Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents, 37115-37116 [2020-13254]
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Federal Register / Vol. 85, No. 119 / Friday, June 19, 2020 / Notices
for Docket ID NRC–2019–0246. A copy
of the collection of information and
related instructions may be obtained
without charge by accessing Docket ID
NRC–2019–0246 on this website.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, 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 pdr.resource@
nrc.gov. A copy of the collection of
information and related instructions
may be obtained without charge by
accessing ADAMS Accession No.
ML20162A172. The supporting
statement is available in ADAMS under
Accession No. ML20049A689.
• NRC’s Clearance Officer: A copy of
the collection of information and related
instructions may be obtained without
charge by contacting NRC’s Clearance
Officer, David Cullison, Office of the
Chief Information Officer, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
2084; email: Infocollects.Resource@
nrc.gov.
khammond on DSKJM1Z7X2PROD with NOTICES
B. Submitting Comments
Please include Docket ID NRC–2019–
0246 in the subject line of your
comment submission, in order to ensure
that the NRC is able to make your
comment submission available to the
public in this docket.
The NRC cautions you not to include
identifying or contact information in
comment submissions that you do not
want to be publicly disclosed in your
comment submission. The NRC will
post all comment submissions at https://
www.regulations.gov as well as enter the
comment submissions into ADAMS,
and 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 not to 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.
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17:17 Jun 18, 2020
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II. Background
In accordance with the Paperwork
Reduction Act of 1995 (44 U.S.C.
Chapter 35), the NRC is requesting
public comment on its intention to
request the OMB’s approval for the
information collection summarized
below.
1. The title of the information
collection: Comprehensive
Decommissioning Program Annual Site
List and Point of Contact.
2. OMB approval number: 3150–0206.
3. Type of submission: Revision.
4. The form number, if applicable: N/
A.
5. How often the collection is required
or requested: Annually.
6. Who will be required or asked to
respond: All Agreement States that have
signed Section 274(b) Agreements with
the NRC.
7. The estimated number of annual
responses: 39 (14 responses from
Agreement States with sites undergoing
decommissioning + 25 responses from
Agreement States with no sites
undergoing decommissioning).
8. The estimated number of annual
respondents: 39 (14 Agreement States
with sites undergoing decommissioning
+ 25 Agreement States with no sites
undergoing decommissioning).
9. The estimated number of hours
needed annually to comply with the
information collection requirement or
request: 40.5 (28 hours for Agreement
States with sites undergoing
decommissioning + 12.5 hours for
Agreement States with no sites
undergoing decommissioning).
10. Abstract: The Agreement States
will be asked to provide a list of
uranium recovery and complex sites
undergoing decommissioning regulated
by their States on an annual basis. The
Agreement States will also be asked to
provide a point of contact who is
cognizant of site status. The information
request will allow the NRC to compile,
in a centralized location, updated
contact information and a list of sites
decommissioning in the United States to
provide a national perspective on
decommissioning. The information will
be made available to the public by the
NRC in order to ensure openness and
promote communication to enhance
public knowledge of the national
decommissioning program.
III. Specific Requests for Comments
The NRC is seeking comments that
address the following questions:
1. Is the proposed collection of
information necessary for the NRC to
properly perform its functions? Does the
information have practical utility?
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37115
2. Is the estimate of the burden of the
information collection accurate?
3. Is there a way to enhance the
quality, utility, and clarity of the
information to be collected?
4. How can the burden of the
information collection on respondents
be minimized, including the use of
automated collection techniques or
other forms of information technology?
Dated: June 16, 2020.
For the Nuclear Regulatory Commission.
David C. Cullison,
NRC Clearance Officer, Office of the Chief
Information Officer.
[FR Doc. 2020–13253 Filed 6–18–20; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2016–0233]
Pressurized-Water Reactor Control
Rod Ejection and Boiling-Water
Reactor Control Rod Drop Accidents
Nuclear Regulatory
Commission.
ACTION: Regulatory guide; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing regulatory
guide (RG) 1.236, ‘‘Pressurized-Water
Reactor Control Rod Ejection and
Boiling-Water Reactor Control Rod Drop
Accidents.’’ This is a new RG that
provides guidance for analyzing control
rod accidents. It defines fuel cladding
failure thresholds for ductile failure,
brittle failure, and pellet-clad
mechanical interaction. It also describes
analytical limits and guidance for
demonstrating compliance with
regulations governing reactivity limits.
RG 1.236 supersedes the guidance for
control rod ejection accidents in RG
1.77, ‘‘Assumptions Used for Evaluation
a Control Rod Ejection Accident for
Pressurized Water Reactors,’’ which is
being withdrawn in conjunction with
the issuance of RG 1.236.
DATES: RG 1.236 is available on June 19,
2020.
ADDRESSES: Please refer to Docket ID
NRC–2016–0233 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly-available
information related to this document
using any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0233. Address
questions about NRC dockets IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
Jennifer.Borges@nrc.gov. For technical
SUMMARY:
E:\FR\FM\19JNN1.SGM
19JNN1
37116
Federal Register / Vol. 85, No. 119 / Friday, June 19, 2020 / Notices
questions, contact the individual listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, 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 pdr.resource@
nrc.gov. RG 1.236 and the regulatory
analysis may be found in ADAMS under
Accession Nos. ML20055F490 and
ML16124A198, respectively.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT: Paul
Clifford, Office of Nuclear Reactor
Regulation, telephone: 301–415–4043,
email: Paul.Clifford@nrc.gov and
Edward O’Donnell, Office of Nuclear
Regulatory Research, telephone: 301–
415–3317, email: Edward.ODonnell@
nrc.gov. Both are staff of the U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
khammond on DSKJM1Z7X2PROD with NOTICES
I. Discussion
The NRC is issuing a new guide in the
NRC’s ‘‘Regulatory Guide’’ series. This
series was developed to describe and
make available to the public information
regarding methods that are acceptable to
the NRC staff for implementing specific
parts of the NRC’s regulations,
techniques that the staff uses in
evaluating specific issues or postulated
events, and information that the staff
needs in its review of applications for
permits and licenses.
The RG, titled ‘‘Pressurized-Water
Reactor Control Rod Ejection and
Boiling-Water Reactor Control Rod Drop
Accidents,’’ describes one acceptable
method for demonstrating compliance
with appendix A of part 50 of title 10
of the Code of Federal Regulations (10
CFR), General Design Criteria (GDC) 28,
‘‘Reactivity Limit,’’ with respect to
control rod ejection (CRE) accidents for
pressurized-water reactors and control
rod drop (CRD) accidents for boilingwater reactors. RG 1.236 provides
guidance for analyzing these reactivityinitiated accidents. It defines fuel
cladding failure thresholds for ductile
failure, brittle failure, and pellet-clad
mechanical interaction. It also describes
analytical limits and guidance for
demonstrating compliance with
regulations governing reactivity limits.
VerDate Sep<11>2014
17:17 Jun 18, 2020
Jkt 250001
The guide incorporates new empirical
data from in-pile, prompt power pulse
test programs and analyses from several
international publications that examine
fuel rod performance under reactivityinitiated accident conditions to provide
guidance on acceptable analytical
methods, assumptions, and limits for
evaluating a CRE and CRD accidents.
The guide supersedes the guidance for
control rod ejection accidents in RG
1.77, ‘‘Assumptions Used for Evaluation
a Control Rod Ejection Accident for
Pressurized Water Reactors,’’ which is
being withdrawn in conjunction with
the issuance of RG 1.236.
II. Additional Information
The NRC issued RG 1.236 as Draft
Guide (DG)-1327 for public comment on
November 21, 2016 (81 FR 83288), with
a 60 day comment period that expired
on February 21, 2017. A public meeting
was held at NRC Headquarters on
January 25, 2017, while the guide was
issued for public comment. During the
meeting NRC made a commitment to
hold a second public meeting to discuss
the staff’s proposed resolution of key
comments prior to finalization of the
guide. Following the public meeting the
NRC extended the comment period to
April 21, 2017 (82 FR 8998), to allow
more time for comment. A second
public meeting was held at NRC
Headquarters on June 5, 2018, to discuss
resolution of the public comments. To
facilitate discussion at the meeting,
drafts of the guide (ADAMS Accession
No. ML18138A459) and a table showing
resolution of the public comments
(ADAMS Accession No. ML18138A458)
were made publicly available.
As a result of the written public
comments and discussion at the two
public meetings, the NRC made several
changes to the draft guide and it was
released a second time for public
comment on July 30, 2019 (84 FR
36961). That comment period ended
November 18, 2019. The guide was
further revised to address the second
round of public comments. The
response to this second round of public
comments is located in ADAMS under
Accession No. ML20055F489. Among
the changes resulting from the two
public meetings and the two rounds of
public comments were: (1) The pelletclad mechanical interaction cladding
failure thresholds were revised; (2) the
appendix that provided acceptable
steady-state and transient fission
product releases was removed; and (3)
the implementation section was revised
to be consistent with recent Commission
direction on backfitting and forward
fitting as found in Management
Directive 8.4 ‘‘Management of
PO 00000
Frm 00057
Fmt 4703
Sfmt 4703
Backfitting, Forward Fitting, Issue
Finality, and Information Requests.’’
III. Congressional Review Act
This RG 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.
IV. Backfitting, Forward Fitting, and
Issue Finality
RG 1.236 describes one acceptable
method for demonstrating compliance
with 10 CFR part 50, appendix A, GDC
28 with respect to CRE accidents for
pressurized-water reactors and CRD
accidents for boiling-water reactors. In
general, issuance of this RG does not
constitute backfitting as defined in 10
CFR 50.109, ‘‘Backfitting,’’ and as
described in NRC Management Directive
8.4; does not constitute forward fitting
as that term is defined and described in
Management Directive 8.4; and does not
affect the issue finality of any approval
issued under 10 CFR part 52, ‘‘Licenses,
Certificates, and Approvals for Nuclear
Power Plants.’’ As explained in this
regulatory guide, applicants and
licensees are not required to comply
with the positions set forth in this RG.
Licensees using RG 1.77 may continue
using that RG. In future requests or
applications for NRC licensing actions
related to the guidance in RG 1.77, those
licensees should use RG 1.236, which
contains the guidance in RG 1.77.
Further information on the staff’s use of
the RG is contained in the RG under
Section D., ‘‘Implementation.’’
Dated: June 16, 2020.
For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guidance and Generic
Issues Branch, Division of Engineering, Office
of Nuclear Regulatory Research.
[FR Doc. 2020–13254 Filed 6–18–20; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–331; NRC–2020–0148]
NextEra Energy Duane Arnold, LLC;
Duane Arnold Energy Center; PostShutdown Decommissioning Activities
Report
Nuclear Regulatory
Commission.
ACTION: Notice of receipt; availability;
public meeting and request for
comment.
AGENCY:
On April 2, 2020, the U.S.
Nuclear Regulatory Commission (NRC)
SUMMARY:
E:\FR\FM\19JNN1.SGM
19JNN1
]]>Agencies
[Federal Register Volume 85, Number 119 (Friday, June 19, 2020)]
[Notices]
[Pages 37115-37116]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2020-13254]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2016-0233]
Pressurized-Water Reactor Control Rod Ejection and Boiling-Water
Reactor Control Rod Drop Accidents
AGENCY: Nuclear Regulatory Commission.
ACTION: Regulatory guide; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing
regulatory guide (RG) 1.236, ``Pressurized-Water Reactor Control Rod
Ejection and Boiling-Water Reactor Control Rod Drop Accidents.'' This
is a new RG that provides guidance for analyzing control rod accidents.
It defines fuel cladding failure thresholds for ductile failure,
brittle failure, and pellet-clad mechanical interaction. It also
describes analytical limits and guidance for demonstrating compliance
with regulations governing reactivity limits. RG 1.236 supersedes the
guidance for control rod ejection accidents in RG 1.77, ``Assumptions
Used for Evaluation a Control Rod Ejection Accident for Pressurized
Water Reactors,'' which is being withdrawn in conjunction with the
issuance of RG 1.236.
DATES: RG 1.236 is available on June 19, 2020.
ADDRESSES: Please refer to Docket ID NRC-2016-0233 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2016-0233. Address
questions about NRC dockets IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
[[Page 37116]]
questions, contact the individual listed in the FOR FURTHER INFORMATION
CONTACT section of this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, 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]. RG 1.236 and the regulatory analysis
may be found in ADAMS under Accession Nos. ML20055F490 and ML16124A198,
respectively.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT: Paul Clifford, Office of Nuclear
Reactor Regulation, telephone: 301-415-4043, email:
[email protected] and Edward O'Donnell, Office of Nuclear
Regulatory Research, telephone: 301-415-3317, email:
[email protected]. Both are staff of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
I. Discussion
The NRC is issuing a new guide in the NRC's ``Regulatory Guide''
series. This series was developed to describe and make available to the
public information regarding methods that are acceptable to the NRC
staff for implementing specific parts of the NRC's regulations,
techniques that the staff uses in evaluating specific issues or
postulated events, and information that the staff needs in its review
of applications for permits and licenses.
The RG, titled ``Pressurized-Water Reactor Control Rod Ejection and
Boiling-Water Reactor Control Rod Drop Accidents,'' describes one
acceptable method for demonstrating compliance with appendix A of part
50 of title 10 of the Code of Federal Regulations (10 CFR), General
Design Criteria (GDC) 28, ``Reactivity Limit,'' with respect to control
rod ejection (CRE) accidents for pressurized-water reactors and control
rod drop (CRD) accidents for boiling-water reactors. RG 1.236 provides
guidance for analyzing these reactivity-initiated accidents. It defines
fuel cladding failure thresholds for ductile failure, brittle failure,
and pellet-clad mechanical interaction. It also describes analytical
limits and guidance for demonstrating compliance with regulations
governing reactivity limits.
The guide incorporates new empirical data from in-pile, prompt
power pulse test programs and analyses from several international
publications that examine fuel rod performance under reactivity-
initiated accident conditions to provide guidance on acceptable
analytical methods, assumptions, and limits for evaluating a CRE and
CRD accidents. The guide supersedes the guidance for control rod
ejection accidents in RG 1.77, ``Assumptions Used for Evaluation a
Control Rod Ejection Accident for Pressurized Water Reactors,'' which
is being withdrawn in conjunction with the issuance of RG 1.236.
II. Additional Information
The NRC issued RG 1.236 as Draft Guide (DG)-1327 for public comment
on November 21, 2016 (81 FR 83288), with a 60 day comment period that
expired on February 21, 2017. A public meeting was held at NRC
Headquarters on January 25, 2017, while the guide was issued for public
comment. During the meeting NRC made a commitment to hold a second
public meeting to discuss the staff's proposed resolution of key
comments prior to finalization of the guide. Following the public
meeting the NRC extended the comment period to April 21, 2017 (82 FR
8998), to allow more time for comment. A second public meeting was held
at NRC Headquarters on June 5, 2018, to discuss resolution of the
public comments. To facilitate discussion at the meeting, drafts of the
guide (ADAMS Accession No. ML18138A459) and a table showing resolution
of the public comments (ADAMS Accession No. ML18138A458) were made
publicly available.
As a result of the written public comments and discussion at the
two public meetings, the NRC made several changes to the draft guide
and it was released a second time for public comment on July 30, 2019
(84 FR 36961). That comment period ended November 18, 2019. The guide
was further revised to address the second round of public comments. The
response to this second round of public comments is located in ADAMS
under Accession No. ML20055F489. Among the changes resulting from the
two public meetings and the two rounds of public comments were: (1) The
pellet-clad mechanical interaction cladding failure thresholds were
revised; (2) the appendix that provided acceptable steady-state and
transient fission product releases was removed; and (3) the
implementation section was revised to be consistent with recent
Commission direction on backfitting and forward fitting as found in
Management Directive 8.4 ``Management of Backfitting, Forward Fitting,
Issue Finality, and Information Requests.''
III. Congressional Review Act
This RG 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.
IV. Backfitting, Forward Fitting, and Issue Finality
RG 1.236 describes one acceptable method for demonstrating
compliance with 10 CFR part 50, appendix A, GDC 28 with respect to CRE
accidents for pressurized-water reactors and CRD accidents for boiling-
water reactors. In general, issuance of this RG does not constitute
backfitting as defined in 10 CFR 50.109, ``Backfitting,'' and as
described in NRC Management Directive 8.4; does not constitute forward
fitting as that term is defined and described in Management Directive
8.4; and does not affect the issue finality of any approval issued
under 10 CFR part 52, ``Licenses, Certificates, and Approvals for
Nuclear Power Plants.'' As explained in this regulatory guide,
applicants and licensees are not required to comply with the positions
set forth in this RG. Licensees using RG 1.77 may continue using that
RG. In future requests or applications for NRC licensing actions
related to the guidance in RG 1.77, those licensees should use RG
1.236, which contains the guidance in RG 1.77. Further information on
the staff's use of the RG is contained in the RG under Section D.,
``Implementation.''
Dated: June 16, 2020.
For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guidance and Generic Issues Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2020-13254 Filed 6-18-20; 8:45 am]
BILLING CODE 7590-01-P
