decrease in safeguards effectiveness'' is not 
defined in our regulations. Accordingly, the NRC is considering adding 
the following definition to Sec.  50.2, ``Definitions,'' or to Sec.  
50.54(p)(2): A decrease in the safeguards effectiveness of a security 
plan is a change or series of changes to the security plan that reduces 
or eliminates the licensee's ability to perform or maintain the 
security function that was previously performed or provided by the 
changed element or component without compensating changes to other 
security plan elements or components.
    12. The NRC staff requests public comments on the following 
options.
    Option 1, no change. Decommissioning licensees continue to 
implement security plan changes that do not decrease safeguards 
effectiveness using the provisions of Sec.  50.54(p)(2), reporting 
changes to the NRC within 2 months. If the NRC staff is unable to 
verify the licensee's safeguards effectiveness determination through a 
review of the submitted report, the NRC staff would continue to follow 
up on the changes through the inspection process.
    Option 2, develop regulatory guidance associated with 
decommissioning

[[Page 13781]]

reactor security plan changes to provide licensees guidance for making 
security plan changes that do and do not decrease the safeguards 
effectiveness of the plan.
    Option 3, revise the requirements in Sec.  50.54(p) to include the 
aforementioned definition of safeguards effectiveness and revise the 
specific requirements in Sec.  50.54(p)(2) to more closely reflect the 
wording found in Sec.  50.54(q), ``Emergency Plans,'' specifically 
within paragraphs 50.54(q)(3) and (5).
    13. Which option should the NRC pursue to address this issue?

Specific Question Regarding the Community Advisory Board (CAB)

    Although not a regulatory requirement, to date all decommissioning 
licensees have created some form of a community advisory board, with 
membership and activity levels commensurate with the overall level of 
public interest in the decommissioning activities at the facility. 
Currently, the staff doesn't have a compelling safety basis to 
recommend an option for rulemaking regarding the licensee's 
establishment of a community advisory board.
    14. The staff is seeking public comment on how such a requirement 
might constitute a cost-justified, substantial increase in protection 
of the public health and safety or the common defense and security.

IV. Cumulative Effects of Regulation

    The cumulative effects of regulation (CER) describe the challenges 
that licensees or other impacted entities (such as State agency 
partners) may face while implementing new regulatory positions, 
programs, and requirements (e.g., rules, generic letters, backfits, 
inspections). The CER is an organizational effectiveness challenge that 
results from a licensee or impacted entity implementing a number of 
complex positions, programs, or requirements within a limited 
implementation period and with available resources (which may include 
limited available expertise to address a specific issue). The NRC has 
implemented CER enhancements to the rulemaking process to facilitate 
public involvement throughout the rulemaking process. Therefore, the 
NRC is specifically requesting comment on the cumulative effects that 
may result from this proposed rulemaking. In developing comments on the 
draft regulatory basis, consider the following questions:
    (1) In light of any current or projected CER challenges, what 
should be a reasonable effective date, compliance date, or submittal 
date(s) from the time the final rule is published to the actual 
implementation of any new proposed requirements, including changes to 
programs, procedures, or the facility?
    (2) If current or projected CER challenges exist, what should be 
done to address this situation (e.g., if more time is required to 
implement the new requirements, what period of time would be 
sufficient, and why such a time frame is necessary)?
    (3) Do other regulatory actions (e.g., orders, generic 
communications, license amendment requests, and inspection findings of 
a generic nature) by the NRC or other agencies influence the 
implementation of the potential proposed requirements?
    (4) Are there unintended consequences? Does the potential proposed 
action create conditions that would be contrary to the potential 
proposed action's purpose and objectives? If so, what are the 
consequences and how should they be addressed?
    (5) Please provide information on the costs and benefits of the 
potential proposed action. This information will be used to support 
additional regulatory analysis by the NRC.

V. Availability of Documents

    The NRC may post additional materials related to this rulemaking 
activity to the Federal rulemaking Web site at www.regulations.gov 
under Docket ID NRC-2015-0070. These documents will inform the public 
of the current status of this activity and/or provide additional 
material for use at future public meetings.
    The Federal rulemaking Web site allows you to receive alerts when 
changes or additions occur in a docket folder. To subscribe: (1) 
Navigate to the docket folder (NRC-2015-0070); (2) click the ``Sign up 
for Email Alerts'' link; and (3) enter your email address and select 
how frequently you would like to receive emails (daily, weekly, or 
monthly).
    The documents identified in the following table are available to 
interested persons through one or more of the methods listed in the 
ADDRESSES section of this document.

------------------------------------------------------------------------
                                    ADAMS Accession No./web link/Federal
             Document                        Register citation
------------------------------------------------------------------------
SECY-14-0118, ``Request by Duke    ML14364A111.
 Energy Florida, Inc., for
 Exemptions from Certain
 Emergency Planning
 Requirements,'' December 30,
 2014.
SECY-00-0145--``Integrated         ML003721626.
 Rulemaking Plan for Nuclear
 Power Plant Decommissioning,''
 June 28, 2000..
Federal Register notice,           80 FR 72358.
 ``Advance Notice of Proposed
 Rulemaking: Regulatory
 Improvements for Decommissioning
 Power Reactors,'' November 19,
 2015.
Federal Register notice, ``Maine   78 FR 58571.
 Yankee Atomic Power Company,
 Connecticut Yankee Atomic Power
 Company, and The Yankee Atomic
 Electric Company,'' September
 24, 2013.
Code of Conduct on the Safety and  http://www-ns.iaea.org/tech-areas/
 Security of Radioactive Sources,   radiation-safety/code-of-
 September 8, 2003.                 conduct.asp.
------------------------------------------------------------------------

VI. Plain Writing

    The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal 
agencies to write documents in a clear, concise, 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 in the Federal Register on June 10, 
1998 (63 FR 31883). The NRC requests comment on this document with 
respect to the clarity and effectiveness of the language used.

    Dated at Rockville, Maryland, this 10th day of March 2017.

    For the Nuclear Regulatory Commission.
Louise Lund,
Director, Division of Policy and Rulemaking, Office of Nuclear Reactor 
Regulation.
[FR Doc. 2017-05141 Filed 3-14-17; 8:45 am]
 BILLING CODE 7590-01-P



                                                 13778

                                                 Proposed Rules                                                                                                Federal Register
                                                                                                                                                               Vol. 82, No. 49

                                                                                                                                                               Wednesday, March 15, 2017



                                                 This section of the FEDERAL REGISTER                      For additional direction on obtaining               B. Submitting Comments
                                                 contains notices to the public of the proposed          information and submitting comments,                    Please include Docket ID NRC–2015–
                                                 issuance of rules and regulations. The                  see ‘‘Obtaining Information and
                                                 purpose of these notices is to give interested                                                                0070 in your comment submission. If
                                                                                                         Submitting Comments’’ in the                          you cannot submit your comments on
                                                 persons an opportunity to participate in the            SUPPLEMENTARY INFORMATION section of
                                                 rule making prior to the adoption of the final                                                                the Federal rulemaking Web site,
                                                 rules.
                                                                                                         this document.                                        www.regulations.gov, then contact one
                                                                                                         FOR FURTHER INFORMATION CONTACT:                      of the individuals listed in the FOR
                                                                                                         Alysia G. Bone, telephone: 301–415–                   FURTHER INFORMATION CONTACT section of
                                                 NUCLEAR REGULATORY                                      1034, email: Alysia.Bone@nrc.gov; or                  this document.
                                                 COMMISSION                                              Jennifer C. Tobin, telephone: 301–415–                  The NRC cautions you not to include
                                                                                                         2328, email: Jennifer.Tobin@nrc.gov.                  identifying or contact information that
                                                 10 CFR Parts 26, 50, 52, 73, and 140                                                                          you do not want to be publicly
                                                                                                         Both are staff of the Office of Nuclear
                                                 [NRC–2015–0070]                                         Reactor Regulation, U.S. Nuclear                      disclosed in your comment submission.
                                                                                                         Regulatory Commission, Washington,                    The NRC will post all comment
                                                 RIN 3150–AJ59                                                                                                 submissions at http://
                                                                                                         DC 20555–0001.
                                                                                                                                                               www.regulations.gov as well as enter the
                                                 Regulatory Improvements for Power                       SUPPLEMENTARY INFORMATION:                            comment submissions into ADAMS.
                                                 Reactors Transitioning to                                                                                     The NRC does not routinely edit
                                                 Decommissioning                                         Table of Contents
                                                                                                                                                               comment submissions to remove
                                                                                                         I. Obtaining Information and Submitting               identifying or contact information.
                                                 AGENCY: Nuclear Regulatory                                    Comments
                                                 Commission.                                                                                                     If you are requesting or aggregating
                                                                                                         II. Discussion
                                                                                                                                                               comments from other persons for
                                                 ACTION: Draft regulatory basis; request                 III. Specific Requests for Comments
                                                                                                         IV. Cumulative Effects of Regulation                  submission to the NRC, then you should
                                                 for comment.
                                                                                                         V. Availability of Documents                          inform those persons to not include
                                                 SUMMARY:    The U.S. Nuclear Regulatory                 VI. Plain Writing                                     identifying or contact information that
                                                 Commission (NRC) is requesting                                                                                they do not want to be publicly
                                                                                                         I. Obtaining Information and                          disclosed in their comment submission.
                                                 comments on a draft regulatory basis to                 Submitting Comments
                                                 support a rulemaking that would amend                                                                         Your request should state that the NRC
                                                 NRC’s regulations for the                               A. Obtaining Information                              does not routinely edit comment
                                                 decommissioning of nuclear power                                                                              submissions to remove such information
                                                 reactors. The NRC’s goals in amending                      Please refer to Docket ID NRC–2015–                before making the comment
                                                 these regulations would be to provide                   0070 when contacting the NRC about                    submissions available to the public or
                                                 for an efficient decommissioning                        the availability of information for this              entering the comment into ADAMS.
                                                 process; reduce the need for exemptions                 action. You may obtain publicly-                      Please note that the NRC will not
                                                 from existing regulations; address other                available information related to this                 provide formal written responses to
                                                 decommissioning issues deemed                           action by any of the following methods:               each of the comments received on the
                                                 relevant by the NRC staff; and support                     • Federal Rulemaking Web site: Go to               draft regulatory basis. However, the
                                                 the principles of good regulation,                      http://www.regulations.gov and search                 NRC staff will consider all comments
                                                 including openness, clarity, and                        for Docket ID NRC–2015–0070.                          received in the development of the final
                                                 reliability. The NRC plans to hold a                                                                          regulatory basis.
                                                                                                            • NRC’s Agencywide Documents
                                                 public meeting to discuss the draft                     Access and Management System                          II. Discussion
                                                 regulatory basis and facilitate public                  (ADAMS): You may obtain publicly-
                                                 comment.                                                                                                         On December 30, 2014, in the staff
                                                                                                         available documents online in the                     requirements memorandum (SRM) for
                                                 DATES:  Submit comments by June 13,                     ADAMS Public Documents collection at                  SECY–14–0118, ‘‘Request by Duke
                                                 2017. Comments received after this date                 http://www.nrc.gov/reading-rm/                        Energy Florida, Inc., for Exemptions
                                                 will be considered if it is practical to do             adams.html. To begin the search, select               from Certain Emergency Planning
                                                 so, but the NRC is only able to ensure                  ‘‘ADAMS Public Documents’’ and then                   Requirements’’ (ADAMS Accession No.
                                                 consideration of comments received on                   select ‘‘Begin Web-based ADAMS                        ML14364A111), the Commission
                                                 or before this date.                                    Search.’’ For problems with ADAMS,                    directed the NRC staff to proceed with
                                                 ADDRESSES: You may submit comments                      please contact the NRC’s Public                       a rulemaking on power reactor
                                                 by the following method:                                Document Room (PDR) reference staff at                decommissioning. The Commission also
                                                   • Federal Rulemaking Web site: Go to                  1–800–397–4209, 301–415–4737, or by                   stated that the rulemaking should
                                                 http://www.regulations.gov and search                   email to pdr.resource@nrc.gov. The draft              address: Issues discussed in SECY–00–
                                                                                                         regulatory basis document is available
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                                                 for Docket ID NRC–2015–0070. Address                                                                          0145, ‘‘Integrated Rulemaking Plan for
                                                 questions about NRC dockets to Carol                    in ADAMS under Accession No.                          Nuclear Power Plant Decommissioning’’
                                                 Gallagher; telephone: 301–415–3463;                     ML17047A413.                                          (ADAMS Accession No. ML003721626),
                                                 email: Carol.Gallagher@nrc.gov. For                        • NRC’s PDR: You may examine and                   such as the graded approach to
                                                 technical questions contact the                         purchase copies of public documents at                emergency preparedness (EP); lessons
                                                 individuals listed in the FOR FURTHER                   the NRC’s PDR, Room O1–F21, One                       learned from the plants that have
                                                 INFORMATION CONTACT section of this                     White Flint North, 11555 Rockville                    already (or are currently) going through
                                                 document.                                               Pike, Rockville, Maryland 20852.                      the decommissioning process; the


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                                                                       Federal Register / Vol. 82, No. 49 / Wednesday, March 15, 2017 / Proposed Rules                                             13779

                                                 advisability of requiring a licensee’s                  amended the NRC’s decommissioning                     requests that members of the public
                                                 Post-Shutdown Decommissioning                           regulations (61 FR 39278).                            answer the following specific questions
                                                 Activities Report (PSDAR) to be                           At this time, the NRC staff has                     regarding these additional regulatory
                                                 approved by the NRC; the                                determined that additional stakeholder                issues.
                                                 appropriateness of maintaining the three                input is needed prior to finalizing
                                                                                                                                                               Foreign Ownership, Control, or
                                                 existing options for decommissioning                    recommendations related to cyber
                                                                                                                                                               Domination (FOCD) Exemptions for
                                                 and the timeframes associated with                      security, drug and alcohol testing,
                                                                                                                                                               Facilities in Decommissioning
                                                 those options; the appropriate role of                  certified fuel handler training and
                                                 state and local governments and non-                    minimum staffing, aging management,                      A licensee in decommissioning may
                                                 governmental stakeholders in the                        and fatigue management. The NRC                       desire to transfer their license under 10
                                                 decommissioning process; and any                        received comments in these areas from                 CFR part 50, ‘‘Domestic Licensing of
                                                 other issues deemed relevant by the                     the ANPR and intends to seek specific                 Production and Utilization Facilities,’’
                                                 NRC.                                                    public input on these topics as part of               to another entity to perform the
                                                    The NRC issued an advance notice of                  the public comment request on the                     decommissioning activities described in
                                                 proposed rulemaking (ANPR) in the                       entire draft regulatory basis.                        the licensee’s PSDAR. However,
                                                 Federal Register (80 FR 72358;                            In the draft regulatory basis, the NRC              pursuant to § 50.38, ‘‘Ineligibility of
                                                 November 19, 2015) to obtain                            staff concludes that regulatory activities            Certain Applicants,’’ the receiving entity
                                                 stakeholder feedback on the regulatory                  other than rulemaking—such as                         is ineligible to obtain the license if it is
                                                 issues included in the SRM for SECY–                    guidance development—should be used                   a citizen, national, or agent of a foreign
                                                 14–0118. The NRC received public                        to address concerns expressed in                      country or if it is any corporation or
                                                 comments related to each of the                         comments received on the ANPR                         other entity which the Commission
                                                 regulatory issues outlined in the ANPR.                 regarding the appropriate role of State               knows or has reason to believe is
                                                 Most public feedback pertained to the                   and local governments in the                          owned, controlled, or dominated by an
                                                 level of public involvement in the                      decommissioning process, the level of                 alien, a foreign corporation, or a foreign
                                                 decommissioning process, the 60-year                    NRC review and approval of the PSDAR,                 government. The NRC has granted
                                                 limit for power reactor                                 and the 60 year limit for power reactor               exemptions from this requirement for
                                                 decommissioning, whether the NRC                        decommissioning. The NRC is                           facilities that have been dismantled and
                                                 should approve the PSDAR, EP                            requesting public comment on the draft                removed, such that only independent
                                                 considerations, and the use of the                      regulatory basis and its associated                   spent fuel storage installations remained
                                                 decommissioning trust funds (DTFs).                     appendices. To supplement the draft                   onsite (78 FR 58571; September 24,
                                                 The NRC reviewed the comments and                       regulatory basis, the NRC is preparing a              2013).
                                                 used input received from the comments                   preliminary draft regulatory analysis,                   5. Should the NRC address the
                                                 to develop the options presented in the                 which will be made available for public               exemption to § 50.38 for licensees of
                                                 draft regulatory basis.                                 comment in the near future.                           facilities in decommissioning on a
                                                    In the draft regulatory basis, the NRC                                                                     generic basis as a part of this
                                                 staff concludes that it has sufficient                  III. Request for Comment                              rulemaking? If so, why, and how should
                                                 justification to proceed with rulemaking                   The NRC is requesting comment on                   the NRC address this issue?
                                                 in the areas of EP, physical security,                  the draft regulatory basis, ‘‘Regulatory              Potential Changes to 10 CFR Part 37
                                                 DTFs, offsite and onsite financial                      Improvements for Reactors
                                                 protection requirements and indemnity                   Transitioning to Decommissioning.’’ As                  Both operating and decommissioning
                                                 agreements, and application of the                      you prepare your comments, consider                   power reactor licensees are subject to
                                                 backfit rule. As stated previously, the                 the following general questions:                      the physical protection programs
                                                 NRC staff included all of these areas in                   1. Is the NRC considering appropriate              contained in § 73.55, ‘‘Requirements for
                                                 the ANPR and received stakeholder                       options for each regulatory area                      physical protection of licensed activities
                                                 feedback. Further, the NRC staff is                     described in the draft regulatory basis?              in nuclear power reactors against
                                                 recommending rulemaking to: (1)                            2. Are there additional factors that the           radiological sabotage,’’ of 10 CFR part
                                                 Require that the PSDAR contain a                        NRC should consider in each regulatory                73, ‘‘Physical Protection of Plants and
                                                 description of how the spent fuel stored                area? What are these factors?                         Materials;’’ appendix B, ‘‘General
                                                 under a general independent spent fuel                     3. Are there any additional options                Criteria for Security Personnel,’’ to 10
                                                 storage installation license will be                    that the NRC should consider during                   CFR part 73; and appendix C, ‘‘Licensee
                                                 removed from the reactor site in                        development of the proposed rule?                     Safeguards Contingency Plans,’’ to 10
                                                 accordance with the regulatory                             4. Is there additional information                 CFR part 73. These licensees are also
                                                 requirements in § 50.82 of title 10 of the              concerning regulatory impacts that NRC                subject to 10 CFR part 37, ‘‘Physical
                                                 Code of Federal Regulations (10 CFR),                   should include in its regulatory basis for            Protection of Category 1 and Category 2
                                                 ‘‘Termination of License,’’ 10 CFR                      this rulemaking?                                      Quantities of Radioactive Material,’’ if
                                                 50.54(bb), ‘‘Conditions of Licenses,’’ 10                                                                     they possess category 1 and category 2
                                                 CFR 52.110, ‘‘Termination of License,’’                 Specific Regulatory Issues                            quantities of radioactive material.
                                                 and/or 10 CFR 72.218, ‘‘Termination of                    In addition to these general questions,             Therefore, these licensees are
                                                 Licenses;’’ and (2) amend 10 CFR 51.53,                 the NRC has identified additional areas               potentially subject to both 10 CFR part
                                                 ‘‘Postconstruction Environmental                        of consideration that either could be                 73 and 10 CFR part 37 security
                                                 Reports,’’ and 10 CFR 51.95,                            included in the scope of the power                    regulations.
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                                                 ‘‘Postconstruction Environmental                        reactor decommissioning rulemaking or                   The NRC issued the regulations in 10
                                                 Impact Statements,’’ to clarify that the                addressed through other actions. The                  CFR part 37 to establish security
                                                 requirements for a license amendment                    NRC may include additional discussion                 requirements for the use and transport
                                                 before decommissioning activities may                   of these issues in the final regulatory               of risk significant quantities of category
                                                 commence applies only to non-power                      basis, and if included, will use any                  1 and category 2 radioactive material.
                                                 reactors, as specified in 10 CFR 50.82(b),              public comments received regarding                    Category 1 and category 2 thresholds of
                                                 ‘‘Termination of License,’’ in                          these issues to inform the development                radioactive materials in 10 CFR part 37
                                                 accordance with the 1996 final rule that                of the final regulatory basis. The NRC                are consistent with similar categories of


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                                                 13780                 Federal Register / Vol. 82, No. 49 / Wednesday, March 15, 2017 / Proposed Rules

                                                 radioactive materials established by the                initial licensing, throughout operations,             to licensees who already have
                                                 International Atomic Energy Agency in                   and while in decommissioning. A future                exemptions from insurance
                                                 its Code of Conduct on the Safety and                   licensee would provide at licensing site-             requirements and whose levels of
                                                 Security of Radioactive Sources                         specific decommissioning plans,                       insurance have not been adjusted for
                                                 (available at http://www-ns.iaea.org/                   including an initial site-specific cost               inflation?
                                                 tech-areas/radiation-safety/code-of-                    estimate that captures the major
                                                                                                                                                               Specific Question Regarding Security
                                                 conduct.asp (last visited on February                   assumptions, major decommissioning
                                                                                                                                                               Plan Changes During Decommissioning
                                                 10, 2017)).                                             activities, references, and any other
                                                    The objective of 10 CFR part 37 is to                bases used to develop this estimate.                     Operating reactor licensees that are
                                                 provide reasonable assurance that                       Each plan would address how the cost                  decommissioning may use the
                                                 licensees can prevent the theft or                      estimate will be adjusted for future cost             § 50.54(p)(2) process to implement
                                                 diversion of category 1 and category 2                  escalation, the mechanism to be                       changes to their site security plans (e.g.,
                                                 quantities of radioactive material. The                 established for funding, and a schedule               removal of barriers, reduction of vital
                                                 current 10 CFR part 37 regulation is                    for periodic contributions and                        areas and armed response team
                                                 applicable to any licensee that possesses               assumptions about future                              members) that do not decrease the
                                                 an aggregated category 1 or category 2                  decommissioning trust fund growth                     safeguards effectiveness of their plans.
                                                 quantity of radioactive material, any                   (e.g., 2 percent real-rate of return).                After the licensee has implemented the
                                                 licensee that transports these materials                During operations, each licensee would                changes to their security plans and
                                                 using ground transportation, and any                    update the initial site-specific cost                 submitted the required report of the
                                                 licensee that transports small quantities               estimate periodically to account for cost             changes, the NRC staff practice is to
                                                 of irradiated reactor fuel.                             escalation and any changes in                         review these reports to ensure that the
                                                    To address the potential impact of                   assumptions that may result in                        licensee has properly adhered to the
                                                 redundant security regulations during                   increased decommissioning costs (i.e.,                requirements of § 50.54(p)(2) and not
                                                 decommissioning, the NRC is                             years 1–35 at 5 year intervals; annually              implemented a change that decreases
                                                 considering revising security                           thereafter). Should this option be                    the safeguards effectiveness of its
                                                 regulations, including addressing the                   considered, the NRC would recommend                   security plans. Although not specifically
                                                 physical security requirements for                      the following:                                        required by regulation, licensees have
                                                 category 1 and category 2 materials at                     a. The Table of Minimum Amounts in                 typically included in their submitted
                                                 facilities undergoing decommissioning.                  § 50.75(b) would continue to require                  reports information demonstrating that
                                                    6. Are the physical security protection              certification of a site-specific                      these changes do not constitute a
                                                 programs in 10 CFR part 37 an area of                   decommissioning cost estimate that                    decrease in safeguards effectiveness.
                                                 regulation that the NRC should address                  meets, or exceeds, the NRC minimum                    However, submission of this additional
                                                 in this rulemaking? If so, why, and how                 formula amount.                                       information currently is not a regulatory
                                                 should the NRC address this issue?                         b. Implementation Period: The NRC                  requirement.
                                                    7. Should 10 CFR part 50 licensees                   would recommend that current                             The NRC staff further notes that the
                                                 transitioning from an operating status to               licensees be provided the biennial (2                 change process in § 50.54(p)(2) is
                                                 decommissioning status be provided                      year) status report period with an                    complicated for both licensees and the
                                                 specific physical security requirements                 additional year to provide and assure to              NRC staff by the fact that the term
                                                 in 10 CFR part 37 for category 1 and                    the site-specific decommissioning plan                ‘‘decrease in safeguards effectiveness’’ is
                                                 category 2 materials, based on their                    referenced herein.                                    not defined in our regulations.
                                                 decommissioning status (i.e., in DECON,                    10. Should this area of the regulations            Accordingly, the NRC is considering
                                                 SAFSTOR, and ENTOMB)?                                   be addressed in this rulemaking? If so,               adding the following definition to
                                                    8. Should the NRC establish specific                 why, and how should the NRC address                   § 50.2, ‘‘Definitions,’’ or to § 50.54(p)(2):
                                                 security requirements for the storage of                this issue?                                           A decrease in the safeguards
                                                 category 1 and category 2 materials                                                                           effectiveness of a security plan is a
                                                                                                         Onsite and Offsite Liability Insurance
                                                 contained in large components, robust                                                                         change or series of changes to the
                                                                                                         During Decommissioning
                                                 structures, and in other equipment that                                                                       security plan that reduces or eliminates
                                                 are not likely to be subject to theft and                  The NRC staff is considering a                     the licensee’s ability to perform or
                                                 diversion due to their inherent self-                   proposal to adjust the amounts of                     maintain the security function that was
                                                 protecting features (i.e., large physical               primary liability insurance that power                previously performed or provided by
                                                 size and weight)?                                       reactor licensees in decommissioning                  the changed element or component
                                                    9. Is a clarification of the exemption               must maintain. The current practice is                without compensating changes to other
                                                 in § 37.11(b) needed with respect to                    to exempt these licensees from the                    security plan elements or components.
                                                 facilities with 10 CFR part 73 security                 § 140.11 requirements (for offsite                       12. The NRC staff requests public
                                                 plans that are undergoing                               insurance) and § 50.54(w) (for onsite                 comments on the following options.
                                                 decommissioning?                                        insurance) so that the amount of offsite                 Option 1, no change.
                                                                                                         and onsite insurance corresponds to the               Decommissioning licensees continue to
                                                 Specific Questions Regarding Appendix                   risks of a decommissioning plant. The                 implement security plan changes that
                                                 F, ‘‘Decommissioning Trust Funds,’’ of                  NRC staff would use this rulemaking to                do not decrease safeguards effectiveness
                                                 the Draft Regulatory Basis                              establish regulations for licensees in                using the provisions of § 50.54(p)(2),
                                                    In addition to the options proposed in               decommissioning to preclude the need                  reporting changes to the NRC within 2
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                                                 Appendix F of the draft regulatory basis,               for these licensees to request                        months. If the NRC staff is unable to
                                                 the NRC is considering an option to                     exemptions. The NRC staff is                          verify the licensee’s safeguards
                                                 amend the regulations in § 50.75,                       considering using the amounts                         effectiveness determination through a
                                                 ‘‘Reporting and Recordkeeping for                       approved in several previous exemption                review of the submitted report, the NRC
                                                 Decommissioning Planning,’’ to require                  actions and adjusting those amounts for               staff would continue to follow up on the
                                                 each power reactor licensee to provide                  inflation.                                            changes through the inspection process.
                                                 and assure to a site-specific cost                         11. If the NRC takes this approach,                   Option 2, develop regulatory guidance
                                                 estimate that is reviewed by the NRC at                 should the NRC apply this requirement                 associated with decommissioning


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                                                                       Federal Register / Vol. 82, No. 49 / Wednesday, March 15, 2017 / Proposed Rules                                                  13781

                                                 reactor security plan changes to provide                (such as State agency partners) may face               or other agencies influence the
                                                 licensees guidance for making security                  while implementing new regulatory                      implementation of the potential
                                                 plan changes that do and do not                         positions, programs, and requirements                  proposed requirements?
                                                 decrease the safeguards effectiveness of                (e.g., rules, generic letters, backfits,                 (4) Are there unintended
                                                 the plan.                                               inspections). The CER is an                            consequences? Does the potential
                                                    Option 3, revise the requirements in                 organizational effectiveness challenge                 proposed action create conditions that
                                                 § 50.54(p) to include the aforementioned                that results from a licensee or impacted               would be contrary to the potential
                                                 definition of safeguards effectiveness                  entity implementing a number of                        proposed action’s purpose and
                                                 and revise the specific requirements in                 complex positions, programs, or                        objectives? If so, what are the
                                                 § 50.54(p)(2) to more closely reflect the               requirements within a limited                          consequences and how should they be
                                                 wording found in § 50.54(q),                            implementation period and with                         addressed?
                                                 ‘‘Emergency Plans,’’ specifically within                available resources (which may include                   (5) Please provide information on the
                                                 paragraphs 50.54(q)(3) and (5).                         limited available expertise to address a               costs and benefits of the potential
                                                    13. Which option should the NRC                      specific issue). The NRC has                           proposed action. This information will
                                                 pursue to address this issue?                           implemented CER enhancements to the                    be used to support additional regulatory
                                                                                                         rulemaking process to facilitate public                analysis by the NRC.
                                                 Specific Question Regarding the                         involvement throughout the rulemaking
                                                 Community Advisory Board (CAB)                                                                                 V. Availability of Documents
                                                                                                         process. Therefore, the NRC is
                                                    Although not a regulatory                            specifically requesting comment on the                    The NRC may post additional
                                                 requirement, to date all                                cumulative effects that may result from                materials related to this rulemaking
                                                 decommissioning licensees have created                  this proposed rulemaking. In developing                activity to the Federal rulemaking Web
                                                 some form of a community advisory                       comments on the draft regulatory basis,                site at www.regulations.gov under
                                                 board, with membership and activity                     consider the following questions:                      Docket ID NRC–2015–0070. These
                                                 levels commensurate with the overall                       (1) In light of any current or projected            documents will inform the public of the
                                                 level of public interest in the                         CER challenges, what should be a                       current status of this activity and/or
                                                 decommissioning activities at the                       reasonable effective date, compliance                  provide additional material for use at
                                                 facility. Currently, the staff doesn’t have             date, or submittal date(s) from the time               future public meetings.
                                                 a compelling safety basis to recommend                  the final rule is published to the actual                 The Federal rulemaking Web site
                                                 an option for rulemaking regarding the                  implementation of any new proposed                     allows you to receive alerts when
                                                 licensee’s establishment of a community                 requirements, including changes to                     changes or additions occur in a docket
                                                 advisory board.                                         programs, procedures, or the facility?                 folder. To subscribe: (1) Navigate to the
                                                    14. The staff is seeking public                         (2) If current or projected CER                     docket folder (NRC–2015–0070); (2)
                                                 comment on how such a requirement                       challenges exist, what should be done to               click the ‘‘Sign up for Email Alerts’’
                                                 might constitute a cost-justified,                      address this situation (e.g., if more time             link; and (3) enter your email address
                                                 substantial increase in protection of the               is required to implement the new                       and select how frequently you would
                                                 public health and safety or the common                  requirements, what period of time                      like to receive emails (daily, weekly, or
                                                 defense and security.                                   would be sufficient, and why such a                    monthly).
                                                                                                         time frame is necessary)?                                 The documents identified in the
                                                 IV. Cumulative Effects of Regulation                       (3) Do other regulatory actions (e.g.,              following table are available to
                                                    The cumulative effects of regulation                 orders, generic communications, license                interested persons through one or more
                                                 (CER) describe the challenges that                      amendment requests, and inspection                     of the methods listed in the ADDRESSES
                                                 licensees or other impacted entities                    findings of a generic nature) by the NRC               section of this document.

                                                                                                                                                                                   ADAMS Accession No./web
                                                                                                               Document                                                              link/Federal Register
                                                                                                                                                                                            citation

                                                 SECY–14–0118, ‘‘Request by Duke Energy Florida, Inc., for Exemptions from Certain Emergency Planning Re-                          ML14364A111.
                                                   quirements,’’ December 30, 2014.
                                                 SECY–00–0145—‘‘Integrated Rulemaking Plan for Nuclear Power Plant Decommissioning,’’ June 28, 2000. ...........                   ML003721626.
                                                 Federal Register notice, ‘‘Advance Notice of Proposed Rulemaking: Regulatory Improvements for Decommis-                           80 FR 72358.
                                                   sioning Power Reactors,’’ November 19, 2015.
                                                 Federal Register notice, ‘‘Maine Yankee Atomic Power Company, Connecticut Yankee Atomic Power Company,                            78 FR 58571.
                                                   and The Yankee Atomic Electric Company,’’ September 24, 2013.
                                                 Code of Conduct on the Safety and Security of Radioactive Sources, September 8, 2003 .........................................    http://www-ns.iaea.org/tech-
                                                                                                                                                                                      areas/radiation-safety/
                                                                                                                                                                                      code-of-conduct.asp.



                                                 VI. Plain Writing                                       Register on June 10, 1998 (63 FR 31883).                 For the Nuclear Regulatory Commission.
                                                                                                         The NRC requests comment on this                       Louise Lund,
                                                    The Plain Writing Act of 2010                        document with respect to the clarity and               Director, Division of Policy and Rulemaking,
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                                                 (Pub. L. 111–274) requires Federal
                                                                                                         effectiveness of the language used.                    Office of Nuclear Reactor Regulation.
                                                 agencies to write documents in a clear,
                                                 concise, well-organized manner. The                       Dated at Rockville, Maryland, this 10th day          [FR Doc. 2017–05141 Filed 3–14–17; 8:45 am]
                                                 NRC has written this document to be                     of March 2017.                                         BILLING CODE 7590–01–P
                                                 consistent with the Plain Writing Act as
                                                 well as the Presidential Memorandum,
                                                 ‘‘Plain Language in Government
                                                 Writing,’’ published in the Federal


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Document Created: 2017-03-15 06:04:17
Document Modified: 2017-03-15 06:04:17
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionProposed Rules
ActionDraft regulatory basis; request for comment.
DatesSubmit comments by June 13, 2017. Comments received after this date will be considered if it is practical to do so, but the NRC is only able to ensure consideration of comments received on or before this date.
ContactAlysia G. Bone, telephone: 301-415- 1034, email: [email protected]; or Jennifer C. Tobin, telephone: 301- 415-2328, email: [email protected] Both are staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
FR Citation82 FR 13778 
RIN Number3150-AJ59
CFR Citation10 CFR 140
10 CFR 26
10 CFR 50
10 CFR 52
10 CFR 73

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