Regulation of Advanced Nuclear Power Plants; Draft Statement of Policy, 26349-26351 [E8-10443]
Download as PDF
Federal Register / Vol. 73, No. 91 / Friday, May 9, 2008 / Proposed Rules
Accordingly, we propose to amend 9
CFR part 2 as follows:
PART 2—REGULATIONS
1. The authority citation for part 2
continues to read as follows:
Authority: 7 U.S.C. 2131–2159; 7 CFR 2.22,
2.80, and 371.7.
2. Section 2.130 is revised to read as
follows:
rwilkins on PROD1PC63 with PROPOSALS
§ 2.130
Minimum age requirements.
(a) Unless being transported in the
same enclosure as its mother or
documented surrogate mother, no
animal, other than birds, except as
provided in paragraphs (b) and (c) of
this section, shall be delivered by any
person to any carrier or intermediate
handler for transportation in commerce,
or be transported in commerce by any
person unless such animal has been
weaned and is at least 8 weeks of age.
(b)(1) Persons wishing to transport an
animal that has not been weaned and
that is not at least 8 weeks of age
without its mother or documented
surrogate mother to a registered research
facility for a specific protocol approved
by the Institutional Animal Care and
Use Committees (IACUC) must obtain
prior written approval by the
appropriate Animal Care regional office
by submitting, in writing, a
transportation plan signed by the
attending veterinarian and head of the
animal caregiving staff outlining the
reason for the transport (including the
IACUC-approved protocol involved, if
applicable), transportation specifics
(including, but not limited to, dates,
destination, intermediate carrier or
handler to be used, mode of
transportation, and enclosure size and
design), food and water arrangements,
attendants and/or monitoring plan,
contact provisions in case of medical or
other care needs, and, for nonhuman
primates, how the special needs of the
infant will be met during transportation
(in support of the requirements of
§ 3.81).
(2) One transportation plan may be
submitted for multiple animals being
transported from one facility if the plan
can show that the needs of all of the
animals have been accommodated as
determined by Animal Care.
(3) Transportation plans submitted via
e-mail or facsimile must also include
the names, mailing addresses, and
phone numbers of the attending
veterinarian and head of the animal
caregiving staff. Those submitting plans
via e-mail or facsimile must also keep
on file a copy of the transportation plan
that is signed by the attending
veterinarian and head of the animal
VerDate Aug<31>2005
16:15 May 08, 2008
Jkt 214001
caregiving staff and make the plan
available to Animal Care upon request.
(c)(1) Persons may transport an
animal that has not been weaned and
that is not at least 8 weeks of age
without its mother or documented
surrogate mother to a licensed
veterinarian for routine medical care,
provided the animal is returned to the
licensed or registered facility from
which it originated upon the completion
of the medical care for which it was
transported and no change of ownership
is involved. If those conditions are not
met, then persons wishing to transport
animals that have not been weaned and
that are not at least 8 weeks of age for
routine medical care must obtain
approval from the appropriate Animal
Care regional office by submitting a
transportation plan in accordance with
paragraph (b) of this section.
(2) One transportation plan may be
submitted for multiple animals being
transported from one facility if the plan
can show that the needs of all of the
animals have been accommodated as
determined by Animal Care.
(3) Persons may transport animals that
have not been weaned and that are not
at least 8 weeks of age to a licensed
veterinarian for emergency medical care
without a transportation plan.
Done in Washington, DC, this 5th day of
May 2008.
Bruce Knight,
Under Secretary for Marketing and Regulatory
Programs.
[FR Doc. E8–10400 Filed 5–8–08; 8:45 am]
BILLING CODE 3410–34–P
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 50
[NRC–2008–0237]
Regulation of Advanced Nuclear Power
Plants; Draft Statement of Policy
U.S. Nuclear Regulatory
Commission.
ACTION: Issuance of draft policy
statement and notice of opportunity for
public comment.
AGENCY:
SUMMARY: The Nuclear Regulatory
Commission (NRC) is considering
adopting a statement of policy to
improve the licensing environment for
advanced nuclear power reactors to
minimize complexity and uncertainty in
the regulatory process. This statement
would provide the Commission’s policy
regarding the review of, and desired
characteristics associated with,
advanced reactors. This policy
PO 00000
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Fmt 4702
Sfmt 4702
26349
statement would be the second revision
of the policy statement titled
‘‘Regulation of Advanced Nuclear Power
Plants; Statement of Policy.’’ The
purpose of this revision is to update the
Commission’s policy statement on
advanced reactors to integrate the
Commission’s expectations for security
and preparedness with the current
expectations for safety. This draft policy
statement is being issued for public
comment.
Comments on this document
should be submitted by July 8, 2008.
Comments received after that date will
be considered to the extent practical. To
ensure efficient and complete comment
resolution, comments should include
references to the section, page, and line
numbers of the document to which the
comment applies, if possible.
ADDRESSES: You may submit comments
by any one of the following methods.
Comments submitted in writing or in
electronic form will be made available
for public inspection. Because your
comments will not be edited to remove
any identifying or contact information,
the NRC cautions you against including
any information in your submission that
you do not want to be publicly
disclosed.
Federal e-Rulemaking Portal: Go to
https://www.regulations.gov and search
for documents filed under Docket ID
[NRC–2008–0237]. Address questions
about NRC dockets to Carol Gallagher
301–415–5905, e-mail
Carol.Gallagher@nrc.gov.
Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, ATTN:
Rulemakings and Adjudications Staff.
E-mail comments to:
Rulemaking.Comments@nrc.gov. If you
do not receive a reply e-mail confirming
that we have received your comments,
contact us directly at 301–415–1966.
Hand deliver comments to: 11555
Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m.
Federal workdays. (Telephone 301–415–
1966.)
Fax comments to: Secretary, U.S.
Nuclear Regulatory Commission at 301–
415–1101.
You can access publicly available
documents related to this document
using the following methods:
NRC’s Public Document Room (PDR):
The public may examine and have
copied for a fee publicly available
documents at the NRC’s PDR, Public
File Area O F21, One White Flint North,
11555 Rockville Pike, Rockville,
Maryland.
NRC’s Agencywide Documents Access
and Management System (ADAMS):
DATES:
E:\FR\FM\09MYP1.SGM
09MYP1
26350
Federal Register / Vol. 73, No. 91 / Friday, May 9, 2008 / Proposed Rules
rwilkins on PROD1PC63 with PROPOSALS
Publicy available documents created or
received at the NRC are available
electronically at the NRC’s electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this page,
the public can gain entry into ADAMS,
which provides text and image files of
NRC’s public documents. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC’s
PDR reference staff at 1–899–397–4209,
301–415–4737, or by e-mail to
pdr.resources@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
Wesley H. Held, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001,
Telephone: 301–415–1583, e-mail:
Wesley.Held@nrc.gov.
SUPPLEMENTARY INFORMATION:
Background
On July 8, 1986 (51 FR 24643), the
Commission published a policy
statement on regulation of advanced
reactors in the Federal Register. The
Commission’s primary objectives in
issuing the advanced reactor policy
statement were as follows:
• To maintain the earliest possible
interaction of applicants, vendors, and
government agencies with the NRC.
• To provide all interested parties,
including the public, with the
Commission’s views concerning the
desired characteristics of advanced
reactor designs.
• To express the Commission’s intent
to issue timely comment on the
implications of such designs for safety
and the regulatory process.
On July 12, 1994 (59 FR 35461), the
Commission revised the 1986 advanced
reactor policy statement by addressing
the Commission’s policy on metrication
(57 FR 46202; October 7, 1992; as
revised June 19, 1996 (61 FR 31169)).
Since the events of September 11,
2001, the NRC has assessed potential
threats and their possible impacts on the
Nation’s fleet of operating nuclear
power reactors and has required
upgrades of physical security measures
and mitigative strategies through the
issuance of a series of security orders
and license conditions. For new nuclear
power reactors, the Commission
considers it prudent to provide
expectations and guidance on security
matters to prospective applicants so that
they can use this information early in
the design stage to identify potential
mitigative measures and/or design
features that provide a more robust and
effective security posture. Therefore, the
Commission decided to revise the
advanced reactor policy statement to
VerDate Aug<31>2005
16:15 May 08, 2008
Jkt 214001
integrate these expectations for security
and preparedness with the current
expectations for safety.
The NRC is seeking public comment
in order to receive feedback from the
widest range of interested parties and to
ensure that all information relevant to
developing this document is available to
the NRC staff. This document is issued
for comment only. The NRC will review
public comments received on the
document, incorporate suggested
changes as necessary, and issue the final
revision.
Commission Policy
Consistent with its legislative
mandate, the Commission’s policy with
respect to regulating nuclear power
reactors is to ensure adequate protection
of the environment and public health
and safety and common defense and
security. Regarding advanced reactors,
the Commission expects, as a minimum,
at least the same degree of protection of
the environment and public health and
safety and the common defense and
security, that is required for currentgeneration light-water reactors.
Furthermore, the Commission expects
that advanced reactors will provide
enhanced margins of safety and/or use
simplified, inherent, passive, or other
innovative means to accomplish their
safety and security functions.
The Commission’s expectation for
advanced reactor designs that consider
the effects of a large, commercial
airplane impact is currently being
addressed through rulemaking
(Consideration of Aircraft Impacts for
New Nuclear Power Reactor Designs—
RIN AI19—ID Docket NRC–2007–0009).
The Commission believes that reactors
designed with potential aircraft impact
considerations resulting from this rule
would be more robust than if they were
designed in the absence of this rule.
Among the attributes that could assist
in establishing the acceptability or
licensability of a proposed advanced
reactor design, and therefore should be
considered in advanced designs, are:
• Highly reliable and less complex
shutdown and decay heat removal
systems. The use of inherent or passive
means to accomplish this objective is
encouraged (negative temperature
coefficient, natural circulation, etc.).
• Longer time constants and
sufficient instrumentation to allow for
more diagnosis and management before
reaching safety systems challenge and/
or exposure of vital equipment to
adverse conditions.
• Simplified safety systems that,
where possible, reduce required
operator actions, equipment subjected to
severe environmental conditions, and
PO 00000
Frm 00011
Fmt 4702
Sfmt 4702
components needed for maintaining safe
shutdown conditions. Such simplified
systems should facilitate operator
comprehension, reliable system
function, and more straightforward
engineering analysis.
• Designs that minimize the potential
for severe accidents and their
consequences by providing sufficient
inherent safety, reliability, redundancy,
diversity, and independence in safety
systems.
• Designs that provide reliable
equipment in the balance of plant (BOP)
(or safety-system independence from
BOP) to reduce the number of
challenges to safety systems.
• Designs that provide easily
maintainable equipment and
components.
• Designs that reduce potential
radiation exposures to plant personnel.
• Designs that incorporate the
defense-in-depth philosophy by
maintaining multiple barriers against
radiation release, and by reducing the
potential for, and consequences of,
severe accidents.
• Design features that can be proven
by citation of existing technology, or
that can be satisfactorily established by
commitment to a suitable technology
development program.
• Designs that include considerations
for safety and security requirements
together in the design process such that
security issues (e.g., newly identified
threats of terrorist attacks) can be
effectively resolved through facility
design and engineered security features,
and formulation of mitigation measures,
with reduced reliance on human
actions.
• Designs with features to prevent a
simultaneous loss of containment
integrity (including situations where the
containment is by-passed), and the
ability to maintain core cooling as a
result of an aircraft impact, or
identification of system designs that
would provide inherent delay in
radiological releases (if prevention of
release is not possible).
• Designs with features to prevent
loss of spent fuel pool integrity as a
result of an aircraft impact.
If specific advanced reactor designs
with some or all of the previously
mentioned attributes are brought to the
NRC for comment and/or evaluation, the
Commission can develop preliminary
design safety evaluation and licensing
criteria for their safety-related and
security-related aspects. Incorporating
the above attributes may promote more
efficient and effective design reviews.
However, the listing of a particular
attribute does not necessarily mean that
specific licensing criteria will attach to
E:\FR\FM\09MYP1.SGM
09MYP1
rwilkins on PROD1PC63 with PROPOSALS
Federal Register / Vol. 73, No. 91 / Friday, May 9, 2008 / Proposed Rules
that attribute. Designs with some or all
of these attributes are also likely to be
more readily understood by the general
public. Indeed, the number and nature
of the regulatory requirements may
depend on the extent to which an
individual advanced reactor design
incorporates general attributes such as
those listed previously.
In addition, the Commission expects
that the safety features of these
advanced reactor designs will be
complemented by the operational
program for Emergency Planning (EP).
This EP operational program, in turn,
must be demonstrated by inspections,
tests, analyses, and acceptance criteria
to ensure effective implementation of
established measures. The Commission
also expects that advanced reactor
designs will comply with the
Commission’s safety goal policy
statement (51 FR 28044; August 4, 1986
as corrected and republished at 51 FR
30028; August 21, 1986), and the policy
statement on conversion to the metric
measurement system (61 FR 31169; June
19, 1996).
To provide for more timely and
effective regulation of advanced
reactors, the Commission encourages
the earliest possible interaction of
applicants, vendors, other government
agencies, and the NRC to provide for
early identification of regulatory
requirements for advanced reactors and
to provide all interested parties,
including the public, with a timely,
independent assessment of the safety
and security characteristics of advanced
reactor designs. Such licensing
interaction and guidance early in the
design process will contribute towards
minimizing complexity and adding
stability and predictability in the
licensing and regulation of advanced
reactors.
While the NRC does not develop new
designs, the Commission intends to
develop the capability, when
appropriate, for timely assessment and
response to innovative and advanced
designs that might be presented for NRC
review. Prior experience has shown that
new reactor designs—even variations of
established designs—may involve
technical problems that must be solved
to ensure adequate protection of the
public health and safety. The earlier
these design problems are identified, the
earlier satisfactory resolution can be
achieved. Prospective applicants are
reminded that, while the NRC will
undertake to review and comment on
new design concepts, the applicants are
responsible for documentation and
research necessary to support a specific
application. Research activities would
include testing of new safety or security
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16:15 May 08, 2008
Jkt 214001
features that differ from existing designs
for operating reactors, or that use
simplified, inherent, passive means to
accomplish their safety or security
function. The testing shall ensure that
these new features will perform as
predicted, provide collection of
sufficient data to validate computer
codes, and show that the effects of
system interactions are acceptable.
During the initial phase of advanced
reactor development, the Commission
particularly encourages design
innovations that enhance safety,
reliability, and security (such as those
described previously) and that generally
depend on technology that is either
proven or can be demonstrated by a
straightforward technology development
program. In the absence of a significant
history of operating experience on an
advanced concept reactor, plans for
innovative use of proven technology
and/or new technology development
programs should be presented to the
NRC for review as early as possible, so
that the NRC can assess how the
proposed program might influence
regulatory requirements.
Finally, the NRC also believes that it
will be in the interest of the public as
well as the design vendors’ and the
prospective license applicants to
address security issues early in the
design stage to achieve a more robust
and effective security posture for future
nuclear power reactors.
Dated at Rockville, Maryland, this 5th day
of May 2008.
For the Nuclear Regulatory Commission,
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. E8–10443 Filed 5–8–08; 8:45 am]
BILLING CODE 7590–01–P
DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 39
[Docket No. FAA–2008–0536; Directorate
Identifier 2008–CE–030–AD]
RIN 2120–AA64
Airworthiness Directives; APEX
Aircraft Model CAP 10 B Airplanes
Federal Aviation
Administration (FAA), Department of
Transportation (DOT).
ACTION: Notice of proposed rulemaking
(NPRM).
AGENCY:
SUMMARY: We propose to adopt a new
airworthiness directive (AD) for the
products listed above. This proposed
AD results from mandatory continuing
PO 00000
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Fmt 4702
Sfmt 4702
26351
airworthiness information (MCAI)
originated by an aviation authority of
another country to identify and correct
an unsafe condition on an aviation
product. The MCAI describes the unsafe
condition as:
It has been determined that the currently
used values for Arms of front and rear fuel
tanks, and luggage compartment from the
CAP 10B Airplane Flight Manuals (AFM),
must be rectified.
If left uncorrected, these weight and
balance data could lead to erroneous
determination of the location of the Center of
Gravity (CG) and possibly cause operation
with the CG outside the approved limits
which may result in control difficulty.
The proposed AD would require actions
that are intended to address the unsafe
condition described in the MCAI.
DATES: We must receive comments on
this proposed AD by June 9, 2008.
ADDRESSES: You may send comments by
any of the following methods:
• Federal eRulemaking Portal: Go to
https://www.regulations.gov. Follow the
instructions for submitting comments.
• Fax: (202) 493–2251.
• Mail: U.S. Department of
Transportation, Docket Operations,
M–30, West Building Ground Floor,
Room W12–140, 1200 New Jersey
Avenue, SE., Washington, DC 20590.
• Hand Delivery: U.S. Department of
Transportation, Docket Operations,
M–30, West Building Ground Floor,
Room W12–140, 1200 New Jersey
Avenue, SE., Washington, DC 20590,
between 9 a.m. and 5 p.m., Monday
through Friday, except Federal holidays.
Examining the AD Docket
You may examine the AD docket on
the Internet at https://
www.regulations.gov; or in person at the
Docket Management Facility between
9 a.m. and 5 p.m., Monday through
Friday, except Federal holidays. The AD
docket contains this proposed AD, the
regulatory evaluation, any comments
received, and other information. The
street address for the Docket Office
(telephone (800) 647–5527) is in the
ADDRESSES section. Comments will be
available in the AD docket shortly after
receipt.
FOR FURTHER INFORMATION CONTACT:
Sarjapur Nagarajan, Aerospace Engineer,
FAA, Small Airplane Directorate, 901
Locust, Room 301, Kansas City,
Missouri 64106; telephone: (816) 329–
4145; fax: (816) 329–4090.
SUPPLEMENTARY INFORMATION:
Comments Invited
We invite you to send any written
relevant data, views, or arguments about
this proposed AD. Send your comments
E:\FR\FM\09MYP1.SGM
09MYP1
Agencies
[Federal Register Volume 73, Number 91 (Friday, May 9, 2008)]
[Proposed Rules]
[Pages 26349-26351]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-10443]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Part 50
[NRC-2008-0237]
Regulation of Advanced Nuclear Power Plants; Draft Statement of
Policy
AGENCY: U.S. Nuclear Regulatory Commission.
ACTION: Issuance of draft policy statement and notice of opportunity
for public comment.
-----------------------------------------------------------------------
SUMMARY: The Nuclear Regulatory Commission (NRC) is considering
adopting a statement of policy to improve the licensing environment for
advanced nuclear power reactors to minimize complexity and uncertainty
in the regulatory process. This statement would provide the
Commission's policy regarding the review of, and desired
characteristics associated with, advanced reactors. This policy
statement would be the second revision of the policy statement titled
``Regulation of Advanced Nuclear Power Plants; Statement of Policy.''
The purpose of this revision is to update the Commission's policy
statement on advanced reactors to integrate the Commission's
expectations for security and preparedness with the current
expectations for safety. This draft policy statement is being issued
for public comment.
DATES: Comments on this document should be submitted by July 8, 2008.
Comments received after that date will be considered to the extent
practical. To ensure efficient and complete comment resolution,
comments should include references to the section, page, and line
numbers of the document to which the comment applies, if possible.
ADDRESSES: You may submit comments by any one of the following methods.
Comments submitted in writing or in electronic form will be made
available for public inspection. Because your comments will not be
edited to remove any identifying or contact information, the NRC
cautions you against including any information in your submission that
you do not want to be publicly disclosed.
Federal e-Rulemaking Portal: Go to https://www.regulations.gov and
search for documents filed under Docket ID [NRC-2008-0237]. Address
questions about NRC dockets to Carol Gallagher 301-415-5905, e-mail
Carol.Gallagher@nrc.gov.
Mail comments to: Secretary, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff.
E-mail comments to: Rulemaking.Comments@nrc.gov. If you do not
receive a reply e-mail confirming that we have received your comments,
contact us directly at 301-415-1966.
Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m. Federal workdays. (Telephone
301-415-1966.)
Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at
301-415-1101.
You can access publicly available documents related to this
document using the following methods:
NRC's Public Document Room (PDR): The public may examine and have
copied for a fee publicly available documents at the NRC's PDR, Public
File Area O F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland.
NRC's Agencywide Documents Access and Management System (ADAMS):
[[Page 26350]]
Publicy available documents created or received at the NRC are
available electronically at the NRC's electronic Reading Room at http:/
/www.nrc.gov/reading-rm/adams.html. From this page, the public can gain
entry into ADAMS, which provides text and image files of NRC's public
documents. If you do not have access to ADAMS or if there are problems
in accessing the documents located in ADAMS, contact the NRC's PDR
reference staff at 1-899-397-4209, 301-415-4737, or by e-mail to
pdr.resources@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Wesley H. Held, Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, Telephone: 301-415-1583, e-mail: Wesley.Held@nrc.gov.
SUPPLEMENTARY INFORMATION:
Background
On July 8, 1986 (51 FR 24643), the Commission published a policy
statement on regulation of advanced reactors in the Federal Register.
The Commission's primary objectives in issuing the advanced reactor
policy statement were as follows:
To maintain the earliest possible interaction of
applicants, vendors, and government agencies with the NRC.
To provide all interested parties, including the public,
with the Commission's views concerning the desired characteristics of
advanced reactor designs.
To express the Commission's intent to issue timely comment
on the implications of such designs for safety and the regulatory
process.
On July 12, 1994 (59 FR 35461), the Commission revised the 1986
advanced reactor policy statement by addressing the Commission's policy
on metrication (57 FR 46202; October 7, 1992; as revised June 19, 1996
(61 FR 31169)).
Since the events of September 11, 2001, the NRC has assessed
potential threats and their possible impacts on the Nation's fleet of
operating nuclear power reactors and has required upgrades of physical
security measures and mitigative strategies through the issuance of a
series of security orders and license conditions. For new nuclear power
reactors, the Commission considers it prudent to provide expectations
and guidance on security matters to prospective applicants so that they
can use this information early in the design stage to identify
potential mitigative measures and/or design features that provide a
more robust and effective security posture. Therefore, the Commission
decided to revise the advanced reactor policy statement to integrate
these expectations for security and preparedness with the current
expectations for safety.
The NRC is seeking public comment in order to receive feedback from
the widest range of interested parties and to ensure that all
information relevant to developing this document is available to the
NRC staff. This document is issued for comment only. The NRC will
review public comments received on the document, incorporate suggested
changes as necessary, and issue the final revision.
Commission Policy
Consistent with its legislative mandate, the Commission's policy
with respect to regulating nuclear power reactors is to ensure adequate
protection of the environment and public health and safety and common
defense and security. Regarding advanced reactors, the Commission
expects, as a minimum, at least the same degree of protection of the
environment and public health and safety and the common defense and
security, that is required for current-generation light-water reactors.
Furthermore, the Commission expects that advanced reactors will provide
enhanced margins of safety and/or use simplified, inherent, passive, or
other innovative means to accomplish their safety and security
functions.
The Commission's expectation for advanced reactor designs that
consider the effects of a large, commercial airplane impact is
currently being addressed through rulemaking (Consideration of Aircraft
Impacts for New Nuclear Power Reactor Designs--RIN AI19--ID Docket NRC-
2007-0009). The Commission believes that reactors designed with
potential aircraft impact considerations resulting from this rule would
be more robust than if they were designed in the absence of this rule.
Among the attributes that could assist in establishing the
acceptability or licensability of a proposed advanced reactor design,
and therefore should be considered in advanced designs, are:
Highly reliable and less complex shutdown and decay heat
removal systems. The use of inherent or passive means to accomplish
this objective is encouraged (negative temperature coefficient, natural
circulation, etc.).
Longer time constants and sufficient instrumentation to
allow for more diagnosis and management before reaching safety systems
challenge and/or exposure of vital equipment to adverse conditions.
Simplified safety systems that, where possible, reduce
required operator actions, equipment subjected to severe environmental
conditions, and components needed for maintaining safe shutdown
conditions. Such simplified systems should facilitate operator
comprehension, reliable system function, and more straightforward
engineering analysis.
Designs that minimize the potential for severe accidents
and their consequences by providing sufficient inherent safety,
reliability, redundancy, diversity, and independence in safety systems.
Designs that provide reliable equipment in the balance of
plant (BOP) (or safety-system independence from BOP) to reduce the
number of challenges to safety systems.
Designs that provide easily maintainable equipment and
components.
Designs that reduce potential radiation exposures to plant
personnel.
Designs that incorporate the defense-in-depth philosophy
by maintaining multiple barriers against radiation release, and by
reducing the potential for, and consequences of, severe accidents.
Design features that can be proven by citation of existing
technology, or that can be satisfactorily established by commitment to
a suitable technology development program.
Designs that include considerations for safety and
security requirements together in the design process such that security
issues (e.g., newly identified threats of terrorist attacks) can be
effectively resolved through facility design and engineered security
features, and formulation of mitigation measures, with reduced reliance
on human actions.
Designs with features to prevent a simultaneous loss of
containment integrity (including situations where the containment is
by-passed), and the ability to maintain core cooling as a result of an
aircraft impact, or identification of system designs that would provide
inherent delay in radiological releases (if prevention of release is
not possible).
Designs with features to prevent loss of spent fuel pool
integrity as a result of an aircraft impact.
If specific advanced reactor designs with some or all of the
previously mentioned attributes are brought to the NRC for comment and/
or evaluation, the Commission can develop preliminary design safety
evaluation and licensing criteria for their safety-related and
security-related aspects. Incorporating the above attributes may
promote more efficient and effective design reviews. However, the
listing of a particular attribute does not necessarily mean that
specific licensing criteria will attach to
[[Page 26351]]
that attribute. Designs with some or all of these attributes are also
likely to be more readily understood by the general public. Indeed, the
number and nature of the regulatory requirements may depend on the
extent to which an individual advanced reactor design incorporates
general attributes such as those listed previously.
In addition, the Commission expects that the safety features of
these advanced reactor designs will be complemented by the operational
program for Emergency Planning (EP). This EP operational program, in
turn, must be demonstrated by inspections, tests, analyses, and
acceptance criteria to ensure effective implementation of established
measures. The Commission also expects that advanced reactor designs
will comply with the Commission's safety goal policy statement (51 FR
28044; August 4, 1986 as corrected and republished at 51 FR 30028;
August 21, 1986), and the policy statement on conversion to the metric
measurement system (61 FR 31169; June 19, 1996).
To provide for more timely and effective regulation of advanced
reactors, the Commission encourages the earliest possible interaction
of applicants, vendors, other government agencies, and the NRC to
provide for early identification of regulatory requirements for
advanced reactors and to provide all interested parties, including the
public, with a timely, independent assessment of the safety and
security characteristics of advanced reactor designs. Such licensing
interaction and guidance early in the design process will contribute
towards minimizing complexity and adding stability and predictability
in the licensing and regulation of advanced reactors.
While the NRC does not develop new designs, the Commission intends
to develop the capability, when appropriate, for timely assessment and
response to innovative and advanced designs that might be presented for
NRC review. Prior experience has shown that new reactor designs--even
variations of established designs--may involve technical problems that
must be solved to ensure adequate protection of the public health and
safety. The earlier these design problems are identified, the earlier
satisfactory resolution can be achieved. Prospective applicants are
reminded that, while the NRC will undertake to review and comment on
new design concepts, the applicants are responsible for documentation
and research necessary to support a specific application. Research
activities would include testing of new safety or security features
that differ from existing designs for operating reactors, or that use
simplified, inherent, passive means to accomplish their safety or
security function. The testing shall ensure that these new features
will perform as predicted, provide collection of sufficient data to
validate computer codes, and show that the effects of system
interactions are acceptable.
During the initial phase of advanced reactor development, the
Commission particularly encourages design innovations that enhance
safety, reliability, and security (such as those described previously)
and that generally depend on technology that is either proven or can be
demonstrated by a straightforward technology development program. In
the absence of a significant history of operating experience on an
advanced concept reactor, plans for innovative use of proven technology
and/or new technology development programs should be presented to the
NRC for review as early as possible, so that the NRC can assess how the
proposed program might influence regulatory requirements.
Finally, the NRC also believes that it will be in the interest of
the public as well as the design vendors' and the prospective license
applicants to address security issues early in the design stage to
achieve a more robust and effective security posture for future nuclear
power reactors.
Dated at Rockville, Maryland, this 5th day of May 2008.
For the Nuclear Regulatory Commission,
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. E8-10443 Filed 5-8-08; 8:45 am]
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