Revision Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors, 6897-6898 [2016-02564]
Download as PDF
<![CDATA[
Federal Register / Vol. 81, No. 26 / Tuesday, February 9, 2016 / Notices
6897
ADAMS accession
No.
Document
Section 11.1, ‘‘Coolant Source Terms,’’ Revision 4 ...................................................................................................................
Section 11.2, ‘‘Liquid Waste Management System,’’ Revision 5 ...............................................................................................
Section 11.3, ‘‘Gaseous Waste Management System,’’ Revision 4 ...........................................................................................
Section 11.4, ‘‘Solid Waste Management System,’’ Revision 4 .................................................................................................
Section 11.5, ‘‘Process and Effluent Radiological Monitoring Instrumentation and Sampling Systems,’’ Revision 6 ...............
BTP 11–3, ‘‘Design Guidance for Solid Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear
Power Reactor Plants,’’ Revision 4*.
BTP 11–5, ‘‘Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure,’’ Revision 4 * ...........................
BTP 11–6, ‘‘Postulated Radioactive Releases due to Liquid Containing Tank Failures,’’ Revision 4 * .....................................
ML15029A022
ML15029A032
ML15029A039
ML15029A174
ML15029A182
ML15027A198
ML15027A302
ML15027A401
* No changes resulting from public comments. See documents in the package at ADAMS Accession Number ML14113A532 to see changes
made since last revision.
Dated at Rockville, Maryland, this 8th day
of January, 2016.
For the Nuclear Regulatory Commission.
Kimyata Morgan Butler,
Chief, New Reactor Rulemaking and
Guidance Branch, Division of Advanced
Reactors and Rulemaking, Office of New
Reactors.
[FR Doc. 2016–02588 Filed 2–8–16; 8:45 am]
BILLING CODE 3410–16–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2012–0232]
Revision Probabilistic Risk
Assessment and Severe Accident
Evaluation for New Reactors
Nuclear Regulatory
Commission.
ACTION: Standard review plan—final
section revision; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a final
revision to the following section in
Chapter 19 of NUREG–0800, ‘‘Standard
Review Plan (SRP) for the Review of
Safety Analysis Reports for Nuclear
Power Plants: LWR Edition,’’ Section
19.0, ‘‘Probabilistic Risk Assessment
and Severe Accident Evaluation for New
Reactors.’’
DATES: The effective date of this
Standard Review Plan update is March
10, 2016.
ADDRESSES: Please refer to Docket ID
NRC–2012–0232 when contacting the
NRC about the availability of
information regarding this document.
You may access publicly-available
information related to this document
using any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0232. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual(s) listed in the FOR FURTHER
mstockstill on DSK4VPTVN1PROD with NOTICES
SUMMARY:
VerDate Sep<11>2014
17:54 Feb 08, 2016
Jkt 238001
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
‘‘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
ADAMS accession number for each
document referenced (if it available in
ADAMS) is provided the first time that
a document is referenced. The final
revision for the SRP, Section 19.0,
Revision 3, ‘‘Probabilistic Risk
Assessment and Severe Accident
Evaluation for New Reactors,’’ is
available in ADAMS under Accession
No. ML15089A068. A redline strikeout
comparing the proposed revision to the
final revision can be found in ADAMS
under Accession No. ML15089A115.
The responses to public comments can
be found in ADAMS under Accession
No. ML15086A472.
• 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.
• The NRC posts its issued staff
guidance on the NRC’s external Web
page: https://www.nrc.gov/reading-rm/
doc-collections/nuregs/staff/sr0800/.
INFORMATION CONTACT
FOR FURTHER INFORMATION CONTACT:
Mark Notich, telephone: 301–415–3053,
email: Mark.Notich@nrc.gov or Nishka
Devaser, telephone: 301–415–5196,
email: Nishka.Devaser@nrc.gov, both are
staff of the Office of New Reactors, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
PO 00000
Frm 00070
Fmt 4703
Sfmt 4703
I. Background
On December 8, 2014 (79 FR 72709),
the NRC published for public comment
a proposed revision to this section of the
SRP. The staff made changes to the
proposed revision after consideration of
comments received. A summary of the
comments and the staff’s disposition of
the comments are available in a separate
document, ‘‘Response to Public
Comments on Draft SRP Section 19.0’’
(ADAMS Accession No. ML15086A472).
The changes to this SRP section
reflect current staff review methods and
practices based on lessons learned from
NRC reviews of design certification (DC)
and combined license (COL)
applications completed since the last
revision of this chapter. Changes
include: (1) Incorporation of guidance
previously published in Interim Staff
Guidance (ISG) DC/COL–ISG–003
(ADAMS Accession No. ML081430087)
concerning the review of probabilistic
risk assessment (PRA) information and
severe accident assessments submitted
to support DC and COL applications, (2)
incorporation of guidance for DC and
COL applicants previously published in
ISG DC/COL–ISG–020 (ADAMS
Accession No. ML100491233)
concerning review of information from
PRA-based seismic margin analyses
submitted in support of DC and COL
applications, (3) incorporation of
guidance previously published in ISG
Digital Instrumentation and Controls
(DI&C)/COL–ISG–003 (ADAMS
Accession No. ML080570048)
concerning review of DI&C system
PRAs, including treatment of common
cause failure (CCFs) in PRAs and
uncertainty analysis associated with
new reactor digital systems, (4)
incorporation of additional procedures
for review of PRA information and
severe accident assessments developed
during NRC reviews of DC and COL
applications completed after Revision 2
of SRP Section 19.0 was issued, (5)
additional proposed acceptance criteria
and review procedures for the staff’s
review of an applicant’s assessment of
E:\FR\FM\09FEN1.SGM
09FEN1
6898
Federal Register / Vol. 81, No. 26 / Tuesday, February 9, 2016 / Notices
mstockstill on DSK4VPTVN1PROD with NOTICES
risk from accidents that could affect
multiple modules in facilities with
small modular integral pressurized
water reactors (iPWRs), (6) additional
review procedures for the staff’s review
of the results of the PRA for non-power
modes of operation, and (7) several
editorial changes to ensure that there is
no confusion between text in this SRP
section and text in the ASME/ANS PRA
Standard currently endorsed by the NRC
and referenced in this SRP section. The
ISG DC/COL–ISG–003 and ISG DI&C/
COL–ISG–003 have now been
superseded by SRP 19.0, Revision 3 and
should no longer be used. The ISG DC/
COL–ISG–020 contains guidance for
COL holders which has not been
superseded by SRP 19.0, Revision 3 and
should still be used by COL holders.
II. Backfitting and Issue Finality
Issuance of this final SRP does not
constitute backfitting as defined in 10
CFR 50.109 (the Backfit Rule) or
otherwise be inconsistent with the issue
finality provisions in 10 CFR part 52.
The NRC’s position is based upon the
following considerations:
1. The SRP positions, does not
constitute backfitting, inasmuch as the
SRP is internal guidance to NRC staff.
The SRP provides internal guidance
to the NRC staff on how to review an
application for NRC regulatory approval
in the form of licensing. Changes in
internal staff guidance are not matters
for which either nuclear power plant
applicants or licensees are protected
under either the Backfit Rule or the
issue finality provisions of 10 CFR part
52.
2. The NRC staff has no intention to
impose the SRP positions on existing
licensees either now or in the future.
The NRC staff does not intend to
impose or apply the positions described
in the draft SRP to existing licenses and
regulatory approvals. Hence, the
issuance of a final SRP—even if
considered guidance within the purview
of the issue finality provisions in 10
CFR part 52—need not be evaluated as
if it were a backfit or inconsistent with
issue finality provisions. If, in the
future, the NRC staff seeks to impose a
position in the SRP on holders of
already issued licenses in a manner that
does not provide issue finality as
described in the applicable issue finality
provision, then the staff must make the
showing as set forth in the Backfit Rule
or address the criteria for avoiding issue
finality as described in the applicable
issue finality provision.
3. Backfitting and issue finality do
not—with limited exceptions not
VerDate Sep<11>2014
17:54 Feb 08, 2016
Jkt 238001
applicable here—protect current or
future applicants.
Applicants and potential applicants
are not, with certain exceptions,
protected by either the Backfit Rule or
any issue finality provisions under 10
CFR part 52. Neither the Backfit Rule
nor the issue finality provisions under
10 CFR part 52, with certain exclusions,
were intended to apply to every NRC
action that substantially changes the
expectations of current and future
applicants. The exceptions to the
general principle are applicable
whenever an applicant references a 10
CFR part 52 license (e.g., an early site
permit) and/or NRC regulatory approval
(e.g., a design certification rule) with
specified issue finality provisions.
The exceptions to the general
principle are applicable whenever an
applicant references a 10 CFR part 52
license (e.g., an early site permit) and/
or NRC regulatory approval (e.g., a
design certification rule) with specified
issue finality provisions. The NRC staff
does not, at this time, intend to impose
the positions represented in the draft
SRP in a manner that is inconsistent
with any issue finality provisions. If, in
the future, the staff seeks to impose a
position in the draft SRP in a manner
that does not provide issue finality as
described in the applicable issue finality
provision, then the staff must address
the criteria for avoiding issue finality as
described in the applicable issue finality
provision.
III. Congressional Review Act
In accordance with the Congressional
Review Act, the NRC has determined
that this action is not a major rule and
has verified this determination with the
Office of Information and Regulatory
Affairs of the Office of Management and
Budget.
Dated at Rockville, Maryland, this 21st day
of January, 2016.
For the Nuclear Regulatory Commission.
Tanya Smith,
Chief, New Reactor Rulemaking and
Guidance Branch, Division of Advanced
Reactors and Rulemaking, Office of New
Reactors.
[FR Doc. 2016–02564 Filed 2–8–16; 8:45 am]
BILLING CODE 7590–01–P
ACTION:
Notice.
This notice identifies
Schedule A, B, and C appointing
authorities applicable to a single agency
that were established or revoked from
November 1, 2015, to November 30,
2015.
SUMMARY:
FOR FURTHER INFORMATION CONTACT:
Senior Executive Resources Services,
Senior Executive Services and
Performance Management, Employee
Services, 202–606–2246.
SUPPLEMENTARY INFORMATION: In
accordance with 5 CFR 213.103,
Schedule A, B, and C appointing
authorities available for use by all
agencies are codified in the Code of
Federal Regulations (CFR). Schedule A,
B, and C appointing authorities
applicable to a single agency are not
codified in the CFR, but the Office of
Personnel Management (OPM)
publishes a notice of agency-specific
authorities established or revoked each
month in the Federal Register at
www.gpo.gov/fdsys/. OPM also
publishes an annual notice of the
consolidated listing of all Schedule A,
B, and C appointing authorities, current
as of June 30, in the Federal Register.
Schedule A
11. Department of Homeland Security
(Sch. A, 213.3111)
(d) General—
(1) Not to exceed 1,000 positions to
perform cyber risk and strategic
analysis, incident handling and
malware/vulnerability analysis, program
management, distributed control
systems security, cyber incident
response, cyber exercise facilitation and
management, cyber vulnerability
detection and assessment, network and
systems engineering, enterprise
architecture, intelligence analysis,
investigation, investigative analysis and
cyber-related infrastructure
interdependency analysis requiring
unique qualifications currently not
established by OPM. Positions will be at
the General Schedule (GS) grade levels
09–15. Appointments may be made
under this authority until March 31,
2017.
Schedule B
No Schedule B Authorities to report
during November 2015.
OFFICE OF PERSONNEL
MANAGEMENT
Schedule C
Excepted Service
U.S. Office of Personnel
Management (OPM).
AGENCY:
PO 00000
Frm 00071
Fmt 4703
Sfmt 4703
The following Schedule C appointing
authorities were approved during
November 2015.
E:\FR\FM\09FEN1.SGM
09FEN1
]]>Agencies
[Federal Register Volume 81, Number 26 (Tuesday, February 9, 2016)]
[Notices]
[Pages 6897-6898]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-02564]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2012-0232]
Revision Probabilistic Risk Assessment and Severe Accident
Evaluation for New Reactors
AGENCY: Nuclear Regulatory Commission.
ACTION: Standard review plan--final section revision; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a
final revision to the following section in Chapter 19 of NUREG-0800,
``Standard Review Plan (SRP) for the Review of Safety Analysis Reports
for Nuclear Power Plants: LWR Edition,'' Section 19.0, ``Probabilistic
Risk Assessment and Severe Accident Evaluation for New Reactors.''
DATES: The effective date of this Standard Review Plan update is March
10, 2016.
ADDRESSES: Please refer to Docket ID NRC-2012-0232 when contacting the
NRC about the availability of information regarding this document. You
may access publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0232. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual(s) 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 ``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
ADAMS accession number for each document referenced (if it available in
ADAMS) is provided the first time that a document is referenced. The
final revision for the SRP, Section 19.0, Revision 3, ``Probabilistic
Risk Assessment and Severe Accident Evaluation for New Reactors,'' is
available in ADAMS under Accession No. ML15089A068. A redline strikeout
comparing the proposed revision to the final revision can be found in
ADAMS under Accession No. ML15089A115. The responses to public comments
can be found in ADAMS under Accession No. ML15086A472.
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.
The NRC posts its issued staff guidance on the NRC's
external Web page: https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/.
FOR FURTHER INFORMATION CONTACT: Mark Notich, telephone: 301-415-3053,
email: Mark.Notich@nrc.gov or Nishka Devaser, telephone: 301-415-5196,
email: Nishka.Devaser@nrc.gov, both are staff of the Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.
SUPPLEMENTARY INFORMATION:
I. Background
On December 8, 2014 (79 FR 72709), the NRC published for public
comment a proposed revision to this section of the SRP. The staff made
changes to the proposed revision after consideration of comments
received. A summary of the comments and the staff's disposition of the
comments are available in a separate document, ``Response to Public
Comments on Draft SRP Section 19.0'' (ADAMS Accession No. ML15086A472).
The changes to this SRP section reflect current staff review
methods and practices based on lessons learned from NRC reviews of
design certification (DC) and combined license (COL) applications
completed since the last revision of this chapter. Changes include: (1)
Incorporation of guidance previously published in Interim Staff
Guidance (ISG) DC/COL-ISG-003 (ADAMS Accession No. ML081430087)
concerning the review of probabilistic risk assessment (PRA)
information and severe accident assessments submitted to support DC and
COL applications, (2) incorporation of guidance for DC and COL
applicants previously published in ISG DC/COL-ISG-020 (ADAMS Accession
No. ML100491233) concerning review of information from PRA-based
seismic margin analyses submitted in support of DC and COL
applications, (3) incorporation of guidance previously published in ISG
Digital Instrumentation and Controls (DI&C)/COL-ISG-003 (ADAMS
Accession No. ML080570048) concerning review of DI&C system PRAs,
including treatment of common cause failure (CCFs) in PRAs and
uncertainty analysis associated with new reactor digital systems, (4)
incorporation of additional procedures for review of PRA information
and severe accident assessments developed during NRC reviews of DC and
COL applications completed after Revision 2 of SRP Section 19.0 was
issued, (5) additional proposed acceptance criteria and review
procedures for the staff's review of an applicant's assessment of
[[Page 6898]]
risk from accidents that could affect multiple modules in facilities
with small modular integral pressurized water reactors (iPWRs), (6)
additional review procedures for the staff's review of the results of
the PRA for non-power modes of operation, and (7) several editorial
changes to ensure that there is no confusion between text in this SRP
section and text in the ASME/ANS PRA Standard currently endorsed by the
NRC and referenced in this SRP section. The ISG DC/COL-ISG-003 and ISG
DI&C/COL-ISG-003 have now been superseded by SRP 19.0, Revision 3 and
should no longer be used. The ISG DC/COL-ISG-020 contains guidance for
COL holders which has not been superseded by SRP 19.0, Revision 3 and
should still be used by COL holders.
II. Backfitting and Issue Finality
Issuance of this final SRP does not constitute backfitting as
defined in 10 CFR 50.109 (the Backfit Rule) or otherwise be
inconsistent with the issue finality provisions in 10 CFR part 52. The
NRC's position is based upon the following considerations:
1. The SRP positions, does not constitute backfitting, inasmuch as
the SRP is internal guidance to NRC staff.
The SRP provides internal guidance to the NRC staff on how to
review an application for NRC regulatory approval in the form of
licensing. Changes in internal staff guidance are not matters for which
either nuclear power plant applicants or licensees are protected under
either the Backfit Rule or the issue finality provisions of 10 CFR part
52.
2. The NRC staff has no intention to impose the SRP positions on
existing licensees either now or in the future.
The NRC staff does not intend to impose or apply the positions
described in the draft SRP to existing licenses and regulatory
approvals. Hence, the issuance of a final SRP--even if considered
guidance within the purview of the issue finality provisions in 10 CFR
part 52--need not be evaluated as if it were a backfit or inconsistent
with issue finality provisions. If, in the future, the NRC staff seeks
to impose a position in the SRP on holders of already issued licenses
in a manner that does not provide issue finality as described in the
applicable issue finality provision, then the staff must make the
showing as set forth in the Backfit Rule or address the criteria for
avoiding issue finality as described in the applicable issue finality
provision.
3. Backfitting and issue finality do not--with limited exceptions
not applicable here--protect current or future applicants.
Applicants and potential applicants are not, with certain
exceptions, protected by either the Backfit Rule or any issue finality
provisions under 10 CFR part 52. Neither the Backfit Rule nor the issue
finality provisions under 10 CFR part 52, with certain exclusions, were
intended to apply to every NRC action that substantially changes the
expectations of current and future applicants. The exceptions to the
general principle are applicable whenever an applicant references a 10
CFR part 52 license (e.g., an early site permit) and/or NRC regulatory
approval (e.g., a design certification rule) with specified issue
finality provisions.
The exceptions to the general principle are applicable whenever an
applicant references a 10 CFR part 52 license (e.g., an early site
permit) and/or NRC regulatory approval (e.g., a design certification
rule) with specified issue finality provisions. The NRC staff does not,
at this time, intend to impose the positions represented in the draft
SRP in a manner that is inconsistent with any issue finality
provisions. If, in the future, the staff seeks to impose a position in
the draft SRP in a manner that does not provide issue finality as
described in the applicable issue finality provision, then the staff
must address the criteria for avoiding issue finality as described in
the applicable issue finality provision.
III. Congressional Review Act
In accordance with the Congressional Review Act, the NRC has
determined that this action is not a major rule and has verified this
determination with the Office of Information and Regulatory Affairs of
the Office of Management and Budget.
Dated at Rockville, Maryland, this 21st day of January, 2016.
For the Nuclear Regulatory Commission.
Tanya Smith,
Chief, New Reactor Rulemaking and Guidance Branch, Division of Advanced
Reactors and Rulemaking, Office of New Reactors.
[FR Doc. 2016-02564 Filed 2-8-16; 8:45 am]
BILLING CODE 7590-01-P
