Methodology for Modeling Fire Growth and Suppression for Electrical Cabinet Fires in Nuclear Power Plants, 31354-31355 [2019-13928]
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Federal Register / Vol. 84, No. 126 / Monday, July 1, 2019 / Notices
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khammond on DSKBBV9HB2PROD with NOTICES
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Comments submitted in response to
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19:58 Jun 28, 2019
Gatrie Johnson,
NASA PRA Clearance Officer.
[FR Doc. 2019–13909 Filed 6–28–19; 8:45 am]
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NATIONAL FOUNDATION ON THE
ARTS AND THE HUMANITIES
National Endowment for the Arts
60-Day Notice for the ‘‘Blanket
Justification for Arts Endowment
Funding Application Guidelines and
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They will also become a matter of
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and the Humanities.
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comment request.
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The National Endowment for
the Arts (Arts Endowment), as part of its
continuing effort to reduce paperwork
and respondent burden, conducts a
preclearance consultation program to
provide the general public and federal
agencies with an opportunity to
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continuing collections of information in
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agency’s estimate of the burden of the
SUMMARY:
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Dated: June 26, 2019.
Jillian Miller,
Director, Office of Guidelines and Panel
Operations, National Endowment for the Arts.
[FR Doc. 2019–13955 Filed 6–28–19; 8:45 am]
BILLING CODE 7537–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2019–0119]
Methodology for Modeling Fire Growth
and Suppression for Electrical Cabinet
Fires in Nuclear Power Plants
Nuclear Regulatory
Commission.
ACTION: Draft NUREG; request for
comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing for public
comment a draft NUREG entitled,
‘‘Methodology for Modeling Fire Growth
and Suppression for Electrical Cabinet
Fires in Nuclear Power Plants’’
(NUREG–2230/EPRI 3002016051). This
report is a joint product of the NRC and
the Electric Power Research Institute
(EPRI) collaborating under a
memorandum of understanding for fire
research. The purpose of this report is
to provide an approach that more
closely models the types of fire
progressions and response activities
observed in operating experience. This
report provides a revised set of
parameters addressing both the fire
growth portion and the suppression
response for electrical cabinet fires.
DATES: Submit comments by July 31,
2019. Comments received after this date
will be considered if it is practical to do
so, but the Commission is able to ensure
consideration only for comments
received before this date.
ADDRESSES: You may submit comments
by any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov/ and search
SUMMARY:
E:\FR\FM\01JYN1.SGM
01JYN1
Federal Register / Vol. 84, No. 126 / Monday, July 1, 2019 / Notices
for Docket ID NRC–2019–0119. Address
questions about docket IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
Jennifer.Borges@nrc.gov. For technical
questions, contact the individuals listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• Mail comments to: Office of
Administration, Mail Stop: TWFN–7–
A60M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, ATTN: Program Management,
Announcements and Editing Staff.
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:
David W. Stroup, Office of Nuclear
Regulatory Research, telephone: 301–
415–1649, email: David.Stroup@nrc.gov;
or Nicholas Melly, Office of Nuclear
Regulatory Research, telephone: 301–
415–2392, email: Nicholas.Melly@
nrc.gov. Both are staff of the U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
khammond on DSKBBV9HB2PROD with NOTICES
A. Obtaining Information
Please refer to Docket ID NRC–2019–
0119 when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable 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–2019–0119.
• 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. The draft NUREG on
‘‘Methodology for Modeling Fire Growth
and Suppression Response of Electrical
Cabinet Fires in Nuclear Power Plants’’
is available in ADAMS under Accession
No. ML19163A293.
• 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.
VerDate Sep<11>2014
19:58 Jun 28, 2019
Jkt 247001
B. Submitting Comments
Please include Docket ID NRC–2019–
0119 in your comment submission.
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 https://
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 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.
II. Discussion
Over the past decade, modern fire
probabilistic risk assessments (PRAs)
have been developed using NUREG/CR–
6850 (EPRI 1011989), EPRI/NRC Fire
PRA Methodology for Nuclear Power
Facilities. The results show that fire can
be a significant portion of the overall
site risk profile, however, the
methodology was never fully piloted
tested before implementation. As a
result, some areas of the fire PRAs have
been found to be overly conservative
resulting in potentially unrealistic
results. Additional research is being
conducted to improve the tools,
methods, and data used for fire PRAs
and refine the estimates of risk and
close technical gaps in the methodology.
Recent research efforts focused on
obtaining more detailed information
regarding the fire incidents at nuclear
power plants. This data collection has
enabled researchers to obtain more
details on the fire attributes, timeline,
and plant impact. This project
specifically reviewed the available
electrical cabinet fire incident data in an
effort to update the methodology to
better reflect the observed operating
experience. Insights from the data
review served as the basis for amending
portions of the fire modeling and
suppression response to more accurately
align with operating experience.
Specifically, the methodology
described in this report provides:
• A conceptual fire event tree
progression model developed through a
review of insights from the fire event
PO 00000
Frm 00069
Fmt 4703
Sfmt 4703
31355
database. From this review, guidance
was developed to allow for consistent
classification of fire events into two
different growth profiles, Interruptible
and Growing.
• Split fractions for Interruptible and
Growing fires for use in the revised
detection-suppression event tree.
• A revised electrical cabinet heat
release rate (HRR) profile for use in the
detailed fire modeling of Interruptible
Fires. This revised profile includes a
pre-growth period of up to 8 minutes of
negligible HRR. The treatment for the
HRR profile for Growing Fires was not
modified in this research.
• Revisions to the detectionsuppression event tree to include paths
for crediting early intervention by plant
personnel as well as new parameters to
facilitate these revisions. These new
parameters include an opportunity to
credit detection by general plant
personnel.
• An opportunity for main control
room (MCR) indications as a means for
fire detection when applicable in the
detection-suppression event tree.
• New suppression curves for
electrical cabinets (Bin 15) applicable to
Interruptible and Growing electrical
cabinet fire scenarios.
• New suppression curves for the
MCR.
• A new electrical fire suppression
curve for use with other non-cabinet
electrical ignition sources (e.g., motors,
pumps, transformers).
• A probability of automatic smoke
detection effectiveness for
characterizing the ability of spot type
smoke detection devices to operate in a
range of geometric conditions and heat
release rates. This is necessary for better
alignment with operating experience,
which suggests that the majority of the
fires are detected by plant personnel
and MCR indicators instead of
automatic smoke detection systems.
• An updated Bin 15 fire frequency
that makes use of the fire event data
classified in EPRI 3002005302, Fire
Events Database Update for the Period
2010–2014.
Dated at Rockville, Maryland, this 25th day
of June 2019.
For the Nuclear Regulatory Commission.
Mark H. Salley,
Branch Chief, Fire and External Hazards
Analysis Branch, Division of Risk Analysis,
Office of Nuclear Regulatory Research.
[FR Doc. 2019–13928 Filed 6–28–19; 8:45 am]
BILLING CODE 7590–01–P
E:\FR\FM\01JYN1.SGM
01JYN1
Agencies
[Federal Register Volume 84, Number 126 (Monday, July 1, 2019)]
[Notices]
[Pages 31354-31355]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-13928]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2019-0119]
Methodology for Modeling Fire Growth and Suppression for
Electrical Cabinet Fires in Nuclear Power Plants
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft NUREG; request for comment.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for
public comment a draft NUREG entitled, ``Methodology for Modeling Fire
Growth and Suppression for Electrical Cabinet Fires in Nuclear Power
Plants'' (NUREG-2230/EPRI 3002016051). This report is a joint product
of the NRC and the Electric Power Research Institute (EPRI)
collaborating under a memorandum of understanding for fire research.
The purpose of this report is to provide an approach that more closely
models the types of fire progressions and response activities observed
in operating experience. This report provides a revised set of
parameters addressing both the fire growth portion and the suppression
response for electrical cabinet fires.
DATES: Submit comments by July 31, 2019. Comments received after this
date will be considered if it is practical to do so, but the Commission
is able to ensure consideration only for comments received before this
date.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov/ and search
[[Page 31355]]
for Docket ID NRC-2019-0119. Address questions about docket IDs in
Regulations.gov to Jennifer Borges; telephone: 301-287-9127; email:
[email protected]. For technical questions, contact the
individuals listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: Office of Administration, Mail Stop:
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
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: David W. Stroup, Office of Nuclear
Regulatory Research, telephone: 301-415-1649, email:
[email protected]; or Nicholas Melly, Office of Nuclear Regulatory
Research, telephone: 301-415-2392, email: [email protected]. Both
are staff of the 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-2019-0119 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 Website: Go to https://www.regulations.gov/ and search for Docket ID NRC-2019-0119.
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]. The draft NUREG on ``Methodology for
Modeling Fire Growth and Suppression Response of Electrical Cabinet
Fires in Nuclear Power Plants'' is available in ADAMS under Accession
No. ML19163A293.
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-2019-0119 in your comment submission.
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
https://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 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.
II. Discussion
Over the past decade, modern fire probabilistic risk assessments
(PRAs) have been developed using NUREG/CR-6850 (EPRI 1011989), EPRI/NRC
Fire PRA Methodology for Nuclear Power Facilities. The results show
that fire can be a significant portion of the overall site risk
profile, however, the methodology was never fully piloted tested before
implementation. As a result, some areas of the fire PRAs have been
found to be overly conservative resulting in potentially unrealistic
results. Additional research is being conducted to improve the tools,
methods, and data used for fire PRAs and refine the estimates of risk
and close technical gaps in the methodology.
Recent research efforts focused on obtaining more detailed
information regarding the fire incidents at nuclear power plants. This
data collection has enabled researchers to obtain more details on the
fire attributes, timeline, and plant impact. This project specifically
reviewed the available electrical cabinet fire incident data in an
effort to update the methodology to better reflect the observed
operating experience. Insights from the data review served as the basis
for amending portions of the fire modeling and suppression response to
more accurately align with operating experience.
Specifically, the methodology described in this report provides:
A conceptual fire event tree progression model developed
through a review of insights from the fire event database. From this
review, guidance was developed to allow for consistent classification
of fire events into two different growth profiles, Interruptible and
Growing.
Split fractions for Interruptible and Growing fires for
use in the revised detection-suppression event tree.
A revised electrical cabinet heat release rate (HRR)
profile for use in the detailed fire modeling of Interruptible Fires.
This revised profile includes a pre-growth period of up to 8 minutes of
negligible HRR. The treatment for the HRR profile for Growing Fires was
not modified in this research.
Revisions to the detection-suppression event tree to
include paths for crediting early intervention by plant personnel as
well as new parameters to facilitate these revisions. These new
parameters include an opportunity to credit detection by general plant
personnel.
An opportunity for main control room (MCR) indications as
a means for fire detection when applicable in the detection-suppression
event tree.
New suppression curves for electrical cabinets (Bin 15)
applicable to Interruptible and Growing electrical cabinet fire
scenarios.
New suppression curves for the MCR.
A new electrical fire suppression curve for use with other
non-cabinet electrical ignition sources (e.g., motors, pumps,
transformers).
A probability of automatic smoke detection effectiveness
for characterizing the ability of spot type smoke detection devices to
operate in a range of geometric conditions and heat release rates. This
is necessary for better alignment with operating experience, which
suggests that the majority of the fires are detected by plant personnel
and MCR indicators instead of automatic smoke detection systems.
An updated Bin 15 fire frequency that makes use of the
fire event data classified in EPRI 3002005302, Fire Events Database
Update for the Period 2010-2014.
Dated at Rockville, Maryland, this 25th day of June 2019.
For the Nuclear Regulatory Commission.
Mark H. Salley,
Branch Chief, Fire and External Hazards Analysis Branch, Division of
Risk Analysis, Office of Nuclear Regulatory Research.
[FR Doc. 2019-13928 Filed 6-28-19; 8:45 am]
BILLING CODE 7590-01-P