Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities, 62894-62896 [2022-22536]
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62894
Federal Register / Vol. 87, No. 199 / Monday, October 17, 2022 / Notices
Activity for Which Permit is
Requested: Waste Management. The
applicant seeks an Antarctic
Conservation Act permit for waste
management activities associated with
coastal camping and the operation of a
remotely piloted aircraft system (RPAS)
in the Antarctic Peninsula region. The
applicant seeks permission for no more
than 40 campers and expedition staff to
camp overnight at select locations for a
maximum of 10 hours ashore. Camping
would be away from vegetated sites and
at least 150m from wildlife
concentrations or lakes, protected areas,
historical sites, and scientific stations.
Tents would be pitched on snow, ice, or
bare smooth rock, at least 20m from the
high-water line. No food, other than
emergency rations, would be brought
onshore and all wastes, including
human waste, would be collected and
returned to the ship for proper disposal.
For remotely piloted aircraft systems
(RPAS) operation, the applicant
proposes to operate small, batteryoperated RPAS consisting, in part, of a
quadcopter equipped with cameras to
collect commercial and educational
footage of the Antarctic. The quadcopter
would not be flown over concentrations
of birds or mammals, or over Antarctic
Specially Protected Areas or Historic
Sites and Monuments. The RPAS would
only be operated by pilots with
extensive experience, who are preapproved by the Expedition Leader.
Location: Port Lockroy, Damoy Point/
Dorian Bay, Paradise Bay, Neko Harbor,
Danco Island and Cuverville and the
vicinity of the Errera Channel,
Neumeyer Channel, Petermann Island,
South of the Lemaire Channel, South
Shetland Islands, Antarctic Peninsula
area.
Dates of Permitted Activities: October
22, 2022–March 30, 2023.
Erika N. Davis,
Program Specialist, Office of Polar Programs.
[FR Doc. 2022–22451 Filed 10–14–22; 8:45 am]
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For the Nuclear Regulatory Commission.
Monika G. Coflin,
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Secretary.
[FR Doc. 2022–22594 Filed 10–13–22; 11:15 am]
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NUCLEAR REGULATORY
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Acceptability of Probabilistic Risk
Assessment Results for Non-Light
Water Reactor Risk-Informed Activities
Nuclear Regulatory
Commission.
ACTION: Regulatory guide for trial use;
response to comments.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is addressing
comments received after issuing for
public comment on the trial use of the
new regulatory guide (RG) 1.247,
‘‘Acceptability of Probabilistic Risk
Assessment Results for Non-Light Water
Reactor Risk-Informed Activities.’’ The
NRC will not make any changes to the
RG as a result of these comments.
DATES: The public comment period for
RG 1.247 ended on May 23, 2022.
ADDRESSES: Please refer to Docket ID
NRC–2022–0052 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–2022–0052. Address
questions about Docket IDs in
Regulations.gov to Stacy Schumann;
telephone: 301–415–0624; email:
Stacy.Schumann@nrc.gov. For technical
questions, contact the individuals listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• NRC’s Agencywide Documents
Access and Management System
SUMMARY:
E:\FR\FM\17OCN1.SGM
17OCN1
Federal Register / Vol. 87, No. 199 / Monday, October 17, 2022 / Notices
(ADAMS): You may obtain publicly
available documents online in the
ADAMS Public Documents collection at
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‘‘Begin Web-based ADAMS Search.’’ For
problems with ADAMS, please contact
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4737, between 8:00 a.m. and 4:00 p.m.
Eastern Time (ET), Monday through
Friday, except Federal holidays.
RG 1.247 for trial use and the
regulatory analysis may be found in
ADAMS under Accession Nos.
ML21235A008 and ML21235A010,
respectively.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT:
Michelle Gonzalez, telephone: 301–415–
5661, email: Michelle.Gonzalez@
nrc.gov, Anders Gilbertson, telephone:
301–415–1541, email:
Anders.Gilbertson@nrc.gov, or Harriet
Karagiannis, telephone: 301–415–2493,
email: Harriet.Karagiannis@nrc.gov.
These individuals are staff in the Office
of Nuclear Regulatory Research at the
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
lotter on DSK11XQN23PROD with NOTICES1
I. Background
The NRC has issued for trial use this
new RG titled, ‘‘Acceptability of
Probabilistic Risk Assessment Results
for Non-Light Water Reactor RiskInformed Activities,’’ and it is
designated as trial use RG 1.247. It
describes one acceptable approach for
determining whether a design-specific
or plant-specific probabilistic risk
assessment (PRA) used to support an
application is sufficient to provide
confidence in the results, such that the
PRA can be used in regulatory decisionmaking for non-light water reactors
(NLWRs) for implementing the
requirements in part 50 and 52 of title
10 of the Code of Federal Regulations
(10 CFR). In addition, this trial use RG
VerDate Sep<11>2014
17:35 Oct 14, 2022
Jkt 259001
is intended to be consistent with the
NRC’s PRA Policy Statement and
reflects and endorses, with staff
exceptions, national consensus PRA
standards provided by standards
development organizations and
guidance provided by nuclear industry
organizations. As a trial use RG, this
issuance allows early use prior to
general implementation, and the
guidance may be revised based on
experience obtained by the NRC from
the implementation of the trial use RG.
The staff is planning to conduct a
public meeting by the end of calendar
year 2022 to obtain stakeholder
feedback on the development of a draft
guide, which will be issued at the
conclusion of the trial use period, and
subsequent final publication of RG
1.247. The NRC will also provide an
additional opportunity for formal public
comment on the planned draft RG, with
feedback considered prior to final RG
publication.
II. Public Comments
This trial use RG was not published
for public comment as a draft RG. Trial
use RG 1.247 was issued for a 60-day,
post-promulgation public comment in
the Federal Register on March 24, 2022
(87 FR 16770). Pursuant to 10 CFR
2.804(e), the NRC must publish in the
Federal Register an evaluation of any
significant comments and describe any
revisions made as a result of the
comments and their evaluation.
The public comment period ended on
May 23, 2022, and comments were
received from two organizations
(Nuclear Energy Institute (NEI) and Xenergy). NEI and X-energy submitted
separate comments on the staff
endorsement of items HLR–HR–E and
HR–E4 from the American Society of
Mechanical Engineers (ASME) and
American Nuclear Society (ANS) NLWR
PRA standard. The staff considers these
comments significant to the extent they
warrant a response to clarify the record.
While the staff is not responding in this
notice to the other comments submitted
in response to the opportunity to
comment the NRC published at 87 FR
16770, the staff will consider those
comments in preparing a draft of RG
1.247 for comment or in considering the
experience obtained through trial use of
RG 1.247.
For items HLR–HR–E and HR–E4, the
staff takes exceptions to the ASME and
ANS NLWR PRA standard regarding the
treatment of errors of commission
(EOCs) in a PRA. The exceptions
provide for consideration of EOCs that
result in adverse safety impacts for
Compatibility Category I, (CC–I). CC–I
defines the minimum capability needed
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62895
for a PRA element. In contrast,
Compatibility Category II (CC–II) defines
the minimum capability needed to meet
current good practice standards for each
PRA element. The comments indicate
that these exceptions are not consistent
with the current PRA state of practice,
which does not call for broad
consideration of EOCs for PRAs for
LWRs as per the NRC endorsement of
HR–E4 in the trial use RG. Thus, the
comment contends that broadly
considering EOCs goes above and
beyond the requirement for the current
operating fleet. Although no changes
were made to the trial use RG based on
these comments, the staff provides a
brief discussion on these significant
comments.
Specifically, the comment
recommends that this exception to HR–
E4 and the HLR–HR–E be removed from
the trial use RG or only be applicable for
CC–II of HR–E4, the latter of which
would represent good practice as
opposed to a minimum capability.
Another comment notes that the trial
use RG 1.247 includes additional
language on the scope of such
considerations; however, the comment
states that this added language does not
maintain consistency with the LWR
PRA standard. The comment supports
retaining consistency with the LWR
PRA standard in the trial use RG 1.247,
which would call for removal of this
added exception regarding
consideration of EOCs in the NLWR
PRA standard.
The staff is keeping the exceptions
related to EOCs in this trial use RG,
which is based on the following
consideration. The development efforts
for the ASME/ANS NLWR PRA
standard relied substantially on the
development efforts for the next edition
of the ASME/ANS Level 1/large early
release frequency (LERF) LWR PRA
standard and, in many cases, the NLWR
PRA standard adopted the same or
similar requirements as the next edition
of the Level 1/LERF LWR PRA standard.
However, the Level 1/LERF LWR PRA
standard state of practice relies on
significant LWR operating experience
that facilitates a consensus to generally
exclude EOCs from LWR PRAs, but no
similar body of operating experience
underlies the NLWR PRA standard.
Because there is limited operating
experience regarding EOCs for NLWRs
and the scope of the ASME/ANS NLWR
PRA standard is broader than the scope
of the ASME/ANS Level 1/LERF LWR
PRA standard, EOCs may play a more
important role in NLWR PRA than for
LWR PRA and, therefore, NLWR PRA
developers will need to demonstrate
that EOCs are not an issue before
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62896
Federal Register / Vol. 87, No. 199 / Monday, October 17, 2022 / Notices
lotter on DSK11XQN23PROD with NOTICES1
eliminating them from consideration.
However, the staff also notes that such
identification of EOCs is generally
expected to apply to a PRA developed
for the operational phase of a plant’s
lifecycle. This is based on the premise
that there is expected to be a general
lack of available, relevant information
that would allow meaningful
identification of EOCs in preoperational stages of a plant’s lifecycle.
Related staff guidance on the treatment
of such EOCs during pre-operational
phases of a plant’s lifecycle is currently
under development.
A comment states that EOCs are
already captured in FHR–A1 at CC–II for
fires where operating experience
supports consideration of spurious
signals. Therefore, the comment notes
that the RG 1.247 position on HR–E4
requiring EOCs at CC–I is not internally
consistent with the trial use RG position
on FHR–A1 requiring EOCs only at CC–
II. The comment also states that, for
non-fire hazards, spurious signals
should occur with low frequency and
would require significant operator error
due to the redundancy of information
available to the operator.
The staff notes that, while the
consideration of spurious signals as a
potential cause of an EOC is important
and spurious signals may occur due to
fire damage, such spurious signals are
not the only reason an EOC may occur.
NUREG–1880, ‘‘ATHEANA User’s
Guide,’’ (ADAMS Accession No.
ML072130359) recommends searching
for potential EOCs and the contexts that
could cause them. However, while the
staff maintains that other sources of
EOCs should be considered for
identification in CC–I of FHR–A1, the
staff did not intend for new, undesired
operator actions that could result from
spurious indications from fire-induced
failure of a single instrument to be
identified to meet CC–I of FHR–A1. The
staff would therefore not call for such
identification as part of meeting the trial
use RG. The staff notes that while the
comment characterizes the staff
positions as ‘‘requirements,’’ no
regulatory guide establishes
requirements. Rather, the exceptions
and clarifications in a regulatory guide
are guidance to an applicant stating
elements of an acceptable method for
complying with NRC regulations.
Dated: October 12, 2022.
For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guide and Programs
Management Branch, Division of Engineering,
Office of Nuclear Regulatory Research.
[FR Doc. 2022–22536 Filed 10–14–22; 8:45 am]
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POSTAL REGULATORY COMMISSION
[Docket Nos. MC2023–13 and CP2023–12]
New Postal Products
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Notice.
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ACTION:
The Commission is noticing a
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a negotiated service agreement. This
notice informs the public of the filing,
invites public comment, and takes other
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alternatives.
SUMMARY:
FOR FURTHER INFORMATION CONTACT:
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202–789–6820.
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Introduction
II. Docketed Proceeding(s)
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The Commission gives notice that the
Postal Service filed request(s) for the
Commission to consider matters related
to negotiated service agreement(s). The
request(s) may propose the addition or
removal of a negotiated service
agreement from the market dominant or
the competitive product list, or the
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Service request, the title of each Postal
Service request, the request’s acceptance
date, and the authority cited by the
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request, the Commission appoints an
officer of the Commission to represent
the interests of the general public in the
proceeding, pursuant to 39 U.S.C. 505
(Public Representative). Section II also
establishes comment deadline(s)
pertaining to each request.
The public portions of the Postal
Service’s request(s) can be accessed via
the Commission’s website (https://
www.prc.gov). Non-public portions of
the Postal Service’s request(s), if any,
can be accessed through compliance
PO 00000
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Fmt 4703
Sfmt 4703
with the requirements of 39 CFR
3011.301.1
The Commission invites comments on
whether the Postal Service’s request(s)
in the captioned docket(s) are consistent
with the policies of title 39. For
request(s) that the Postal Service states
concern market dominant product(s),
applicable statutory and regulatory
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that the Postal Service states concern
competitive product(s), applicable
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include 39 U.S.C. 3632, 39 U.S.C. 3633,
39 U.S.C. 3642, 39 CFR part 3035, and
39 CFR part 3040, subpart B. Comment
deadline(s) for each request appear in
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II. Docketed Proceeding(s)
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to Add Priority Mail Express, Priority
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Parcel Select Contract 65 to Competitive
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Public Representative: Kenneth R.
Moeller; Comments Due: October 19,
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This Notice will be published in the
Federal Register.
Erica A. Barker,
Secretary.
[FR Doc. 2022–22489 Filed 10–14–22; 8:45 am]
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1 See Docket No. RM2018–3, Order Adopting
Final Rules Relating to Non-Public Information,
June 27, 2018, Attachment A at 19–22 (Order No.
4679).
E:\FR\FM\17OCN1.SGM
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Agencies
[Federal Register Volume 87, Number 199 (Monday, October 17, 2022)]
[Notices]
[Pages 62894-62896]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2022-22536]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2022-0052]
Acceptability of Probabilistic Risk Assessment Results for Non-
Light Water Reactor Risk-Informed Activities
AGENCY: Nuclear Regulatory Commission.
ACTION: Regulatory guide for trial use; response to comments.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is addressing
comments received after issuing for public comment on the trial use of
the new regulatory guide (RG) 1.247, ``Acceptability of Probabilistic
Risk Assessment Results for Non-Light Water Reactor Risk-Informed
Activities.'' The NRC will not make any changes to the RG as a result
of these comments.
DATES: The public comment period for RG 1.247 ended on May 23, 2022.
ADDRESSES: Please refer to Docket ID NRC-2022-0052 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-2022-0052. Address
questions about Docket IDs in Regulations.gov to Stacy Schumann;
telephone: 301-415-0624; email: [email protected]. For technical
questions, contact the individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this document.
NRC's Agencywide Documents Access and Management System
[[Page 62895]]
(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 ADAMS accession number for each
document referenced (if it is available in ADAMS) is provided the first
time that it is mentioned in this document.
NRC's PDR: You may examine and purchase copies of public
documents, by appointment, at the NRC's PDR, Room P1 B35, One White
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. To make
an appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between
8:00 a.m. and 4:00 p.m. Eastern Time (ET), Monday through Friday,
except Federal holidays.
RG 1.247 for trial use and the regulatory analysis may be found in
ADAMS under Accession Nos. ML21235A008 and ML21235A010, respectively.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT: Michelle Gonzalez, telephone: 301-415-
5661, email: [email protected], Anders Gilbertson, telephone:
301-415-1541, email: [email protected], or Harriet Karagiannis,
telephone: 301-415-2493, email: [email protected]. These
individuals are staff in the Office of Nuclear Regulatory Research at
the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
I. Background
The NRC has issued for trial use this new RG titled,
``Acceptability of Probabilistic Risk Assessment Results for Non-Light
Water Reactor Risk-Informed Activities,'' and it is designated as trial
use RG 1.247. It describes one acceptable approach for determining
whether a design-specific or plant-specific probabilistic risk
assessment (PRA) used to support an application is sufficient to
provide confidence in the results, such that the PRA can be used in
regulatory decision-making for non-light water reactors (NLWRs) for
implementing the requirements in part 50 and 52 of title 10 of the Code
of Federal Regulations (10 CFR). In addition, this trial use RG is
intended to be consistent with the NRC's PRA Policy Statement and
reflects and endorses, with staff exceptions, national consensus PRA
standards provided by standards development organizations and guidance
provided by nuclear industry organizations. As a trial use RG, this
issuance allows early use prior to general implementation, and the
guidance may be revised based on experience obtained by the NRC from
the implementation of the trial use RG.
The staff is planning to conduct a public meeting by the end of
calendar year 2022 to obtain stakeholder feedback on the development of
a draft guide, which will be issued at the conclusion of the trial use
period, and subsequent final publication of RG 1.247. The NRC will also
provide an additional opportunity for formal public comment on the
planned draft RG, with feedback considered prior to final RG
publication.
II. Public Comments
This trial use RG was not published for public comment as a draft
RG. Trial use RG 1.247 was issued for a 60-day, post-promulgation
public comment in the Federal Register on March 24, 2022 (87 FR 16770).
Pursuant to 10 CFR 2.804(e), the NRC must publish in the Federal
Register an evaluation of any significant comments and describe any
revisions made as a result of the comments and their evaluation.
The public comment period ended on May 23, 2022, and comments were
received from two organizations (Nuclear Energy Institute (NEI) and X-
energy). NEI and X-energy submitted separate comments on the staff
endorsement of items HLR-HR-E and HR-E4 from the American Society of
Mechanical Engineers (ASME) and American Nuclear Society (ANS) NLWR PRA
standard. The staff considers these comments significant to the extent
they warrant a response to clarify the record. While the staff is not
responding in this notice to the other comments submitted in response
to the opportunity to comment the NRC published at 87 FR 16770, the
staff will consider those comments in preparing a draft of RG 1.247 for
comment or in considering the experience obtained through trial use of
RG 1.247.
For items HLR-HR-E and HR-E4, the staff takes exceptions to the
ASME and ANS NLWR PRA standard regarding the treatment of errors of
commission (EOCs) in a PRA. The exceptions provide for consideration of
EOCs that result in adverse safety impacts for Compatibility Category
I, (CC-I). CC-I defines the minimum capability needed for a PRA
element. In contrast, Compatibility Category II (CC-II) defines the
minimum capability needed to meet current good practice standards for
each PRA element. The comments indicate that these exceptions are not
consistent with the current PRA state of practice, which does not call
for broad consideration of EOCs for PRAs for LWRs as per the NRC
endorsement of HR-E4 in the trial use RG. Thus, the comment contends
that broadly considering EOCs goes above and beyond the requirement for
the current operating fleet. Although no changes were made to the trial
use RG based on these comments, the staff provides a brief discussion
on these significant comments.
Specifically, the comment recommends that this exception to HR-E4
and the HLR-HR-E be removed from the trial use RG or only be applicable
for CC-II of HR-E4, the latter of which would represent good practice
as opposed to a minimum capability. Another comment notes that the
trial use RG 1.247 includes additional language on the scope of such
considerations; however, the comment states that this added language
does not maintain consistency with the LWR PRA standard. The comment
supports retaining consistency with the LWR PRA standard in the trial
use RG 1.247, which would call for removal of this added exception
regarding consideration of EOCs in the NLWR PRA standard.
The staff is keeping the exceptions related to EOCs in this trial
use RG, which is based on the following consideration. The development
efforts for the ASME/ANS NLWR PRA standard relied substantially on the
development efforts for the next edition of the ASME/ANS Level 1/large
early release frequency (LERF) LWR PRA standard and, in many cases, the
NLWR PRA standard adopted the same or similar requirements as the next
edition of the Level 1/LERF LWR PRA standard. However, the Level 1/LERF
LWR PRA standard state of practice relies on significant LWR operating
experience that facilitates a consensus to generally exclude EOCs from
LWR PRAs, but no similar body of operating experience underlies the
NLWR PRA standard.
Because there is limited operating experience regarding EOCs for
NLWRs and the scope of the ASME/ANS NLWR PRA standard is broader than
the scope of the ASME/ANS Level 1/LERF LWR PRA standard, EOCs may play
a more important role in NLWR PRA than for LWR PRA and, therefore, NLWR
PRA developers will need to demonstrate that EOCs are not an issue
before
[[Page 62896]]
eliminating them from consideration. However, the staff also notes that
such identification of EOCs is generally expected to apply to a PRA
developed for the operational phase of a plant's lifecycle. This is
based on the premise that there is expected to be a general lack of
available, relevant information that would allow meaningful
identification of EOCs in pre-operational stages of a plant's
lifecycle. Related staff guidance on the treatment of such EOCs during
pre-operational phases of a plant's lifecycle is currently under
development.
A comment states that EOCs are already captured in FHR-A1 at CC-II
for fires where operating experience supports consideration of spurious
signals. Therefore, the comment notes that the RG 1.247 position on HR-
E4 requiring EOCs at CC-I is not internally consistent with the trial
use RG position on FHR-A1 requiring EOCs only at CC-II. The comment
also states that, for non-fire hazards, spurious signals should occur
with low frequency and would require significant operator error due to
the redundancy of information available to the operator.
The staff notes that, while the consideration of spurious signals
as a potential cause of an EOC is important and spurious signals may
occur due to fire damage, such spurious signals are not the only reason
an EOC may occur. NUREG-1880, ``ATHEANA User's Guide,'' (ADAMS
Accession No. ML072130359) recommends searching for potential EOCs and
the contexts that could cause them. However, while the staff maintains
that other sources of EOCs should be considered for identification in
CC-I of FHR-A1, the staff did not intend for new, undesired operator
actions that could result from spurious indications from fire-induced
failure of a single instrument to be identified to meet CC-I of FHR-A1.
The staff would therefore not call for such identification as part of
meeting the trial use RG. The staff notes that while the comment
characterizes the staff positions as ``requirements,'' no regulatory
guide establishes requirements. Rather, the exceptions and
clarifications in a regulatory guide are guidance to an applicant
stating elements of an acceptable method for complying with NRC
regulations.
Dated: October 12, 2022.
For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guide and Programs Management Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2022-22536 Filed 10-14-22; 8:45 am]
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