Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants, 61043-61044 [2017-27661]
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Federal Register / Vol. 82, No. 246 / Tuesday, December 26, 2017 / Notices
simply provided conclusory statements
supporting its position.
NRC response. The NRC disagrees
with this comment. The EA
appropriately considered all
withdrawals from the decommissioning
trust that would be permissible under
the NRC’s regulations and under the
exemptions. Specifically, the EA
considered withdrawals for
decommissioning expenses, which are
permitted by the NRC’s regulations, and
withdrawals for spent fuel management
expenses, which are permitted by the
exemptions. The EA did not consider
withdrawals for any nondecommissioning expenses beyond
spent fuel management expenses,
because such withdrawals are
prohibited by the NRC’s regulations and
are not allowed by the exemptions. In
addition, this scope of the EA is
appropriate because the NRC staff
reviews the status of decommissioning
funds annually during decommissioning
to ensure that adequate funds for
decommissioning are available and that
withdrawals from the decommissioning
fund are for approved purposes. Finally,
the cumulative impacts of
decommissioning were considered in
the Decommissioning GEIS. Therefore,
the EA’s consideration of impacts was
appropriate.
Petitioners comment 1.d. The EA fails
to consider reasonable alternatives. The
only alternative that the NRC staff
evaluated was denying Entergy’s
exemption request. The NRC staff failed
to evaluate other alternatives, such as
granting conditional approval.
NRC response. The NRC disagrees
that the EA fails to consider reasonable
alternatives. The exemptions at issue
here allow Entergy to use funds from the
Trust for the non-decommissioning
expense of irradiated fuel management
activities. This EA evaluates denying
the exemption request as a reasonable
alternative to the action of granting the
exemption request. Consistent with the
NRC’s regulations, imposing conditions
on a licensee is typically done through
the license amendment process and not
through the exemption process;
therefore, the NRC disagrees that it
should have also evaluated as a
reasonable alternative granting
conditional approval of the exemption
request.
Petitioners comment 2. The
publication of the EA after the relevant
decision has already been made does
not comply with NEPA’s requirement
that the analysis occur before a decision
is made. The NRC approved the
exemption request on June 23, 2015, but
published the draft EA and FONSI for
comment on March 8, 2017. The NRC
VerDate Sep<11>2014
20:21 Dec 22, 2017
Jkt 244001
staff relies on the Decommissioning
Financial Status Report from March 30,
2015 to support the EA, when it had a
more recent report from March 30, 2016.
NRC response. The NRC disagrees
with this comment. In CLI–16–17, the
Commission directed the NRC staff ‘‘to
conduct an environmental assessment to
examine the environmental impacts, if
any, associated with the exemption.’’
Although the Commission declined to
reverse the staff’s approval of the
exemption request, it specified that if
the staff’s environmental review ‘‘results
in a determination of significant
impacts, the Staff should promptly
notify [the Commission] and, at that
time, [the Commission] may reconsider
whether the exemption should be stayed
or vacated.’’
The March 30, 2015 Decommissioning
Financial Status Report (ADAMS
Accession No. ML15092A141) was not
needed to support the EA and neither
was the more recent report from March
30, 2016 (ADAMS Accession No.
ML16090A355). The supporting
analysis of the adequacy of the Trust to
provide reasonable assurance of
adequate funding to complete all NRC
required decommissioning activities
and to conduct irradiated fuel
management is described in the June 23,
2015 Federal Register Notice of the
issuance of the exemptions.
III. Finding of No Significant Impact
Entergy proposed exemptions from 10
CFR 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv)
to allow the licensee to use funds from
the Trust for irradiated fuel management
activities. The NRC granted the
exemptions on June 23, 2015.
Consistent with 10 CFR 51.21, the
NRC conducted the EA for the
exemptions included in Section II of
this document and incorporated by
reference into this finding. On the basis
of this EA, the NRC concludes that the
exemptions did not, and will not, have
a significant effect on the quality of the
human environment. Accordingly, the
NRC has determined not to prepare an
EIS for the action.
Dated at Rockville, Maryland, this 19th day
of December 2017.
For the Nuclear Regulatory Commission.
Bruce Watson,
Chief, Reactor Decommissioning Branch,
Division of Decommissioning, Uranium
Recovery and Waste Programs, Office of
Nuclear Material Safety and Safeguards.
[FR Doc. 2017–27682 Filed 12–22–17; 8:45 am]
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61043
NUCLEAR REGULATORY
COMMISSION
[NRC–2017–0237]
Criteria for Accident Monitoring
Instrumentation for Nuclear Power
Plants
Nuclear Regulatory
Commission.
ACTION: Draft regulatory guide; request
for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing for public
comment draft regulatory guide (DG),
DG–1335, ‘‘Criteria for Accident
Monitoring Instrumentation for Nuclear
Power Plants.’’ The DG–1335 is
proposed revision 5 of regulatory guide
(RG) 1.97, (same title), last revised in
June 2006 (Revision 4). This guide
describes an approach that is acceptable
to the staff of the NRC to meet
regulatory requirements for
instrumentation to monitor accidents in
nuclear power plants. It endorses, with
clarifications, the Institute of Electrical
and Electronic Engineers (IEEE)
Standard (Std.) 497–2016, ‘‘IEEE
Standard Criteria for Accident
Monitoring Instrumentation for Nuclear
Power Generating Stations.’’
DATES: Submit comments by February
26, 2018. Comments received after this
date will be considered if it is practical
to do so, but the NRC is able to ensure
consideration only for comments
received on or before this date.
Although a time limit is given,
comments and suggestions in
connection with items for inclusion in
guides currently being developed or
improvements in all published guides
are encouraged at any time.
ADDRESSES: You may submit comments
by any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0237. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: May Ma, Office
of Administration, Mail Stop: OWFN–
12H08, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
For additional direction on obtaining
information and submitting comments,
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
SUMMARY:
E:\FR\FM\26DEN1.SGM
26DEN1
61044
Federal Register / Vol. 82, No. 246 / Tuesday, December 26, 2017 / Notices
FOR FURTHER INFORMATION CONTACT:
Pong Chung, telephone: 301–415–2363,
email: Pong.Chung@nrc.gov; and
Stephen Burton, telephone: 301–415–
7000, email: Stephen.Burton@nrc.gov.
Both are staff members of the Office of
Nuclear Regulatory Research, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2017–
0237 when contacting the NRC about
the availability of information regarding
this action. You may obtain publicallyavailable information related to this
action, by any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0237.
• 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
‘‘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 pdr.resource@nrc.gov. The DG
is electronically available in ADAMS
under Accession No. ML17083A134.
The regulatory analysis for this DG is
available in ADAMS under Accession
No. ML17083A133.
• 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.
ethrower on DSK3G9T082PROD with NOTICES
B. Submitting Comments
Please include Docket ID NRC–2017–
0237 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 that
you do not want to be publicly
disclosed in your comment submission.
The NRC posts all comment
submissions at https://
www.regulations.gov as well as entering
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
VerDate Sep<11>2014
20:21 Dec 22, 2017
Jkt 244001
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 submissions into
ADAMS.
II. Additional Information
The NRC is issuing for public
comment a DG 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 data that the staff needs in
its review of applications for permits
and licenses.
The DG, entitled ‘‘Criteria for
Accident Monitoring Instrumentation
for Nuclear Power Plants,’’ is proposed
revision 5 to RG 1.97. The proposed
revised RG is temporarily identified by
its task number, DG–1335. The DG
provides a more technology-neutral
approach and brings the regulatory
guide more in line with related
international standards. This revision
introduces a new set of variables for
parameters that may be monitored when
following severe accident management
guidelines. The NRC staff determined
that RG 1.97 should be revised to
endorse the 2016 version of IEEE Std.
497, with certain exceptions and
clarifications, and to make additional
clarifying changes to support new
reactor license applications, design
certifications, and applications for
license amendments.
Revising RG 1.97 to endorse the
current version of the IEEE consensus
standard is in accordance with Section
12(a)(2) of Public Law 104–113,
‘‘National Technology Transfer and
Advancement Act of 1995,’’ (codified at
15 U.S.C. 272(b)(3)) and is consistent
with the NRC policy of evaluating the
latest versions of national consensus
standards to determine their suitability
for endorsement by regulatory guides.
This revision also will comply with the
NRC’s Management Directive (MD) 6.5,
‘‘NRC Participation in the Development
and Use of Consensus Standards’’
(ADAMS Accession No. ML16193A497).
Copies of IEEE documents may be
purchased from the Institute of
Electrical and Electronics Engineers
Service Center, 445 Hoes Lane, PO Box
PO 00000
Frm 00097
Fmt 4703
Sfmt 4703
1331, Piscataway, NJ 08855 or through
the IEEE’s public website at https://
www.ieee.org/publications_standards/
index.html.
III. Backfitting and Issue Finality
Draft regulatory guide DG–1335, if
finalized as revision 5 to RG 1.97, would
endorse, with certain exceptions and
clarifications, the 2016 revision of IEEE
Std. 497, which contains a more
technology-neutral approach and brings
current guidance more in line with
related international standards. This
revision introduces a new set of
variables for parameters that may be
monitored when following severe
accident management guidelines.
Applicants and licensees may
voluntarily use the guidance in DG–
1335, if finalized as revision 5 to RG
1.97, to demonstrate compliance with
the underlying NRC regulations. Current
licensees may continue to use guidance
the NRC found previously acceptable for
complying with the identified
regulations as long as their current
licensing basis remains unchanged. As
such, this draft regulatory guide, if
finalized, would not constitute
backfitting as defined in 10 CFR 50.109
(the Backfit Rule) and is not otherwise
inconsistent with the issue finality
provisions in 10 CFR part 52, ‘‘Licenses,
Certifications and Approvals for Nuclear
Power Plants.’’
Dated at Rockville, Maryland, this 19th day
of December 2017.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic
Issues Branch, Division of Engineering, Office
of Nuclear Regulatory Research.
[FR Doc. 2017–27661 Filed 12–22–17; 8:45 am]
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[Federal Register Volume 82, Number 246 (Tuesday, December 26, 2017)]
[Notices]
[Pages 61043-61044]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-27661]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2017-0237]
Criteria for Accident Monitoring Instrumentation for Nuclear
Power Plants
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft regulatory guide; request for comment.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for
public comment draft regulatory guide (DG), DG-1335, ``Criteria for
Accident Monitoring Instrumentation for Nuclear Power Plants.'' The DG-
1335 is proposed revision 5 of regulatory guide (RG) 1.97, (same
title), last revised in June 2006 (Revision 4). This guide describes an
approach that is acceptable to the staff of the NRC to meet regulatory
requirements for instrumentation to monitor accidents in nuclear power
plants. It endorses, with clarifications, the Institute of Electrical
and Electronic Engineers (IEEE) Standard (Std.) 497-2016, ``IEEE
Standard Criteria for Accident Monitoring Instrumentation for Nuclear
Power Generating Stations.''
DATES: Submit comments by February 26, 2018. Comments received after
this date will be considered if it is practical to do so, but the NRC
is able to ensure consideration only for comments received on or before
this date. Although a time limit is given, comments and suggestions in
connection with items for inclusion in guides currently being developed
or improvements in all published guides are encouraged at any time.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0237. 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.
Mail comments to: May Ma, Office of Administration, Mail
Stop: OWFN-12H08, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
[[Page 61044]]
FOR FURTHER INFORMATION CONTACT: Pong Chung, telephone: 301-415-2363,
email: [email protected]; and Stephen Burton, telephone: 301-415-7000,
email: [email protected]. Both are staff members of the Office of
Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2017-0237 when contacting the NRC
about the availability of information regarding this action. You may
obtain publically-available information related to this action, by any
of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0237.
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 ``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
DG is electronically available in ADAMS under Accession No.
ML17083A134. The regulatory analysis for this DG is available in ADAMS
under Accession No. ML17083A133.
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-2017-0237 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 that you do not want to be publicly disclosed in your
comment submission. The NRC posts all comment submissions at https://www.regulations.gov as well as entering 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 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 submissions into ADAMS.
II. Additional Information
The NRC is issuing for public comment a DG 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 data that the staff needs in
its review of applications for permits and licenses.
The DG, entitled ``Criteria for Accident Monitoring Instrumentation
for Nuclear Power Plants,'' is proposed revision 5 to RG 1.97. The
proposed revised RG is temporarily identified by its task number, DG-
1335. The DG provides a more technology-neutral approach and brings the
regulatory guide more in line with related international standards.
This revision introduces a new set of variables for parameters that may
be monitored when following severe accident management guidelines. The
NRC staff determined that RG 1.97 should be revised to endorse the 2016
version of IEEE Std. 497, with certain exceptions and clarifications,
and to make additional clarifying changes to support new reactor
license applications, design certifications, and applications for
license amendments.
Revising RG 1.97 to endorse the current version of the IEEE
consensus standard is in accordance with Section 12(a)(2) of Public Law
104-113, ``National Technology Transfer and Advancement Act of 1995,''
(codified at 15 U.S.C. 272(b)(3)) and is consistent with the NRC policy
of evaluating the latest versions of national consensus standards to
determine their suitability for endorsement by regulatory guides. This
revision also will comply with the NRC's Management Directive (MD) 6.5,
``NRC Participation in the Development and Use of Consensus Standards''
(ADAMS Accession No. ML16193A497).
Copies of IEEE documents may be purchased from the Institute of
Electrical and Electronics Engineers Service Center, 445 Hoes Lane, PO
Box 1331, Piscataway, NJ 08855 or through the IEEE's public website at
https://www.ieee.org/publications_standards/.
III. Backfitting and Issue Finality
Draft regulatory guide DG-1335, if finalized as revision 5 to RG
1.97, would endorse, with certain exceptions and clarifications, the
2016 revision of IEEE Std. 497, which contains a more technology-
neutral approach and brings current guidance more in line with related
international standards. This revision introduces a new set of
variables for parameters that may be monitored when following severe
accident management guidelines. Applicants and licensees may
voluntarily use the guidance in DG-1335, if finalized as revision 5 to
RG 1.97, to demonstrate compliance with the underlying NRC regulations.
Current licensees may continue to use guidance the NRC found previously
acceptable for complying with the identified regulations as long as
their current licensing basis remains unchanged. As such, this draft
regulatory guide, if finalized, would not constitute backfitting as
defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise
inconsistent with the issue finality provisions in 10 CFR part 52,
``Licenses, Certifications and Approvals for Nuclear Power Plants.''
Dated at Rockville, Maryland, this 19th day of December 2017.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic Issues Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2017-27661 Filed 12-22-17; 8:45 am]
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