Protection of Safeguards Information, 7196-7217 [05-2665]
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Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules
any criminal statutes or other ethics rules.
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course of an otherwise approvable activity,
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contemplated, that nevertheless, pose ethical
concerns. SSA ethics officials are available to
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[FR Doc. 05–2644 Filed 2–10–05; 8:45 am]
BILLING CODE 4191–02–P
NUCLEAR REGULATORY
COMMISSION
10 CFR Parts 2, 30, 40, 50, 52, 60, 63,
70, 71, 72, 73, 76 and 150
RIN: 3150–AH57
Protection of Safeguards Information
Nuclear Regulatory
Commission.
ACTION: Proposed rule.
AGENCY:
SUMMARY: The Nuclear Regulatory
Commission (NRC) is proposing to
amend its regulations for the protection
of Safeguards Information (SGI) to
protect SGI from inadvertent release and
unauthorized disclosure which might
compromise the security of nuclear
facilities and materials. The proposed
amendments are consistent with recent
Commission practices reflected in
orders and threat advisories, issued
since September 11, 2001. The proposed
amendments would affect certain
licensees, information, and materials
not currently specified in the
regulations, but which are within the
scope of Commission authority under
the Atomic Energy Act of 1954, as
amended (AEA).
DATES: The comment period expires
March 28, 2005. Submit comments
specific to the information collections
aspects of this rule March 14, 2005.
Comments received after that date will
be considered if it is practical to do so,
but the NRC is able to ensure
consideration only for comments
received on or before this date.
ADDRESSES: You may submit comments
by any one of the following methods.
Please include the following number
(RIN 3150–AH57) in the subject line of
your comments. Comments on this
rulemaking 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
personal information such as social
security numbers and birth dates in
your submission.
Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
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Washington, DC 20555–0001, Attn:
Rulemakings and Adjudications Staff.
E-mail comments to: SECY@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. You may also submit
comments via the NRC’s rulemaking
Web site at https://ruleforum.llnl.gov.
Address questions about our rulemaking
Web site to Carol Gallagher at (301)
415–5905; e-mail cag@nrc.gov.
Comments can also be submitted via the
Federal Rulemaking Portal https://
www.regulations.gov.
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. Publicly available documents
related to this rulemaking may be
examined and copied for a fee at the
NRC’s Public Document Room (PDR),
Public File Area O1F21, One White
Flint North, 11555 Rockville Pike,
Rockville, Maryland. Selected
documents, including comments, can be
reviewed and downloaded
electronically via the NRC rulemaking
Web site at https://ruleforum.llnl.gov.
You may submit comments on the
information collections by the methods
indicated in the Paperwork Reduction
Act Statement.
Publicly available documents created
or received at the NRC after November
1, 1999, are available electronically at
the NRC’s Electronic Reading Room at
https://www.nrc.gov/NRC/ADAMS/
index.html. From this site, the public
can gain entry into the NRC’s
Agencywide Document Access and
Management System (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 1–800–397–4209,
301–415–4737 or by e-mail to
pdr@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
Marjorie Rothschild, Office of the
General Counsel, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone (301) 415–
1633, e-mail MUR@nrc.gov or Bernard
Stapleton, Office of Nuclear Security
and Incident Response, Nuclear
Regulatory Commission, Washington,
DC 20555–0001, (301) 415–2432, e-mail
BWS2@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
II. Need for Rule
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III. Purpose of Rulemaking
IV. Request for Specific Comment
V. Discussion of Proposed Amendments by
Section
VI. Criminal Penalties
VII. Agreement State Issues
VIII. Plain Language
IX. Voluntary Consensus Standards
X. Finding of No Significant Impact:
Environmental Assessment
XI. Paperwork Reduction Act Statement
XII. Regulatory Analysis
XIII. Regulatory Flexibility Analysis
XIV. Backfit Analysis
I. Background
Safeguards Information (SGI) is a
special category of sensitive unclassified
information to be protected from
unauthorized disclosure under section
147 of the Atomic Energy Act of 1954,
as amended (AEA). Although SGI is
considered to be sensitive unclassified
information, it is handled and protected
more like classified National Security
Information than like other sensitive
unclassified information (e.g., privacy
and proprietary information). Part 73,
‘‘Physical Protection of Plants and
Materials,’’ of the Commission’s
regulations in Title 10 of the Code of
Federal Regulations contains
requirements for the protection of SGI.
Commission orders issued since
September 11, 2001, have also imposed
requirements for the designation and
protection of SGI. These requirements
apply to SGI in the hands of any person,
whether or not a licensee of the
Commission, who produces, receives, or
acquires SGI. An individual’s access to
SGI requires both a valid ‘‘need to
know’’ such information and
authorization based on an appropriate
background investigation. Power
reactors, certain research and test
reactors, and spent fuel storage
installations are examples of the
categories of licensees currently within
the scope of the provisions of part 73 for
the protection of SGI. Examples of the
types of information designated as SGI
include the physical security plan for a
licensee’s facility; the design features of
such a licensee’s physical protection
system; and operational procedures for
the licensee’s security organization.
The Commission has authority under
section 147 of the AEA to designate, by
regulation or order, other types of
information as SGI. For example,
section 147.a.(2) allows the Commission
to designate as SGI a licensee’s or
applicant’s detailed security measures
(including security plans, procedures
and equipment) for the physical
protection of source material or
byproduct material in quantities
determined by the Commission to be
significant to the public health and
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safety or the common defense and
security. The Commission has, by order,
imposed SGI handling requirements on
certain categories of these other
licensees. An example is a November
25, 2003 order issued to certain
materials licensees.1
Violations of SGI handling and
protection requirements, whether those
specified in part 73 or those imposed by
order, are subject to the applicable civil
and criminal sanctions. Employees, past
or present, and all persons who have
had access to SGI have a continuing
obligation to protect SGI in order to
prevent inadvertent release and
unauthorized disclosure. Information
designated as SGI must be withheld
from public disclosure and must be
physically controlled and protected.
Protection requirements include (1)
secure storage; (2) document marking;
(3) restriction of access; (4) limited
reproduction; (5) protected
transmission; and (6) controls for
information processing on electronic
systems.
Inadequate protection of SGI,
including inadvertent release and
unauthorized disclosure, may result in
civil and/or criminal penalties. The
AEA explicitly provides in section
147.a. that ‘‘any person, whether or not
a licensee of the Commission, who
violates any regulations adopted under
this section shall be subject to the civil
monetary penalties of section 234 of this
Act.’’ Furthermore, willful violation of
any regulation or order governing SGI is
a felony subject to criminal penalties in
the form of fines or imprisonment, or
both, as prescribed in section 223 of the
AEA.
II. Need for Rule
Changes in the threat environment
have revealed the need to protect
additional types of security information
held by a broader group of licensees as
SGI. Under the current regulations,
some categories of licensees are not
explicitly included in the categories of
licensees subject to the general
performance requirements in 10 CFR
73.21(a). Similarly, the current
regulations do not specify all of the
types of information that are now
recognized to be significant to the
public health and safety or the common
1 This order was published in the Federal
Register as ‘‘All Licensees Authorized to
Manufacture or Initially Transfer Items Containing
Radioactive Material for Sale or Distribution and
Who Possess Certain Radioactive Material of
Concern and All Persons Who Obtain Safeguards
Information Described Herein; Order Issued on
November 25, 2003 Imposing Requirements for the
Protection of Certain Safeguards Information
(Effective Immediately),’’ (69 FR 3397 (January 23,
2004).
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defense and security. The unauthorized
release of this information could result
in harm to the public health and safety
and the Nation’s common defense and
security, as well as damage to the
Nation’s critical infrastructure,
including nuclear power plants and
other facilities and materials licensed
and regulated by the NRC.
Since September 11, 2001, the NRC
has issued orders that have increased
the number of licensees whose security
measures will be protected as SGI and
have added additional types of security
information considered to be SGI.
Orders have been issued to power
reactor licensees, fuel cycle facility
licensees, certain source material
licensees, and certain byproduct
material licensees. Some of the orders
expanded the types of information to be
protected by licensees who already have
an SGI protection program, such as
nuclear power reactor licensees. Other
orders were issued to licensees that
have not previously been explicitly
subject to SGI protection requirements
in the regulations, such as certain
licensees authorized to manufacture or
initially transfer items containing
radioactive material.2 Some orders
impose a new designation: Safeguards
Information—Modified Handling (SGI–
M). SGI–M pertains to certain SGI
subject to handling requirements that
are modified from what part 73 itself
currently requires. This designation for
SGI applies to certain quantities of
source, byproduct, and special nuclear
materials for which the risk of
unauthorized disclosure of information
is relatively low. In contrast, more
stringent requirements are imposed for
the protection of SGI pertaining to
licensees such as power reactors and
certain fuel cycle facilities.
Some of the requirements imposed by
orders that have increased the types of
information to be considered SGI are not
covered by the current regulations.
Although new SGI requirements could
continue to be imposed through the
issuance of orders, the regulations
would not reflect current Commission
SGI policy and/or requirements. Orders
apply only to the licensees named in the
orders, and enforcement orders do not
apply prospectively to applicants for
new licenses such as a rule would. Duke
Energy Corp. (Catawba Nuclear Station,
Units 1 and 2), CLI–04–6, 59 NRC 62
(2004) (February 18, 2004). Finally, it
has been Commission policy to codify
requirements in the regulations and not
to rely on orders indefinitely to impose
requirements that should have generic
application.
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2 See
69 FR 3397 (January 23, 2004).
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III. Purpose of Rulemaking
NRC staff review of the SGI regulatory
program indicates that changes in the
regulations are needed to address issues
such as access to SGI, types of security
information to be protected, and
handling and storage requirements.3
This rulemaking would:
Codify the SGI requirements imposed
by the orders;
Expand the scope of part 73 to
include additional categories of
licensees (e.g., source and byproduct
material licensees, research and test
reactors not previously covered, and
fuel cycle facilities not previously
covered);
Expand the types of security
information covered by the definition of
SGI in § 73.21 to include access
authorization for background screening,
detailed emergency planning scenarios
and implementing procedures,
vulnerabilities or weaknesses corrected
in a security system, and some training
and qualification information; and
Update § 73.21 to address advanced
technology, such as new types of
portable communication devices and
copiers using digital technology.
A graded approach based on the risks
and consequences of information
disclosure is being used in determining
which category of licensee or type of
information will be subject to certain
protection requirements. This graded
approach can be applied to such issues
as the type of information to be
protected, the classes of licensees
subject to the rule, and the level of
handling requirements necessary for the
various licensees. For example, the
graded approach allows certain
licensees, whose quantities and forms of
material pose a low risk from
unauthorized information disclosure, to
employ the modified-handling
procedures introduced in recent orders
for Safeguards Information designated
as SGI–M.
The requirements set forth in this
proposed rule are the minimum
restrictions the Commission believes to
be necessary in the current threat
environment to protect Safeguards
Information against inadvertent release
or unauthorized disclosure which might
compromise the health and safety of the
public or the common defense and
security. The proposed rule covers those
facilities and materials the Commission
has already determined need to be
protected against theft or sabotage. The
3 The NRC staff is in the process of revising the
guidance for designation of SGI and has issued a
draft document for comment (Nuclear Regulatory
Commission Draft Guide for the Designation of
Safeguards Information, July 2004).
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categories of information constituting
SGI relate to the types of facilities and
the quantities of special nuclear
material, source material and byproduct
material determined by the Commission
to be significant and therefore subject to
protection against unauthorized
disclosure pursuant to section 147 of the
AEA. Unauthorized release of
Safeguards Information could reduce
the deterrence value of systems and
measures used to protect nuclear
facilities and materials and allow for the
possible compromise of those facilities
and materials. Such disclosures could
also facilitate advance planning by an
adversary intent on committing acts of
theft or sabotage against the facilities
and materials within the scope of the
rule. The rule requirements satisfy the
minimum restrictions provision of
section 147.a.(3)(A) of the AEA. Further,
the Commission has determined,
pursuant to section 147.a.(3)(B) of the
AEA, that the unauthorized disclosure
of the information that is the subject of
the proposed rule could reasonably be
expected to have a significant adverse
effect on the health and safety of the
public or the common defense and
security by significantly increasing the
likelihood of theft, diversion, or
sabotage of nuclear material or a facility.
IV. Request for Specific Comment
The NRC is soliciting specific public
comment on the following issue
associated with the proposed
rulemaking action:
Differing Requirements for Access to
SGI and SGI–M—sections 73.22(b)(1)
and 73.23(b)(1) contain differing
requirements for performing background
checks and making trustworthiness and
reliability determinations for granting
personnel access to SGI or SGI–M.
Specifically, under § 73.22(b)(1)(i)(A),
an individual to be authorized access to
SGI by a nuclear power reactor
applicant or licensee must demonstrate
trustworthiness and reliability and
undergo a Federal Bureau of
Investigation criminal history check to
the extent required by § 73.57, which
includes fingerprinting. Individuals to
be authorized access to SGI by other
applicants or licensees covered by
§ 73.22 or by a source, byproduct, or
special nuclear material applicant or
licensee pursuant to § 73.23(b)(1)(i)
must demonstrate trustworthiness and
reliability through a comprehensive
background check or other means
approved by the Commission. These
different requirements are based on the
statutory authorization in section 149 of
the AEA for the NRC to require
fingerprinting of individuals to be
granted access to SGI by nuclear power
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reactor applicants or licensees. There is
not a similar statutory authorization to
require fingerprinting by other
applicants or licensees.
The NRC specifically invites comment
on whether stakeholders would perceive
difficulties in complying with these
varying requirements. If so, the
Commission would welcome
stakeholder’s suggestions, comments,
and/or proposals which would provide
a more uniform approach to background
checks and trustworthiness and
reliability determinations.
V. Discussion of Proposed Amendments
by Section
Conforming changes to 10 CFR part 2,
‘‘Rules of practice for domestic licensing
proceedings and issuance of orders,’’
would be made to the following sections
to include citation of 10 CFR 73.22 and
73.23, in addition to citation of current
§ 73.21, as applicable appropriate:
paragraph (f) of § 2.709, ‘‘Discovery
against NRC staff;’’ 4 paragraph (a)(4)(iii)
of § 2.1003, ‘‘Availability of material;’’
and paragraph (b)(6) of § 2.1010, ‘‘PreLicense application presiding officer.’’
Conforming changes are also being
proposed to 10 CFR part 30, ‘‘Rules of
general applicability to domestic
licensing of byproduct material,’’ and 10
CFR part 40, ‘‘Domestic licensing of
source material.’’ The proposed changes
would add provisions to the sections of
those parts addressing applications for
specific licenses and terms and
conditions of licenses. In part 30,
§§ 30.32, ‘‘Application for specific
licenses’’ and 30.34, ‘‘Terms and
conditions of licenses,’’ would be
amended to include citation of §§ 73.21
and 73.23. In part 40, corresponding
sections (§§ 40.41 and 40.31) would be
amended to include citation of § 73.21
and the requirements of § 73.22 or
§ 73.23, as applicable. With these
additions, it should be clear that part 30
and part 40 licensees and applicants
(subject to 10 CFR part 73), under each
part would be required to protect
categories of documents and
information in accordance with the
requirements of part 73.
Conforming changes to 10 CFR part
50, ‘‘Domestic licensing of production
and utilization facilities,’’ would add to
§ 50.34, ‘‘Contents of applications;
technical information’’ and § 50.54,
‘‘Conditions of licenses,’’ citations to
§ 73.22, ‘‘Protection of Safeguards
Information: Specific Requirements’’
4 In § 2.709(f), which replaces former § 2.744(e), a
few changes in the language and citations in former
§ 2.744(e), not relevant here, were made as part of
a separate rulemaking amending 10 CFR part 2.
‘‘Changes to Adjudicatory Process; Final Rule,’’ 69
FR 2182, 2262 (January 14, 2004).
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and § 73.23, ‘‘Protection of Safeguards
Information-Modified Handling:
Specific Requirements.’’ The purpose of
these changes would be to reflect that
specific requirements for protecting SGI
relating to such licensees and materials
would be moved from § 73.21 to
proposed § 73.22 and § 73.23, of this
chapter, as applicable.
Conforming changes are also being
proposed to 10 CFR part 52, ‘‘Early site
permits; standard design certifications;
and combined licenses for nuclear
power plants.’’ Specifically, § 52.47,
‘‘Contents of applications,’’ relating to
standard design certifications, would be
amended to add as paragraph (c) the
requirement that an applicant for a
standard design certification under part
52 shall protect SGI against
unauthorized disclosure in accordance
with the requirements of §§ 73.21 and
73.22 of this chapter, as applicable. A
similar conforming change is being
proposed for § 52.79, ‘‘Contents of
application; technical information,’’
relating to combined licenses for
nuclear power facilities.
Part 60, ‘‘Disposal of high-level
Radioactive wastes in geologic
repositories,’’ would be amended to add
in § 60.21, ‘‘Content of application,’’
new paragraph (d). That paragraph
would state that the application for a
license for a geologic repository
operations area shall protect as SGI
detailed security measures and related
information, in accordance with the
requirements of § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable. A parallel change
would be made to a new paragraph (d)
to § 60.42, ‘‘Conditions of license.’’
Part 63, ‘‘Disposal of high-level
radioactive wastes In a geologic
repository at Yucca Mountain, Nevada,’’
would be amended to add new
paragraph (d) to § 63.21, ‘‘Content of
application.’’ That section would state
that the applicant for a license to receive
and possess source, byproduct, and
special nuclear material at a geologic
repository at Yucca Mountain, Nevada
shall protect the detailed security
measures for the physical protection of
high-level radioactive waste as SGI in
accordance with §§ 73.21 and 73.22. A
corresponding change (i.e., adding new
paragraph (e)) would be made to § 63.42,
‘‘Conditions of license.’’
Conforming changes are being
proposed for 10 CFR part 70, ‘‘Domestic
licensing of special nuclear material,’’
subpart D—‘‘License applications.’’
Specifically, § 70.22, ‘‘Contents of
applications,’’ and § 70.32 ‘‘Conditions
of licenses,’’ would be modified to add
citation of proposed § 73.23. These
modifications are being proposed to be
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consistent with the addition of proposed
§ 73.23 containing specific requirements
for Safeguards Information—Modified
Handling related to certain quantities of
source and byproduct material and
special nuclear material of moderate or
low strategic significance, except for
those materials covered under § 73.22.
Part 71, ‘‘Packaging and
transportation of radioactive material,’’
would be amended to add new § 71.11,
‘‘Protection of Safeguards Information’’
because licensees, certificate holders, or
applicants for a Certificate of
Compliance for transport of radioactive
material would be required to protect
Safeguards Information in accordance
with the applicable amended
requirements in part 73. The proposed
revision does not address the protection
of design-related information with
respect to transportation packages.
Part 72, ‘‘Licensing requirements of
the independent storage of spent
nuclear fuel, high-level radioactive
waste, and reactor-related greater than
Class C waste,’’ would also be amended.
A new paragraph (f) would be added to
§ 72.22, ‘‘Contents of application;
General and financial information,’’ to
require that each applicant for a license
under part 72 would be required to
protect SGI against unauthorized
disclosure in accordance with § 73.21
and the requirements of § 73.22 or
§ 73.23, of this chapter, as applicable. In
§ 72.44, ‘‘License conditions,’’
paragraph (h) would include a similar
requirement for each licensee subject to
part 73. Section 72.212 would be
changed to designate paragraph (b)(5)(v)
as paragraph (b)(5)(vi) and a new
paragraph (b)(5)(v) would be added to
require that each general licensee that
receives, transfers, and possesses power
reactor spent fuel, power reactor-related
Greater than Class C (GTCC) waste, and
other radioactive materials associated
with spent fuel storage shall protect
Safeguards Information against
unauthorized disclosure in accordance
with the requirements of § 73.21 and the
requirements of § 73.22 or § 73.23, of
this chapter, as applicable. A new
paragraph (n) would be added to
§ 72.236, ‘‘Specific requirements for
spent fuel storage cask approval and
fabrication,’’ to note that Safeguards
Information shall be protected against
unauthorized disclosure in accordance
with the requirements of § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable.
Section 73.1 Purpose and Scope
Paragraph (b)(7) of this section would
be amended to include a reference to
‘‘Safeguards Information-Modified
Handling’’ (SGI–M), the designation for
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marking of documents containing
Safeguards Information (SGI) to which
the Commission has determined
modified protection requirements apply.
Orders to certain materials licensees
contain this new SGI–M designation
and the handling requirements for such
information.
Section 73.2 Definitions
This section would be amended to
add definitions of the terms Individual
Authorized Access to Safeguards
Information and Individual Authorized
Access to Safeguards InformationModified Handling; Trustworthiness
and Reliability, and Safeguards
Information-Modified Handling
Requirements. In addition, the
definition of the term Safeguards
Information would be modified.
The new terms Individual Authorized
Access to Safeguards Information and
Individual Authorized Access to
Safeguards Information-Modified
Handling, would be added to
distinguish such individuals from an
‘‘authorized individual,’’ which is
defined now to apply only to the control
of and access to special nuclear
material, without reference to handling
of information or documents.
The new term, Safeguards
Information-Modified Handling, would
be added to reflect the new designation
for marking of SGI subject to this
regulation. This marking has been
previously established through
Commission orders.
The new term, Trustworthiness and
Reliability, would be added to reflect
Commission expectations regarding
positive character attributes for access to
SGI and SGI–M handling in addition to
an individual’s ‘‘need to know’’ such
information. This expectation is
embodied elsewhere in part 73 (§ 73.56,
‘‘Personnel access authorization
requirements for nuclear power
plants.’’) and in 10 CFR 26.10, ‘‘General
performance objectives,’’ for fitness-forduty. Specifically, § 73.56(b) requires, as
a performance objective of a licensee’s
access authorization program, ‘‘high
assurance’’ that individuals granted
unescorted access to a nuclear power
plant’s protected and vital areas are
trustworthy and reliable. Similarly,
under § 26.10(a), a licensee’s fitness-forduty program must provide reasonable
assurance that covered personnel will
perform their tasks in a ‘‘trustworthy
and reliable manner.’’
The definition of ‘‘Safeguards
Information’’ would be changed to
reflect that certain categories of
information relating to source and
byproduct material are subject to
protection as SGI against unauthorized
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7199
disclosure pursuant to section 147 of the
AEA. In addition, this definition would
embody the Commission’s authority
under section 147 of the AEA to
determine, by order or regulation, that
the unauthorized disclosure of other
information could reasonably be
expected to have an adverse effect on
the health and safety of the public or the
common defense and security by
significantly increasing the likelihood of
theft, diversion, or sabotage of materials
and facilities. The Commission may
from time to time exercise its authority
under section 147.a.5 of the AEA to
define additional information as SGI.
Thus, the public and other stakeholders
would, through orders or new
regulations, be given notice of any
additional definitions of SGI.
The proposed definition of SGI would
also delete the words ‘‘licensee’s or
applicant’s’’ [information]. This change
is being proposed to reflect in the
regulations the Commission’s authority
under section 147 of the AEA to
determine that other information
involving the materials described in that
provision shall be protected as SGI. This
authority can be exercised if the
unauthorized disclosure of that
information could reasonably be
expected to have an adverse effect on
the health and safety of the public or the
common defense and security by
significantly increasing the likelihood of
theft, diversion, or sabotage of materials
and facilities regulated by the
Commission. The proposed change is
also based on the Commission’s very
broad authority under section 161.b. of
the AEA to regulate the use and
possession of source, byproduct, and
special nuclear material in order to
promote the common defense and
security or to protect health and
minimize danger to life or property.
Section 73.21 Protection of Safeguards
Information: Performance Requirements
This section would be revised as
follows:
Section 73.21(a) General Performance
Requirements
The language in paragraph (a) would
be simplified and revised to state at the
outset that any person, including a
licensee or an applicant, who produces,
receives or acquires SGI shall ensure
that it is protected against unauthorized
disclosure. Although this is not a new
requirement under § 73.21(a), the
current language and format of that
paragraph does not emphasize this as an
5 In the exercise of this authority, the Commission
makes certain determinations and applies the
minimum restrictions necessary to protect SGI, in
compliance with section 147 of the AEA.
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obligation that extends to any person
who produces, receives, or acquires SGI.
Revised paragraphs § 73.21(a)(1)(i)
and (a)(1)(ii) would embody the general
performance requirement in paragraph
(a) of current § 73.21 that licensees,
applicants, and persons subject to that
section must establish, implement, and
maintain an information protection
system that includes specified
measures. However, the proposed rule
presents separate requirements for the
different categories of licensees.
Proposed § 73.22 contains the specific
requirements for Safeguards Information
related to power reactors, licensees
authorized to possess a formula quantity
of strategic special nuclear material,
transportation of or delivery to a carrier
for transportation of a formula quantity
of strategic special nuclear material or
more than 100 grams of irradiated
reactor fuel, and fuel cycle facilities
required to implement security
measures. Measures for protecting SGI
relating to certain quantities of source
and byproduct material, and special
nuclear material of moderate or low
strategic significance are specified in
proposed § 73.23.6
Although the measures for the
protection of SGI are applicable if the
information is produced, received, or
acquired, if licensees do not have such
information then the associated
requirements would not apply. For
example, research and test reactors are
not required to implement the power
reactor Design Basis Threat (DBT),7 and
therefore, in all likelihood would not
possess DBT-related information.
However, should a research and test
reactor receive or acquire such
information, it would be required to
protect the information in accordance
with applicable measures.
Including the references to source,
byproduct, and special nuclear material
in these new paragraphs would reflect
the full scope of section 147 of the AEA.
That section authorizes the Commission
to protect against the unauthorized
disclosure of SGI which specifically
identifies a licensee’s or applicant’s
detailed procedures or security
measures relating to special nuclear
material, byproduct material, and source
material, in quantities determined by
the Commission through order or
6 The
quantities are those determined by the
Commission through order or regulation to be
significant to the public health and safety or the
common defense and security.
7 The DBTs, as described in 10 CFR 73.1, provide
specific adversary characteristics which power
reactor and Category I fuel cycle facilities need to
protect against. The DBTs form the basis for sitespecific defensive strategies as set forth in a site’s
physical security plan and contingency plan.
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regulation to be significant. This change
would lessen the need for the
Commission to issue orders to licensees
for the protection of SGI relating to
categories of licensees, information, or
materials not currently within the scope
of part 73.
Section 73.21(a)(1)(i) and (a)(1)(ii)
would also add the word ‘‘implement’’
to the requirement in current § 73.21(a)
that licensees and persons subject to
this section must establish and maintain
an information protection system to
protect against the unauthorized
disclosure of SGI.
Section 73.21(b) Commission
Authority
This is a new paragraph that
recognizes the Commission’s broad
authority and flexibility under section
147 of the AEA to designate information
as SGI or SGI–M and to impose levels
of handling requirements on any person
who produces, receives, or acquires SGI.
In exercising this authority, the
Commission is required to make a
finding that the unauthorized disclosure
of such information could reasonably be
expected to have a significant adverse
effect on the health and safety of the
public or the common defense and
security by significantly increasing the
likelihood of the theft, diversion, or
sabotage of a facility or source,
byproduct, and special nuclear material.
In addition, the Commission is to
impose the minimum restrictions
necessary to protect the health and
safety of the public or the common
defense and security.
The remaining paragraphs of § 73.21
will be renumbered into new §§ 73.22
and 73.23, and modified as noted.
Section 73.22 Protection of Safeguards
Information: Specific Requirements
New § 73.22 would be added,
containing specific requirements for
Safeguards Information related to power
reactors, licensees authorized to possess
a formula quantity of strategic special
nuclear material, transportation of or
delivery to a carrier for transportation of
a formula quantity of strategic special
nuclear material or more than 100 grams
of irradiated reactor fuel, and fuel cycle
facilities required to implement security
measures.
Section 73.22(a) Information To Be
Protected
Current § 73.21(b) ‘‘Information To Be
Protected,’’ would be renumbered as
§ 73.22(a) and be revised to add
specificity to the types of information
and documents that must be protected
as SGI. Such information and
documents would include the elements
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and characteristics of the DBT in a level
of detail greater than that specified in
§ 73.1, as well as security-related
requirements to be protected against
unauthorized disclosure such as
protective measures, interim
compensatory measures, and additional
security measures. These changes are
necessary to codify in the regulations
the recent practices of the Commission
as reflected in orders and threat
advisories issued since September 11,
2001.
Section 73.21(a)(1), ‘‘Physical
Protection at Fixed Sites,’’ would be
changed to be consistent with the
language in section 147.a.(1), (2), and (3)
of the AEA to include information
relating to all of the materials there
specified. As revised, paragraph (a)(1) of
§ 73.21 would not be limited to
information concerning the protection
of power reactors authorized to operate
and facilities that possess formula
quantities of strategic special nuclear
material, as is current § 73.21(b)(1).
Section (a)(1)(i) would be revised to
delete the word ‘‘nuclear’’ to be
consistent with the terminology in
section 147 of the AEA. In addition, the
words ‘‘All portions of’’ would be added
at the beginning of this category to make
clear the broader scope of this category
of information intended to be protected
as SGI.
Sections 73.22(a)(1)(iii) and
73.22(a)(1)(v) embody changes to
current § 73.21(b)(1)(iii) and current
§ 73.21(b)(1)(v). The new § 73.22(a)(ii)
would delete the words ‘‘Details of’’ at
the beginning of these categories of
information to make clear the broader
scope of the information intended to be
protected as SGI.
Section 73.22(a)(1)(vi) would be
current § 73.21(b)(1)(vi) and would be
amended to include the phrase
‘‘passwords integral to the physical
security system’’ because such
passwords constitute the type of
information that should be protected as
SGI.
Section 73.22(a)(1)(viii), current
§ 73.21(b)(1)(viii), and § 73.22(a)(1)(ix),
current § 73.21(b)(1)(ix), would be
revised to add at the beginning of each
category the words ‘‘All portions of.’’
This change would make it clear that
the referenced plans in their entirety
and subparts are intended to be
designated as SGI. In addition, current
§ 73.21(a)(1)(ix) would be changed to
recognize the importance of the
licensee’s overall facility guard training
and qualification plan as a ‘‘composite’’
plan.
New § 73.22(a)(1)(x) would reflect a
combination of current paragraphs
§ 73.21(b)(1)(x), § 73.21(b)(1)(xi), and
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§ 73.21(b)(1)(xii). As revised, this
paragraph would specify the
enumerated aspects of response forces.
Proposed § 73.22(a)(1)(xi) would be
added to cover information concerning
the size, tactics and capabilities
required to defend against the DBT or
information that would disclose
elements and characteristics of the DBT
in a greater level of detail than that
specified in § 73.1.
Proposed § 73.22(a)(1)(xii) would be
added to specify for protection as SGI
engineering and safety analyses,
emergency planning procedures or
scenarios, and other similar information
relating to the physical protection of a
facility or materials if the unauthorized
disclosure of such information could
reasonably be expected to have a
significant adverse effect on the health
and safety of the public or the common
defense and security by significantly
increasing the likelihood of theft,
diversion, or sabotage of such material
or such facility.
Proposed § 73.22(a)(1)(xiii) is the
current § 73.21(b)(1)(xiii).
Section 73.22(a)(2) Physical Protection
in Transit
The introductory paragraph in current
§ 73.21(b)(2) and § 73.21(b)(2)(i),
§ 73.21(b)(2)(iii) and § 73.21(b)(2)(iv) are
renumbered as new introductory
paragraph § 73.22(a)(2), § 73.22(a)(2)(i),
§ 73.22(a)(2)(iii) and § 73.22(a)(2)(iv).
The introductory paragraph would be
changed to reflect the applicability of
§ 73.22 to the transportation of or
delivery to a carrier for transportation of
a formula quantity of strategic special
nuclear material or more than 100 grams
of irradiated reactor fuel.
Section 73.22(a)(2)(i) would be
revised to include the words ‘‘All
portions of’’ to make it clear that these
plans in their entirety and subparts are
intended to be designated as SGI.
Current § 73.21(b)(2)(ii) would be renumbered as § 73.22(a)(2)(ii) but would
otherwise be unchanged.
Current § 73.21(b)(2)(iii) would be
renumbered as § 73.22(a)(2)(iii) and
changed to delete the words ‘‘Details of’’
to clarify that the features, devices, and
systems in their entirety are a category
of SGI to be protected as such.
Current § 73.21(b)(2)(iv) would be
renumbered as § 73.22(a)(2)(iv) and
would be otherwise unchanged.
Current § 73.21(b)(2)(v) would be
renumbered as § 73.22(a)(2)(v) and
would delete the words ‘‘radiotelephone’’ so as to encompass the more
modern means of communications. This
section would also delete the words
‘‘Details regarding’’ to clarify that all
aspects of communications during
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transport are included in this category
of information.
Current § 73.21(b)(2)(vi) would be renumbered as § 73.22(a)(2)(vi) and would
add the word ‘‘security’’ before the word
‘‘emergencies’.
Section 73.22(a)(2)(vii) is new and its
purpose would be to encompass
information concerning the tactics and
capabilities required to defend against
attempted radiological sabotage or theft
and diversion of formula quantities of
special nuclear material or related
information.
Section 73.22(a)(2)(viii) would be
added to include as information to be
protected as SGI, engineering or safety
analyses and emergency planning
procedures or scenarios relating to the
protection of a facility or material if the
unauthorized disclosure of that
information could reasonably be
expected to have a significant adverse
effect on the health and safety of the
public or the common defense and
security by significantly increasing the
likelihood of theft, diversion, or
sabotage of such facility or material.
Section 73.22(a)(3) is based on current
§ 73.21(b)(3), ‘‘Inspections, audits and
evaluations,’’ and would be broadened
to cover specific requirements for
Safeguards Information related to power
reactors, licensees authorized to possess
a formula quantity of strategic special
nuclear material, transportation of or
delivery to a carrier for transportation of
a formula quantity of strategic special
nuclear material or more than 100 grams
of irradiated reactor fuel, and fuel cycle
facilities required to implement security
measures. Detailed information
regarding defects, weaknesses or
vulnerabilities is generally not released
because identical circumstances may
apply to a licensee or applicant
employing similar security measures. In
addition, the types of inspections and
reports within the scope of the section
would not be limited to safeguards
inspections and reports. This language
would recognize that documents
concerning other types of inspections
could contain SGI.
Current § 73.21(b)(4),
Correspondence, would be renumbered
§ 73.22(a)(4) and would be otherwise
unchanged.
Section 73.22(a)(5) would be new and
would reflect the authority of the
Commission under Section 147.a. of the
AEA to designate as SGI such other
information as the Commission may
determine by order or regulation could
reasonably be expected to have a
significant adverse effect on the health
and safety of the public or the common
defense and security by significantly
increasing the likelihood of theft,
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7201
diversion, or sabotage of material or a
facility (within the scope of § 73.22).
The Commission, may from time to
time, exercise its authority under
section 147.a.8 of the AEA to define
additional information as SGI and the
public and other stakeholders would
have notice as to what these additional
definitions of SGI are, through orders or
new regulations, that would specifically
define SGI.
Section 73.22(b) is based on current
§ 73.21(c) through (i), which address
access to SGI and specific requirements
for protecting it from unauthorized
disclosure. The Commission is
proposing to re-structure part 73 to
accommodate the separate handling
requirements for SGI–M, imposed by
order or regulation on certain
byproduct, source, and special nuclear
materials licensees. Proposed § 73.22
would contain the specific requirements
for Safeguards Information related to
power reactors, licensees authorized to
possess a formula quantity of strategic
special nuclear material, transportation
of or delivery to a carrier for
transportation of a formula quantity of
strategic special nuclear material or
more than 100 grams of irradiated
reactor fuel, and fuel cycle facilities
required to implement security
measures. Corresponding specific
requirements for SGI–M relating to
certain quantities of source and
byproduct material, and special nuclear
material of low or moderate strategic
significance would be set forth in
proposed § 73.23.
Section 73.22(b)(1) would state, as
does current § 73.21(c)(1), the
requirement that no person may have
access to SGI unless the person has an
established ‘‘need to know’’ the
information and fits within described
occupational categories (proposed
§ 73.22(b)(1)(i) through (vii)). The new
§ 73.22(b)(1)(i)(A) and (B) add the
requirement that individuals authorized
access to SGI by a nuclear power reactor
licensee and non-power reactor
licensees and applicants, demonstrate
‘‘trustworthiness and reliability’’ prior
to such access. The Commission has
also updated the descriptions in
§ 73.21(c)(1)(ii) through (vi) of some of
the occupational groups and added a
new group, as described below.
The description of the occupational
category in § 73.22(b)(1)(i),
(Commission, U.S. government, or
licensee or applicant employee, agent,
or contractor) would change the
language in current § 73.21(c)(1)(i) from
8 In the exercise of this authority, the Commission
would make certain determinations and apply the
minimum restrictions necessary to protect SGI.
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‘‘U.S. Government’’ to ‘‘Executive
Branch’’ of the U.S. Government. This
change is necessary because for
purposes of access to SGI, members of
Congress are covered separately in the
occupational category specified in
proposed § 73.22(b)(1)(i).
Additionally, new § 73.22(b)(1)(i)(A)
would require that an individual
authorized access to SGI by a nuclear
power reactor facility applicant or
licensee must undergo an FBI criminal
history check and must demonstrate
trustworthiness and reliability. Another
new paragraph, § 73.22(b)(1)(i)(B) would
be added, mandating that individuals to
be authorized access to SGI by a nonpower reactor facility applicant or
licensee must also demonstrate
trustworthiness and reliability.
However, this demonstration would be
based on a comprehensive background
check or other means approved by the
Commission in lieu of the FBI criminal
history check.
Section 73.22(b)(1)(ii) is based on
current § 73.21(c)(1)(ii) but would delete
the phrase ‘‘a duly authorized
committee of’’ [the Congress]. Under the
Commission’s current regulations in
§ 73.21(c)(1)(ii), a member of a ‘‘duly
authorized committee of the Congress’’
with a ‘‘need to know’’ SGI is given
access to such information. This section
of the regulations does not set forth the
meaning of a ‘‘duly authorized
committee.’’ If narrowly interpreted,
this occupational category might only
apply to members of Congress who
serve on NRC oversight committees. The
deletion in the proposed rule of the
phrase ‘‘a duly authorized committee’’
[of the Congress] would mean that the
authorization would extend to all
members of Congress (with a ‘‘need to
know’’ SGI). This change would be
made because many members of
Congress are not on NRC oversight
committees, yet they may need access to
SGI because of the presence of nuclear
facilities or materials in their states or
districts. As amended, the language
would not alter the Commission’s
current practices in responding to
requests from members of Congress for
access to SGI.
In addition, the authorization in
current § 73.21(c)(1)(ii) does not extend
to congressional staff. The Commission
is not proposing to extend the
authorization to congressional staff. On
a case-by-case basis, with explicit
authorization from the appropriate NRC
office, the NRC staff could share SGI
with a Congressional staff member with
a ‘‘need to know’’ SGI and who
otherwise meets the requirements for
access to such information.
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Section 73.22(b)(1)(iii) renumbers
current § 73.21(c)(1)(iii) and would be
otherwise unchanged.
Section 73.22(b)(1)(iv) is based on
current § 73.21(c)(1)(iv) but the word
‘‘representative’’ is being made plural to
account for the fact that more than one
representative may be designated under
this occupational category. The plural
form is consistent with similar language
in the descriptions of occupational
categories in current § 73.21(c)(1).
Current § 73.21(c)(1)(v) would be renumbered as paragraph (b)(1)(v) and the
description of this occupational
category would be changed to
‘‘employees’’ (which would include the
current term ‘‘member’’) of a state or
local law enforcement authority who are
responsible for responding to requests
for assistance during safeguards or
securities emergencies.
Section 73.22(b)(1)(vi) includes as an
occupational category, State Radiation
Control Program Directors and
Homeland Security Advisors or their
designated representatives. This
category corresponds to
§ 73.23(b)(1)(iii).
Section 73.22(b)(1)(vii) is current
§ 73.21(c)(1)(vi) and substitutes the
citation of 10 CFR § 2.709(f) for
§ 2.744(e) because the latter citation is
outdated.
Section 73.22(b)(2) contains a
statement contained in a recent
Commission order 9 that finds that
individuals in the occupational
categories described in § 73.22(b)(1)(ii)
through § 73.22(b)(1)(vii) 10 are
considered to be trustworthy and
reliable by virtue of their occupational
status. For non-governmental
individuals described in § 73.22(b)(1)(i),
a determination of trustworthiness and
reliability is required prior to granting
access to SGI. Discretion must be
exercised in granting access to these
individuals. If there is any indication
that the recipient would be unwilling or
unable to provide proper protection for
the SGI, they are not authorized to
receive SGI–M.
9 e.g., ‘‘All Licensees Authorized to Manufacture
or Initially Transfer Items Containing Radioactive
Material for Sale or Distribution and Possess Certain
Radioactive Material of Concern and All Other
Persons Who Obtain Safeguards Information; Order
Imposing Requirements for the Protection of Certain
Safeguards Information (Effective Immediately) (69
FR 3397, 3399; January 23, 2004).
10 Individuals (or in some cases, their designated
representatives) in the following occupational
groups are included: State Governors,
representatives of the IAEA, employees of state or
local law enforcement, State Radiation Control
Program Directors and State Homeland Security
Advisors, and individuals to whom disclosure is
ordered pursuant to 10 CFR 2.709(f). (69 FR 3399;
January 23, 2004).
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Section 73.22(c) Protection While in
Use or Storage
Section 73.22(c)(1) contains the
identical requirement in current
§ 73.21(d), that while in use, matter
containing SGI shall be under the
control of an individual authorized
access to SGI.
Under certain conditions the general
control exercised over security zones or
areas would be considered to meet this
requirement. Some examples of these
areas would be: Alarm stations, guard
posts and guard ready rooms;
engineering or drafting areas if visitors
are escorted and information is not
clearly visible; plant maintenance areas
if access is restricted and information is
not clearly visible; administrative
offices (e.g., central records or
purchasing) if visitors are escorted and
information is not clearly visible. The
primary consideration is limiting access
to those who have a ‘‘need to know’’
and are authorized to have access.
Section 73.22(c)(2) would be revised to
limit access to lock combinations.
Section 73.22(d) Preparation and
Marking of Documents or Other Matter
Section 73.22(d) would revise current
§ 73.21(e) to add in the title ‘‘or other
matter,’’ to be consistent with the
language in the substantive paragraphs
that follow. In addition, a new provision
would be added to require certification
that a document or other matter
contains SGI and the certification must
set forth the name and title of the
certifying official and the certification
date. Also, portion marking would be
required for correspondence to NRC.
Such marking would have to be
sufficient to allow the recipient to
identify and distinguish those sections
of the document or other matter
containing the protected information
from the information that is otherwise
unprotected.
Section 73.22(e) Reproduction of
Matter Containing Safeguards
Information
Section 73.21(f) is renumbered to
become § 73.22(e) and the text is revised
to include direction for the use of digital
copiers and to delete language regarding
destruction of SGI, which has been
relocated to § 73.22(i).
Section 73.22(f) External Transmission
of Documents and Material
Section 73.22(f)(1) would amend
§ 73.21(g)(1) to set forth detailed
requirements for packaging SGI when
transmitted outside an authorized place
of use or storage. These prescriptive
requirements are consistent with the
current practices of nuclear power
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reactor licensees and the Commission
now deems it necessary to require them
to adequately protect SGI or SGI-M
when such information is transmitted
externally.
Section 73.22(f)(2) would amend
§ 73.21(g)(2) to conform to other changes
made by this rulemaking.
Section 73.22(f)(3) would add
language to current § 73.21(g)(3) to
permit transmission of SGI by protected
telecommunication circuits (including
facsimile) or encryption (Federal
Information Processing Standard). Both
of these means of transmission must be
approved by the appropriate NRC office.
Section 73.22(g) Processing of SGI on
Electronic Systems
This section updates the title and
expands the content of current
§ 73.21(h), ‘‘Use of automatic data
processing (ADP) systems,’’ to refer to
the processing of SGI on electronic
systems and to add specific
requirements applicable to the computer
processing of SGI.
Section 73.22(h) Removal From
Safeguards Information Category
Section 73.22(h) revises current
§ 73.21(i) to add further restrictions on
decontrolling SGI. One proposed change
concerns the degree of care that must be
exercised in removing information from
the SGI category. The other new
requirement would specify that the
authority to determine that a document
may be decontrolled shall be exercised
only by the NRC or with NRC approval,
or in consultation with the individual or
organization that made the original
determination, if possible. Removal
from the SGI-M category is addressed in
§ 73.23(h).
Section 73.22(i) Destruction of Matter
Containing SGI
Section 73.22(i) contains revised
language from current § 73.21(f) to be
consistent with the policies set forth in
the orders regarding the destruction of
documents.
New Section 73.23 Protection of
Safeguards Information-Modified
Handling: Specific Requirements.
This is a new section which would set
forth the specific requirements for
Safeguards Information—Modified
Handling related to certain quantities of
source and byproduct material and
special nuclear material of moderate or
low strategic significance, except for
those materials covered under section
73.22. The term ‘‘SGI–M’’ would be
used as the distinguishing marking for
SGI relating to certain source,
byproduct, and special nuclear material
licensees. Section 73.23 is based on the
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Commission’s orders and threat
advisories issued to certain byproduct
materials licensees.
Section 73.23(a) Information To Be
Protected
Section 73.23(a) sets forth the
information to be protected in
accordance with the handling
requirements specified in § 73.23(c)
through (i). In general terms,
information deemed SGI–M is
information the disclosure of which
could reasonably be expected to have a
significant adverse effect on the health
and safety of the public or the common
defense and security by significantly
increasing the likelihood of theft,
diversion, or sabotage of materials or
facilities subject to NRC jurisdiction.
SGI–M is the designation and marking
for SGI which is subject to these
requirements. The overall measure for
consideration of SGI–M is the
usefulness of the information (security
or otherwise) to an adversary in
planning or attempting a malevolent act;
the more specific the information, the
more likely that it will be useful to an
adversary.
Section 73.23(a) states that the
specific types of information and
documents to be protected as SGI–M
include security-related requirements
that must be protected from
unauthorized disclosure such as
protective measures, interim
compensatory measures, and additional
safety features. Sections 73.23(a)(1)
through (a)(4) enumerate and describe
the specific categories of SGI–M to be
protected. These categories of
information are based on those
proposed in § 73.22(a)(1) through (a)(5),
as applicable, which in turn update the
types of information specified in current
§ 73.21(b)(1) through (b)(4). In reference
to proposed § 73.23(a)(3)(i), regarding
portions of certain inspection reports,
evaluations, audits, or investigations,
detailed information regarding defects,
weaknesses or vulnerabilities is
generally not released because identical
circumstances may apply to licensees or
applicants employing similar security
measures. Section 73.23(a)(4) references
correspondence as it pertains to this
section.
Section 73.23(a)(5) would be new and
would reflect the authority of the
Commission under section 147a of the
AEA to designate as SGI such other
information as the Commission may
determine by order or regulation could
reasonably be expected to have a
significant adverse effect on the health
and safety of the public or the common
defense and security by significantly
increasing the likelihood of theft,
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diversion, or sabotage of material or a
facility (within the scope of § 73.22).
The Commission, may from time to
time, exercise its authority under
section 147.a.11 of the AEA to define
additional information as SGI and the
public and other stakeholders would
have notice as to what these additional
definitions of SGI are, through orders or
new regulations, that would specifically
define SGI.
Section 73.23(b)(1) addresses
conditions for access to SGI–M.
Authorization for access to SGI–M by
licensee employees, agents, or
contractors must be based on both an
appropriate ‘‘need to know’’
determination by the licensee, as well as
a determination concerning the
trustworthiness and reliability of
individuals having access to the
information. Employees of an
organization associated with the
licensee’s company, for example, a
parent company, may be considered as
employees of the licensee for access
purposes. A recipient of SGI–M should
be made aware that the information is
SGI–M and those having access to it are
subject to the requirements for its
protection as well as civil and criminal
sanctions for mishandling the
information.
Section 73.23(b)(1)(ii) through (vi)
describes occupational groups who are
deemed to be trustworthy and reliable
by virtue of their employment status.
For non-governmental individuals in
§ 73.23(b)(1)(i) and (vii), a determination
of trustworthiness and reliability is
required. Discretion must be exercised
in granting access to these individuals.
If there is any indication that the
recipient would be unwilling or unable
to provide proper protection of the SGI–
M, they are not authorized to receive
SGI–M.
Section 73.23(b)(1)(ii) is identical to
the current § 73.21(c)(1)(ii), except the
phrase ‘‘a duly authorized committee
of’’ [the Congress] would be deleted.
Under the Commission’s current
regulations in § 73.21(c)(1)(ii), a member
of a ‘‘duly authorized committee of the
Congress’’ with a ‘‘need to know’’ SGI
is given access to such information. This
section of the regulations does not set
forth the meaning of a ‘‘duly authorized
committee.’’ The deletion in the
proposed rule of the phrase ‘‘a duly
authorized committee’’ [of the Congress]
would mean that the authorization
would extend to all members of
Congress (with a ‘‘need to know’’ SGI–
11 In the exercise of this authority, the
Commission would make certain determinations
and apply the minimum restrictions necessary to
protect SGI.
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M). This change would be made because
many members of Congress are not on
NRC oversight committees, yet may
need access to SGI–M because nuclear
facilities or materials are located in their
states or districts. As amended, the
language would not alter the
Commission’s current practices in
responding to requests from members of
Congress for access to SGI.
In addition, the authorization in
current § 73.21(c)(1)(ii) does not extend
to Congressional staff. The Commission
is not proposing to extend the
authorization to Congressional staff. On
a case-by-case basis, with explicit
authorization from the appropriate NRC
office, the NRC staff could share SGI–M
with a Congressional staff member with
a ‘‘need to know’’ SGI and who
otherwise meets the requirements for
access to such information.
Section 73.23(b)(1)(iii) corresponds to
§ 73.22(b)(1)(iii), which includes the
Governor of a state or designated
representatives as an occupational
category presumed to be trustworthy
and reliable for access to SGI.
Section 73.23(b)(1)(iv) is based on
§ 73.21(c)(1)(iv) and the only change is
to make ‘‘representative’’ plural because
that would be consistent with language
for other occupational categories in
which the plural form is used.
Section 73.23(b)(1)(v) corresponds to
proposed § 73.22(b)(1)(v), in which the
description of this occupational
category would be changed to
‘‘employees’’ (which would include the
current term ‘‘member’’) of a state or
local law enforcement authority who are
responsible for responding to requests
for assistance during safeguards or
securities emergencies.
Section 73.23(b)(1)(vi) is the same
occupational category of individuals in
§ 73.22(b)(1)(vi). Because homeland
security advisors is the correct title of
the individuals to be included in this
occupational category, that title is
contained in proposed rule text.
Section 73.23(b)(1)(vii) corresponds to
proposed § 73.22(c)(1)(vi), which is
based on current § 73.21(c)(1)(vi). As
proposed, this paragraph substitutes the
citation of 10 CFR 2.709(f) for § 2.744(e)
because the latter citation is outdated.
The subject of § 73.23(c) is protection
of SGI–M while in use or storage. While
in use, SGI–M shall be under the control
of an individual authorized access to
Safeguards Information Modified
Handling. This requirement is satisfied
if the SGI–M is attended by an
authorized individual in certain
locations even though the information is
in fact not constantly being used.
Examples of such locations include:
Engineering or drafting areas, plant
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maintenance areas, or administrative
offices (e.g., central records or
purchasing) if visitors are escorted and
information is not clearly visible in
these areas. Under certain conditions,
the general control exercised over
occupied security zones or areas would
be considered to meet this requirement.
SGI–M, therefore, within alarm stations
or within continuously manned guard
posts or ready rooms need not be locked
in file drawers or storage containers.
The primary consideration is limiting
access to those who have a ‘‘need to
know’’ and are otherwise authorized to
have access.
Section 73.23(d) sets forth
requirements for the preparation and
marking of documents designated as
SGI–M. Although the NRC defines what
specific byproduct material information
constitutes SGI–M, originators of
documents are responsible for
designating those documents that
contain such information. All
documents containing SGI–M in use or
storage shall be marked in accordance
with the requirements of § 73.23(d). As
stated in current § 73.21(a) and by
order,12 since information protection
procedures employed by State and local
police forces are deemed to meet NRC
requirements, documents in the
possession of these agencies need not be
marked as set forth in this paragraph.
Section 73.23(e) contains
requirements governing the
reproduction of matter containing SGI–
M. Newer digital copiers which scan
and retain images of documents
represent a security concern. If the
copier is retaining SGI–M information
in memory, the copier cannot be
connected to a network. It should be
placed in a location that is cleared and
controlled for the authorized processing
of SGI–M information. Different copiers
have different capabilities, including
some which come with features that
allow the memory to be erased. Each
copier would have to be examined from
a physical security perspective.
Section 73.23(f) concerns the external
transmission of documents and
material. Paragraph (f)(1) addresses the
transmittal of Safeguards Information
outside an authorized place of use and
storage, requiring two sealed envelopes
or wrappers and marking of the
envelopes or wrappers. Within a
facility, SGI–M may be transmitted
using a single opaque envelope. It may
also be transmitted within a facility
without single or double wrapping,
provided adequate measures are taken
12 See, for example, the Order cited earlier as
published in the Federal Register on January 23,
2004 (69 FR 3398).
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to protect the material against
unauthorized disclosure. Individuals
transporting SGI–M should retain the
documents in their personal possession
at all times or ensure that the
information is appropriately wrapped
and also secured to preclude
compromise by an unauthorized
individual. SGI–M may be transported
by any commercial delivery company
that provides nationwide overnight
service with computer tracking features,
U.S. first class, registered, express, or
certified mail, or by any individual
authorized access pursuant to the
requirements in § 73.23(b).
Section 73.23(g) describes the
requirements for processing SGI–M on
electronic systems. The basic objective
of the restrictions is to prevent access
and retrieval of stored SGI–M by
unauthorized individuals, particularly
from remote terminals. Specific files
containing SGI–M will be password
protected to preclude access by an
unauthorized individual.
Removal from the SGI–M category is
addressed in § 73.23(h), which contains
requirements which are identical to
those in § 73.22(h) for the removal from
the SGI category. Thus, these
requirements would specify when
information is to be removed from the
SGI–M category, the degree of care to be
exercised in decontrolling a document,
and the authority to determine that a
document may be decontrolled.
Section 73.23(i) contains detailed
requirements for destruction of matter
containing SGI–M. These requirements
cover methods to destroy documents
containing SGI–M and set forth
characteristics of a document which
would be considered completely
destroyed.
Section 73.57 contains requirements
for criminal history checks of
individuals granted unescorted access to
a nuclear power facility or access to
Safeguards Information by power
reactor licensees.
Section 73.57(b)(2)(i) has been revised
to include reference to § 73.22.
The language in § 73.57(b)(2)(ii),
containing an exception to the
fingerprinting requirement for the
occupational categories of members of
Congress and Governors of States,
would be revised to be consistent with
the proposed language in
§ 73.22(b)(1)(ii) and (iii) describing these
same occupational categories.
Section 76.113 Formula Quantities of
Strategic Special Nuclear Material—
Category 1
The language of paragraph (c) would
be changed to include a citation to new
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§ 73.22, Protection of Safeguards
Information: Specific Requirements.
Section 76.115 Special Nuclear
Material of Moderate Strategic
Significance—Category II
The language of this section would be
changed to add a new paragraph (d) to
state that the requirements for the
protection of Safeguards Information
pertaining to special nuclear material of
moderate strategic significance
(Category II) are contained in §§ 73.21
and 73.22.
Section 76.117 Special Nuclear
Material of Low Strategic Significance—
Category III
The language of this section would be
changed to add a new paragraph (c) to
state that the requirements for the
protection of Safeguards Information
pertaining to special nuclear material of
low strategic significance (Category III)
are contained in §§ 73.21 and 73.22.
source, and byproduct material as the
Commission determines to be
significant to the public health and
safety or the common defense and
security. In response to this concern, the
Commission notes that it needs such
broad authority to adequately protect
SGI and section 147 of the AEA
provides such authority to the
Commission.
VIII. Plain Language
The Presidential Memorandum dated
June 1, 1998, entitled ‘‘Plain Language
in Government Writing,’’ directed that
the Government’s writing be in plain
language. This memorandum was
published June 10, 1998 (63 FR 31883).
The NRC requests comments on this
proposed rule specifically with respect
to the clarity and effectiveness of the
language used. Comments should be
sent to the address listed under the
heading ADDRESSES above.
VI. Criminal Penalties
For the purpose of section 223 of the
Atomic Energy Act (AEA), the
Commission is proposing to amend 10
CFR parts 2, 30, 40, 50, 52, 60, 63, 70,
71, 72, 73, 76, and 150 under one or
more of sections 147 161b, 161i, or 161o
of the AEA. Willful violations of the
rule would be subject to criminal
enforcement.
IX. Voluntary Consensus Standards
The National Technology Transfer Act
of 1995 (Pub. L. 104–113) requires that
Federal agencies use technical standards
that are developed or adopted by
voluntary consensus standards bodies
unless the use of such a standard is
inconsistent with applicable law or
otherwise impractical. In this proposed
rule, the NRC is using the following
Government-unique standard: National
Institute of Standards and Technology,
Federal Information Processing
Standard [FIPS] PUB–140–2, ‘‘Security
Requirements for Cryptographic
Modules,’’ May 25, 2001. The NRC has
determined that using this Governmentunique standard is justified because no
voluntary consensus standard has been
identified that could be used instead. In
addition, this Government-unique
standard was developed using the same
procedures used to create a voluntary
consensus standard.
VII. Agreement State Issues
The proposed changes to parts 2, 30,
40, 50, 52, 60, 63, 70, 71, 72, 73, 76, and
150 are considered to be Category NRC
compatibility and therefore are areas of
exclusive NRC authority. However, the
proposed rule has been provided to the
Agreement States for their review and
comment prior to publication of draft
rule text on the NRC Web site and the
publication of the proposed rule in the
Federal Register. The Agreement States
of Illinois and Washington commented
on the proposed rule. Both states
expressed concern about the breadth of
rule text reflecting the Commission’s
authority to prohibit the unauthorized
disclosure of SGI relating to such
quantities of special nuclear material,
X. Finding of No Significant Impact:
Environmental Assessment
The Commission has determined
under the National Environmental
Policy Act of 1969, as amended, and the
Commission’s regulations in subpart A
of 10 CFR part 51, that this rule, if
adopted, would not be a major Federal
action significantly affecting the quality
of the human environment and,
therefore, an environmental impact
statement is not required. The basis for
this determination is that the proposed
rule relates to the designation, handling
and protection of Safeguards
Information and the collection of
information on which a determination
to grant individuals access to this
information is based. The determination
Section 150.15 Persons Not Exempt
A change is also being proposed to
part 150, ‘‘Exemptions and Continued
Regulatory Authority in Agreement
States and In Offshore Waters Under
Section 274.’’ Paragraph (a)(9) would be
added to § 150.15, ‘‘Persons not
exempt,’’ to include the protection of
SGI in the list of activities by persons in
Agreement States that are not exempt
from the Commission’s licensing and
regulatory requirements.
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of this environmental assessment is that
there will be no significant
environmental impacts from this action.
However, the general public should note
that the NRC is seeking public
participation. Comments on any aspect
of the environmental assessment may be
submitted to the NRC as indicated
under the ADDRESSES heading.
The NRC has sent a copy of the
environmental assessment and proposed
rule to every State Liaison Officer and
requested comments on the
environmental assessment.
XI. Paperwork Reduction Act
Statement
This proposed rule amends
information collection requirements that
are subject to the Paperwork Reduction
Act of 1995 (44 U.S.C. 3501 et seq.).
This rule has been submitted to the
Office of Management and Budget for
review and approval of the information
collection requirements.
Type of Submission, New or Revision:
Revision.
The Title of the Information
Collection: 10 CFR 73, ‘‘Protection of
Safeguards Information.’’
The Form Number if Applicable: Not
applicable.
How often the collection is required:
Licensees must mark and protect from
unauthorized disclosure documents
containing Safeguards Information or
Safeguards Information designated for
modified handling, on a continuous
basis.
Who Will be Required or Asked to
Report: Power reactor licensees and
applicants, research and test reactor
licensees and applicants, certificate
holders and applicants, fuel cycle
facility licensees and applicants, and
certain other byproduct, source, and
special nuclear material licensees and
applicants.
An Estimate of the Number of Annual
Responses: None.
The Estimated Number of Annual
Respondents: 646 recordkeepers.
An Estimate of the Total Number of
Hours Needed Annually to Complete the
Requirement or Request: 5,926 (an
average of 9 hours per recordkeeper).
Abstract: The NRC is amending its
regulations for the protection of
Safeguards Information to protect it
from inadvertent release and
unauthorized disclosure which might
compromise the security of nuclear
facilities and materials. The proposed
amendments would be consistent with
Commission practices reflected in
previously issued Orders and
advisories. The proposed amendments
would affect certain licensees,
information, and materials not currently
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Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules
specified in the regulations but which
are within the scope of the
Commission’s statutory authority.
The U.S. Nuclear Regulatory
Commission is seeking public comment
on the potential impact of the
information collections contained in
this proposed rule and on the following
issues:
1. Is the proposed information
collection necessary for the proper
performance of the functions of the
NRC, including whether the information
will have practical utility?
2. Is the estimate of burden accurate?
3. Is there a way to enhance the
quality, utility, and clarity of the
information to be collected?
4. How can the burden of the
information collection be minimized,
including the use of automated
collection techniques?
A copy of the OMB clearance package
may be viewed free of charge at the NRC
Public Document Room, One White
Flint North, 11555 Rockville Pike, Room
O–1 F21, Rockville, MD 20852. The
OMB clearance package and rule are
available at the NRC worldwide Web
site: https://www.nrc.gov/public-involve/
doc-comment/omb/ for 60
days after the signature date of this
notice and are also available at the
RuleForum site, https://
ruleforum.llnl.gov.
Send comments on any aspect of
these proposed information collections,
including suggestions for reducing the
burden and on the above issues, by
March 14, 2005 to the Records and
FOIA/Privacy Services Branch (T–5
F52), U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, or by Internet electronic mail to
infocollects@nrc.gov and to the Desk
Officer, John A. Asalone, Office of
Information and Regulatory Affairs,
NEOB–10202, (3150–0002), Office of
Management and Budget, Washington,
DC 20503. Comments received after this
date will be considered if it is practical
to do so, but assurance of consideration
cannot be given to comments received
after this date. You may also e-mail
comments to
John_A._Asalone@omb.eop.gov or
comment by telephone at (202) 395–
4650.
Public Protection Notification
The NRC may not conduct or sponsor,
and a person is not required to respond
to, a request for information or an
information collection requirement
unless the requesting document
displays a currently valid OMB control
number.
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XII. Regulatory Analysis
The Commission has prepared a draft
regulatory analysis on this proposed
regulation. The analysis examines the
costs and benefits of the alternatives
considered by the Commission. The
regulatory analysis is available for
inspection in the NRC Public Document
Room, 11555 Rockville Pike, Rockville,
MD 20852. Single copies of the analysis
may be obtained from the Office of the
General Counsel, U.S. Nuclear
Regulatory Commission, at 301–415–
1633 or by e-mail at mur@nrc.gov. The
Commission requests public comment
on the draft regulatory analysis.
Comments on the draft analysis may be
submitted to the NRC as indicated
under the ADDRESSES heading.
XIII. Regulatory Flexibility Analysis
The NRC is seeking public comment
on the potential impact of the proposed
rule on small entities. The NRC
particularly desires comment from small
entities (i.e., small businesses, small
organizations, and small jurisdictions
under the Regulatory Flexibility Act) as
to how the proposed regulations will
affect them and how the regulations
may be tiered or otherwise modified to
impose less stringent requirements on
small entities while still adequately
protecting the public health and safety
or the common defense and security.
Those small entities that offer comments
on how the proposed regulations could
be modified to take into account the
differing needs of small entities should
specifically discuss—
(a) The licensee’s size and how the
proposed regulations would result in a
significant economic burden upon the
licensee as compared to a larger
licensee;
(b) How the proposed regulations
could be modified to take into account
the licensee’s differing needs or
capabilities;
(c) The benefits that would accrue, or
the detriments that would be avoided, if
the proposed regulations were modified
as suggested by the licensee;
(d) How the proposed regulations, as
modified, would more closely equalize
the impact of NRC regulations or create
more equal access to the benefits of
Federal programs as opposed to
providing some special advantages to
any particular individual or group;
(e) How the proposed regulation, as
modified, would still adequately protect
public health and safety or the common
defense and security.
Send comments to the NRC as
indicated under the ADDRESSES heading.
The Commission is preparing an
initial regulatory analysis of the impact
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of this proposed rule on small entities.
The NRC requests written comments on
the analysis. Send comments to the NRC
as indicated under the ADDRESSES
heading.
XIV. Backfit Analysis
The Commission has concluded, on
the basis of the documented evaluation
in the draft regulatory analysis, that the
majority of the requirements in the
proposed rule are not backfits as defined
in 10 CFR 50.109(a)(4)(ii),
70.76(a)(4)(iii), 72.62, and 76.76(a)(4)(ii).
The Commission has also concluded
that the requirements in the rule that
constitute backfits are necessary to
insure that the facilities and materials
described in the proposed rule provide
adequate protection to the public health
and safety and are in accord with the
common defense and security, as
applicable. Therefore, a backfit analysis
is not required and the cost-benefit
standards of 10 CFR 50.109(a)(3), 70.76,
72.62, and 76.76, do not apply. The
documented evaluation in the draft
Regulatory Analysis includes a
statement of the objectives of and the
reasons for the backfits that would be
required by the proposed rule and sets
forth the Commission’s conclusion that
these backfits are not subject to the costbenefit standards of 10 CFR 50.109(a)(3),
70.76, 72.62, and 76.76.
List of Subjects
10 CFR Part 2
Administrative practice and
procedure, Antitrust, Byproduct
material, Classified information,
Environmental protection, Nuclear
materials, Nuclear power plants and
reactors, Penalties, Sex discrimination,
Source material, Special nuclear
material, Waste treatment and disposal.
10 CFR Part 30
Byproduct material, Criminal
penalties, Government contracts,
Intergovernmental relations, Isotopes,
Nuclear materials, Radiation protection,
Reporting and recordkeeping
requirements.
10 CFR Part 40
Criminal penalties, Government
contracts, Hazardous materials
transportation, Nuclear materials,
Reporting and recordkeeping
requirements, Source material,
Uranium.
10 CFR Part 50
Antitrust, Classified information,
Criminal penalties, Fire protection,
Intergovernmental relations, Nuclear
power plants and reactors, Radiation
protection, Reactor siting criteria,
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Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules
Reporting and recordkeeping
requirements.
measures, Special nuclear material,
Uranium enrichment by gaseous
diffusion.
10 CFR Part 52
Administrative practice and
procedure, Antitrust, Backfitting,
Combined license, Early site permit,
Emergency planning, Fees, Inspection,
Limited work authorization, Nuclear
power plants and reactors, Probabilistic
risk assessment, Prototype, Reactor
siting criteria, Redress of site, Reporting
and recordkeeping requirements,
Standard design, Standard design
certification.
10 CFR Part 60
Criminal penalties, High-level waste,
Nuclear materials, Nuclear power plants
and reactors, Reporting and
recordkeeping requirements, Waste
treatment and disposal.
10 CFR Part 63
Criminal penalties, High-level waste,
Nuclear power plants and reactors,
Reporting and recordkeeping
requirements, Waste treatment and
disposal.
10 CFR Part 70
Criminal penalties, Hazardous
materials transportation, Material
control and accounting, Nuclear
materials, Packaging and containers,
Radiation protection, Reporting and
recordkeeping requirements, Scientific
equipment, Security measures, Special
nuclear material.
10 CFR Part 71
Criminal penalties, Hazardous
materials transportation, Nuclear
materials, Packaging and containers,
Reporting and recordkeeping
requirements.
10 CFR Part 72
Administrative practice and
procedure, Criminal penalties,
Manpower training programs, Nuclear
materials, Occupational safety and
health, Penalties, Radiation protection,
Reporting and recordkeeping
requirements, Security measures, Spent
fuel, Whistleblowing.
10 CFR Part 73
Criminal penalties, Export, Hazardous
materials transportation, Import,
Nuclear materials, Nuclear power plants
and reactors, Reporting and
recordkeeping requirements, Security
measures.
10 CFR Part 76
Certification, Criminal penalties,
Radiation protection, Reporting and
recordkeeping requirements, Security
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10 CFR Part 150
Criminal penalties, Hazardous
materials transportation,
Intergovernmental relations, Nuclear
materials, Reporting and recordkeeping
requirements, Security measures,
Source material, Special nuclear
material.
For the reasons set out in the
preamble and under the authority of the
Atomic Energy Act of 1954, as amended;
the Energy Reorganization Act of 1974,
as amended; and 5 U.S.C. 553, the NRC
is proposing to adopt the following
amendments to 10 CFR Parts 2, 30, 40,
50, 52, 60, 63, 70, 71, 72, 73, 76 and 150.
PART 2—RULES OF PRACTICE FOR
DOMESTIC LICENSING PROCEEDINGS
AND ISSUANCE OF ORDERS
1. The authority citation for part 2
continues to read as follows:
Authority: Secs. 161, 181, 68 Stat. 948,
953, as amended (42 U.S.C. 2201, 2231); sec.
191, as amended, Pub. L. 87–615, 76 Stat. 409
(42 U.S.C. 2241); sec. 201, 88 Stat. 1242, as
amended (42 U.S.C. 5841); 5 U.S.C. 552; sec.
1704, 112 Stat. 2750 (44 U.S.C. 3504 note).
Section 2.101 also issued under secs. 53, 62,
63, 81, 103, 104, 105, 68 Stat. 930, 932, 933,
935, 936, 937, 938, as amended (42 U.S.C.
2073, 2092, 2093, 2111, 2133, 2134, 2135);
sec. 114(f), Pub. L. 97—425, 96 Stat. 2213, as
amended (42 U.S.C. 10143(f)), sec. 102, Pub.
L. 91—190, 83 Stat. 853, as amended (42
U.S.C. 4332); sec. 301, 88 Stat. 1248 (42
U.S.C. 5871). Sections 2.102, 2.103, 2.104,
2.105, 2.721 also issued under secs. 102, 103,
104, 105, 183i, 189, 68 Stat. 936, 937, 938,
954, 955, as amended (42 U.S.C. 2132, 2133,
2134, 2135, 2233, 2239). Sections 2.105 also
issued under Pub. L. 97–415, 96 Stat. 2073
(42 U.S.C. 2239). Sections 2.200—2.206 also
issued under secs. 161 b, i, o, 182, 186, 234,
68 Stat. 948–951, 955, 83 Stat. 444, as
amended (42 U.S.C. 2201 (b), (i), (o), 2236,
2282); sec. 206, 88 Stat 1246 (42 U.S.C. 5846).
Section 2.205(j) also issued under Pub. L.
101–410, 104 Stat. 90, as amended by section
3100(s), Pub. L. 104–134, 110 Stat. 1321–373
(28 U.S.C. 2461 note). Sections 2.600–2.606
also issued under sec. 102, Pub. L. 91–190,
83 Stat. 853, as amended (42 U.S.C. 4332).
Sections 2.700a, 2.719 also issued under 5
U.S.C. 554. Sections 2.754, 2.760, 2.770,
2.780 also issued under 5 U.S.C. 557. Section
2.764 also issued under secs. 135, 141, Pub.
L. 97—425, 96 Stat. 2232, 2241 (42 U.S.C.
10155, 10161). Section 2.790 also issued
under sec. 103, 68 Stat. 936, as amended (42
U.S.C. 2133), and 5 U.S.C. 552. Sections
2.800 and 2.808 also issued under 5 U.S.C.
553. Section 2.809 also issued under 5 U.S.C.
553, and sec. 29, Pub. L. 85–256, 71 Stat. 579,
as amended (42 U.S.C. 2039). Subpart K also
issued under sec. 189, 68 Stat. 955 (42 U.S.C.
2239); sec. 134, Pub. L. 97–425, 96 Stat. 2230
(42 U.S.C. 10154). Subpart L also issued
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under sec. 189, 68 Stat. 955 (42 U.S.C. 2239).
Subpart M also issued under sec. 184 (42
U.S.C. 2234) and sec. 189, 68 stat. 955 (42
U.S.C. 2239). Appendix A also issued under
sec. 6, Pub. L. 91–560, 84 Stat. 1473 (42
U.S.C. 2135).
2. Paragraph (f) of § 2.709 is amended
to read as follows:
§ 2.709
Discovery against NRC staff.
*
*
*
*
*
(f) In the case of requested documents
and records (including Safeguards
Information referred to in sections 147
and 181 of the Atomic Energy Act, as
amended) exempt from disclosure under
§ 2.390, but whose disclosure is found
by the presiding officer to be necessary
to a proper decision in the proceeding,
any order to the Executive Director for
Operations or a delegate of the
Executive Director for Operations, to
produce the document or records (or
any other order issued ordering
production of the document or records)
may contain any protective terms and
conditions (including affidavits of nondisclosure) as may be necessary and
appropriate to limit the disclosure to
parties in the proceeding, to interested
States and other governmental entities
participating under § 2.315(c), and to
their qualified witnesses and counsel.
When Safeguards Information protected
from disclosure under section 147 of the
Atomic Energy Act, as amended, is
received and possessed by a party other
than the Commission staff, it must also
be protected according to the
requirements of § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable. The presiding
officer may also prescribe additional
procedures to effectively safeguard and
prevent disclosure of Safeguards
Information to unauthorized persons
with minimum impairment of the
procedural rights which would be
available if Safeguards Information were
not involved. In addition to any other
sanction that may be imposed by the
presiding officer for violation of an
order issued pursuant to this paragraph,
violation of an order pertaining to the
disclosure of Safeguards Information
protected from disclosure under section
147 of the Atomic Energy Act, as
amended, may be subject to a civil
penalty imposed under § 2.205. For the
purpose of imposing the criminal
penalties contained in section 223 of the
Atomic Energy Act, as amended, any
order issued pursuant to this paragraph
with respect to Safeguards Information
is considered to be an order issued
under section 161.b. of the Atomic
Energy Act.
*
*
*
*
*
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3. In § 2.1003, paragraph (a)(4)(iii) is
revised to read as follows:
§ 2.1003
Availability of material.
(a) * * *
(4) * * *
(iii) Which constitutes Safeguards
Information under § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable.
*
*
*
*
*
4. In § 2.1010, paragraph (b)(6) is
revised to read as follows:
§ 2.1010
officer.
Pre-License application presiding
*
*
*
*
*
(b) * * *
(6) Whether the material should be
disclosed under a protective order
containing such protective terms and
conditions (including affidavits of
nondisclosure) as may be necessary and
appropriate to limit the disclosure to
potential participants, interested
governmental participants and parties in
the proceeding, or to their qualified
witnesses and counsel. When
Safeguards Information, protected from
disclosure under section 147 of the
Atomic Energy Act of 1954, as amended,
is received and possessed by a potential
party, interested governmental
participant, or party, other than the
Commission staff, it shall also be
protected according to the requirements
of § 73.21 and the requirements in
§ 73.22 or § 73.23 of this chapter, as
applicable. The Pre-License Application
Presiding Officer may also prescribe
such additional procedures as will
effectively safeguard and prevent
disclosure of Safeguards Information to
unauthorized persons with minimum
impairment of the procedural rights
which would be available if Safeguards
Information were not involved. In
addition to any other sanction that may
be imposed by the Pre-License
Application Presiding Officer for
violation of an order pertaining to the
disclosure of Safeguards Information
protected from disclosure under section
147 of the Atomic Energy Act of 1954,
as amended, the entity in violation may
be subject to a civil penalty imposed
pursuant to § 2.205. For the purpose of
imposing the criminal penalties
contained in section 223 of the Atomic
Energy Act of 1954, as amended, any
order issued pursuant to this paragraph
with respect to Safeguards Information
shall be deemed to be an order issued
under section 161b of the Atomic
Energy Act of 1954, as amended.
*
*
*
*
*
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PART 30—RULES OF GENERAL
APPLICABILITY TO DOMESTIC
LICENSING OF BYPRODUCT
MATERIAL
5. The authority citation for part 30
continues to read as follows:
Authority: Secs. 81, 82, 161, 182, 183, 186,
68 Stat. 935, 948, 953, 954, 955, as amended,
sec. 234, 83 Stat. 444, as amended (42 U.S.C.
2111, 2112, 2201, 2232, 2233, 2236, 2282);
secs. 201, as amended, 202, 206, 88 Stat.
1242, as amended, 1244, 1246 (42 U.S.C.
5841, 5842, 5846); sec. 1704, 112 Stat. 2750
(44 U.S.C. 3504 note). Section 30.7 also
issued under Pub. L. 95–601, sec. 10, 92 Stat.
2951 as amended by Pub. L. 102–486, sec.
2902, 106 Stat. 3123, (42 U.S.C. 5851).
Section 30.34(b) also issued under sec. 184,
68 Stat. 954, as amended (42 U.S.C. 2234).
Section 30.61 also issued under sec. 187, 68
Stat. 955 (42 U.S.C. 2237).
6. In § 30.32, paragraph (j) is added to
read as follows:
§ 30.32
Application for specific licenses.
*
*
*
*
*
(j) Each applicant for a license for
byproduct material in quantities
determined by the Commission through
order or regulation to be significant to
the public health and safety or the
common defense and security who
prepares a physical security plan,
security procedures for emergencies, or
guard qualification and training
procedures, shall protect the plans,
procedures, and other related
Safeguards Information against
unauthorized disclosure in accordance
with the requirements in §§ 73.21 and
73.23 of this chapter, as applicable.
7. In § 30.34, paragraph (j) is added to
read as follows:
§ 30.34
Terms and conditions of licenses.
*
*
*
*
*
(j) Each licensee subject to the
requirements of part 73 of this chapter
shall ensure that physical security
plans, security procedures for
emergencies, guard qualification and
training procedures and other related
Safeguards Information are protected
against unauthorized disclosure in
accordance with the requirements in
§§ 73.21 and 73.23 of this chapter, as
applicable.
PART 40—DOMESTIC LICENSING OF
SOURCE MATERIAL
8. The authority citation for part 40
continues to read as follows:
Authority: Secs. 62, 63, 64, 65, 81, 161,
182, 183, 186, 68 Stat. 932, 933, 935, 948,
953, 954, 955, as amended, secs. 11e(2), 83,
84, Pub. L. 95–604, 92 Stat. 3033, as
amended, 3039, sec. 234, 83 Stat. 444, as
amended (42 U.S.C. 2014(e)(2), 2092, 2093,
2094, 2095, 2111, 2113, 2114, 2201, 2232,
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2233, 2236, 2282); sec. 274, Pub. L. 86–373,
73 Stat. 688 (42 U.S.C. 2021); secs. 201, as
amended, 202, 206, 88 Stat. 1242, as
amended, 1244, 1246 (42 U.S.C. 5841, 5842,
5846); sec. 275, 92 Stat. 3021, as amended by
Pub. L. 97–415, 96 Stat. 2067 (42 U.S.C.
2022); sec. 193, 104 Stat. 2835, as amended
by Pub. L. 104–134, 110 Stat. 1321, 1321–349
(42 U.S.C. 2243); sec. 1704, 112 Stat. 2750 (44
U.S.C. 3504 note). Section 40.7 also issued
under Pub. L. 95–601, sec. 10, 92 Stat. 2951
(42 U.S.C. 5851). Section 40.31(g) also issued
under sec. 122, 68 Stat. 939 (42 U.S.C. 2152).
Section 40.46 also issued under sec. 184, 68
Stat. 954, as amended (42 U.S.C. 2234).
Section 40.71 also issued under sec. 187, 68
Stat. 955 (42 U.S.C. 2237).
9. In § 40.31, paragraph (m) is added
to read as follows:
§ 40.31
Application for specific licenses.
*
*
*
*
*
(m) Each applicant for a license for
source material in quantities determined
by the Commission through order or
regulation to be significant to the public
health and safety or the common
defense and security who prepares a
physical security plan, security
procedures for emergencies, or guard
qualification and training procedures,
shall protect the plans, procedures, and
other related Safeguards Information
against unauthorized disclosure in
accordance with the requirements in
§ 73.21 and the requirements of § 73.22
or § 73.23 of this chapter, as applicable.
10. In § 40.41, paragraph (h) is added
to read as follows:
§ 40.41
Terms and conditions of licenses.
*
*
*
*
*
(h) Each licensee subject to the
requirements of part 73 of this chapter
shall ensure that physical security
plans, security procedures for
emergencies, guard qualification and
training procedures and other related
Safeguards Information are protected
against unauthorized disclosure in
accordance with the requirements in
§ 73.21 and the requirements of § 73.22
or § 73.23 of this chapter, as applicable.
PART 50—DOMESTIC LICENSING OF
PRODUCTION AND UTILIZATION
FACILITIES
11. The authority citation for part 50
continues to read as follows:
Authority: Secs. 102, 103, 104, 105, 161,
182, 183, 186, 189, 68 Stat. 936, 937, 938,
948, 953, 954, 955, 956, as amended, sec.
234, 83 Stat. 444, as amended (42 U.S.C.
2132, 2133, 2134, 2135, 2201, 2232, 2233,
2236, 2239, 2282); secs. 201, as amended,
202, 206, 88 Stat. 1242, as amended, 1244,
1246 (42 U.S.C. 5841, 5842, 5846); sec. 1704,
112 Stat. 2750 (44 U.S.C. 3504 note). Section
50.7 also issued under Pub. L. 95–601, sec.
10, 92 Stat. 2951 (42 U.S.C. 5841). Section
50.10 also issued under secs. 101, 185, 68
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Stat. 955, as amended (42 U.S.C. 2131, 2235);
sec. 102, Pub. L. 91–190, 83 Stat. 853 (42
U.S.C. 4332). Sections 50.13, 50.54(dd), and
50.103 also issued under sec. 108, 68 Stat.
939, as amended (42 U.S.C. 2138). Sections
50.23, 50.35, 50.55, and 50.56 also issued
under sec. 185, 68 Stat. 955 (42 U.S.C. 2235).
Sections 50.33a, 50.55a and Appendix Q also
issued under sec. 102, Pub. L. 91–190, 83
Stat. 853 (42 U.S.C. 4332). Sections 50.34 and
50.54 also issued under sec. 204, 88 Stat.
1245 (42 U.S.C. 5844). Sections 50.58, 50.91,
and 50.92 also issued under Pub. L. 97–415,
96 Stat. 2073 (42 U.S.C. 2239). Section 50.78
also issued under sec. 122, 68 Stat. 939 (42
U.S.C. 2152). Sections 50.80—50.81 also
issued under sec. 184, 68 Stat. 954, as
amended (42 U.S.C. 2234). Appendix F also
issued under sec. 187, 68 Stat. 955 (42 U.S.C.
2237).
12. In § 50.34, paragraph (e) is revised
to read as follows:
§ 50.34 Contents of applications; technical
information.
*
*
*
*
*
(e) Each applicant for a license to
operate a production or utilization
facility, who prepares a physical
security plan, a safeguards contingency
plan, or a guard qualification and
training plan, shall protect the plans
and other related Safeguards
Information against unauthorized
disclosure in accordance with the
requirements in § 73.21 and the
requirements in § 73.22 or § 73.23 of this
chapter, as applicable.
*
*
*
*
*
13. In § 50.54, paragraph (v) is revised
to read as follows:
§ 50.54
Conditions of licenses.
*
*
*
*
*
(v) Each licensee subject to the
requirements of part 73 of this chapter
shall ensure that physical security,
safeguards contingency and guard
qualification and training plans and
other related Safeguards Information are
protected against unauthorized
disclosure in accordance with the
requirements in § 73.21 and the
requirements in § 73.22 or § 73.23 of this
chapter, as applicable.
*
*
*
*
*
PART 52—EARLY SITE PERMITS;
STANDARD DESIGN
CERTIFICATIONS; AND COMBINED
LICENSES FOR NUCLEAR POWER
PLANTS
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measures for physical protection of
high-level radioactive waste, including
the design for physical protection, the
safeguards contingency plan, the
security organization personnel training
and qualification plan, and other related
security information.
19. In § 60.42, paragraph (d) is added
to read as follows:
15. In § 52.47, paragraph (c) is added
to read as follows:
§ 60.42
§ 52.47
Contents of applications.
*
*
*
*
*
(c) Each applicant for a standard
design certification under this part shall
protect Safeguards Information against
unauthorized disclosure in accordance
with the requirements in §§ 73.21 and
73.22 of this chapter, as applicable.
16. In § 52.79, paragraph (e) is added
to read as follows:
§ 52.79 Contents of application; technical
information.
*
*
*
*
*
(e) Each applicant for a combined
license under this subpart shall protect
Safeguards Information against
unauthorized disclosure in accordance
with the requirements in §§ 73.21 and
73.22 of this chapter, as applicable.
PART 60—DISPOSAL OF HIGH-LEVEL
RADIOACTIVE WASTES IN GEOLOGIC
REPOSITORIES
17. The authority citation for part 60
continues to read as follows:
Authority: Secs. 51, 53, 62, 63, 65, 81, 161,
182, 183, 68 Stat. 929, 930, 932, 933, 935,
948, 953, 954, as amended (42 U.S.C. 2071,
2073, 2092, 2093, 2095, 2111, 2201, 2232,
2233); secs. 202, 206, 88 Stat. 1244, 1246 (42
U.S.C. 5842, 5846); secs. 10 and 14, Pub. L.
95–601, 92 Stat. 2951 (42 U.S.C. 2021a and
5851); sec. 102, Pub. L. 91–190, 83 Stat. 853
(42 U.S.C. 4332); secs. 114, 121, Pub. L. 97–
425, 96 Stat. 2213g, 2228, as amended (42
U.S.C. 10134, 10141), and Pub. L. 102–486,
sec. 2902, 106 Stat. 3123 (42 U.S.C. 5851);
sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504
note).
18. In § 60.21, paragraph (d) is added
to read as follows:
Content of application.
*
Authority: Sec. 161, 68 Stat. 948, as
amended, sec. 274, 73 Stat. 688 (42 U.S.C.
2201, 2021); sec. 201, 88 Stat. 1242, as
amended (42 U.S.C. 5841); sec. 1704, 112
Stat. 2750 (44 U.S.C. 3504 note). Sections
150.3, 150.15, 150.15a, 150.31, 150.32 also
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issued under secs. 11e(2), 81, 68 Stat. 923,
935, as amended, secs. 83, 84, 92 Stat. 3033,
3039 (42 U.S.C. 2014e(2), 2111, 2113, 2114).
Section 150.14 also issued under sec. 53, 68
Stat. 930, as amended (42 U.S.C. 2073).
Section 150.15 also issued under secs. 135,
141, Pub. L. 97–425, 96 Stat. 2232, 2241 (42
U.S.C. 10155, 10161). Section 150.17a also
issued under sec. 122, 68 Stat. 939 (42 U.S.C.
2152). Section 150.30 also issued under sec.
234, 83 Stat. 444 (42 U.S.C. 2282).
§ 60.21
14. The authority citation for part 52
continues to read as follows:
7209
*
*
*
*
(d) The applicant for a license to
receive and possess source, special
nuclear, and byproduct material at a
geologic repository operations area
sited, constructed, or operated in
accordance with the Nuclear Waste
Policy Act of 1982 shall protect as
Safeguards Information in accordance
with § 73.21 and the requirements of
§ 73.22 or § 73.23 of this chapter, as
applicable, the detailed security
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Fmt 4702
Sfmt 4702
Conditions of license.
*
*
*
*
*
(d) The licensee shall ensure that the
detailed security measures for physical
protection of high-level radioactive
waste, including the design for physical
protection, the safeguards contingency
plan, the security organization
personnel training and qualification
plan and other related security
information is protected against
unauthorized disclosure in accordance
with the requirements in § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable.
PART 63—DISPOSAL OF HIGH-LEVEL
RADIOACTIVE WASTES IN A
GEOLOGIC REPOSITORY AT YUCCA
MOUNTAIN, NEVADA
20. The authority citation for part 63
continues to read as follows:
Authority: Secs. 51, 53, 62, 63, 65, 81, 161,
182, 183, 68 Stat. 929, 930, 932, 933, 935,
948, 953, 954, as amended (42 U.S.C. 2071,
2073, 2092, 2093, 2095, 2111, 2201, 2232,
2233); secs. 202, 206, 88 Stat. 1244, 1246 (42
U.S.C. 5842, 5846); secs. 10 and 14, Pub. L.
95–601, 92 Stat. 2951 (42 U.S.C. 2021a and
5851); sec. 102, Pub. L. 91–190, 83 Stat. 853
(42 U.S.C. 4332); secs. 114, 121, Pub. L. 97–
425, 96 Stat. 2213g, 2238, as amended (42
U.S.C. 10134, 10141), and Pub. L. 102–486,
sec. 2902, 106 Stat. 3123 (42 U.S.C. 5851);
sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504
note).
21. In § 63.21, paragraph (d) is added
to read as follows:
§ 63.21
Content of application.
*
*
*
*
*
(d) The applicant for a license to
receive and possess source, special
nuclear, and byproduct material at a
geologic repository at Yucca Mountain,
Nevada, shall protect as Safeguards
Information in accordance with §§ 73.21
and 73.22 of this chapter, the detailed
security measures for physical
protection of high-level radioactive
waste, including the design for physical
protection, the safeguards contingency
plan, and security organization
personnel training and qualification
plan and other related Safeguards
Information.
22. In § 63.42, paragraph (e) is added
to read as follows:
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§ 63.42
Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules
Conditions of license.
*
*
*
*
*
(e) The licensee shall ensure that the
detailed security measures for physical
protection of high-level radioactive
waste, including the design for physical
protection, the safeguards contingency
plan, and security organization
personnel training and qualification
plan and other related Safeguards
Information is protected against
unauthorized disclosure in accordance
with the requirements in §§ 73.21 and
73.22 of this chapter, as applicable.
PART 70—DOMESTIC LICENSING OF
SPECIAL NUCLEAR MATERIAL
23. The authority citation for part 70
continues to read as follows:
Authority: Secs. 51, 53, 161, 182, 183, 68
Stat. 929, 930, 948, 953, 954, as amended,
sec. 234, 83 Stat. 444, as amended, (42 U.S.C.
2071, 2073, 2201, 2232, 2233, 2282, 2297f);
secs. 201, as amended, 202, 204, 206, 88 Stat.
1242, as amended, 1244, 1245, 1246 (42
U.S.C. 5841, 5842, 5845, 5846). Sec. 193, 104
Stat. 2835 as amended by Pub.L. 104–134,
110 Stat. 1321, 1321–349 (42 U.S.C. 2243);
sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504
note). Sections 70.1(c) and 70.20a(b) also
issued under secs. 135, 141, Pub. L. 97–425,
96 Stat. 2232, 2241 (42 U.S.C. 10155, 10161).
Section 70.7 also issued under Pub. L. 95–
601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5851).
Section 70.21(g) also issued under sec. 122,
68 Stat. 939 (42 U.S.C. 2152). Section 70.31
also issued under sec. 57d, Pub. L. 93–377,
88 Stat. 475 (42 U.S.C. 2077). Sections 70.36
and 70.44 also issued under sec. 184, 68 Stat.
954, as amended (42 U.S.C. 2234). Section
70.81 also issued under secs. 186, 187, 68
Stat. 955 (42 U.S.C. 2236, 2237). Section
70.82 also issued under sec. 108, 68 Stat. 939,
as amended (42 U.S.C. 2138).
24. In § 70.22, paragraph (l) is revised
and paragraph (o) is added to read as
follows:
§ 70.22
Contents of applications.
*
*
*
*
*
(l) Each applicant for a license to
possess, use, transport, or deliver to a
carrier for transport formula quantities
of strategic special nuclear material, or
more than 100 grams of irradiated
reactor fuel, who prepares a physical
security, safeguards contingency, or
guard qualification and training plan
shall protect these plans and other
related Safeguards Information against
unauthorized disclosure in accordance
with the requirements in § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable.
*
*
*
*
*
(o) Each applicant for a license to
possess, use, transport or deliver to a
carrier for transport special nuclear
material of low or moderate strategic
significance, who prepares a physical
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security plan, safeguards contingency
plan, or guard qualification and training
plan shall protect these plans and other
related security Information against
unauthorized disclosure in accordance
with the requirements in §§ 73.21 and
73.23 of this chapter.
25. In § 70.32, paragraph (j) is revised
and paragraph (I) is added to read as
follows:
in quantities determined by the
Commission through order or regulation
to be significant to the public health and
safety or the common defense and
security, shall protect Safeguards
Information against unauthorized
disclosure in accordance with the
requirements in § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable.
§ 70.32
PART 72—LICENSING
REQUIREMENTS FOR THE
INDEPENDENT STORAGE OF SPENT
NUCLEAR FUEL, HIGH-LEVEL
RADIOACTIVE WASTE, AND
REACTOR-RELATED GREATER THAN
CLASS C WASTE
Conditions of licenses.
*
*
*
*
*
(j) Each licensee who possesses a
formula quantity of strategic special
nuclear material, or who transports, or
delivers to a carrier for transport, a
formula quantity of strategic special
nuclear material, special nuclear
material of moderate strategic
significance, or special nuclear material
of low strategic significance, or more
than 100 grams of irradiated reactor fuel
shall ensure that physical security,
safeguards contingency, and guard
qualification and training plans and
other related Safeguards Information are
protected against unauthorized
disclosure in accordance with the
requirements in § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable.
*
*
*
*
*
(l) Each licensee who possesses, uses,
transports, or delivers to a carrier for
transport special nuclear material of
moderate or low strategic significance
and who prepares a physical security
plan shall protect the plan and other
related Safeguards Information against
unauthorized disclosure in accordance
with the requirements in §§ 73.21 and
73.23 of this chapter.
PART 71—PACKAGING AND
TRANSPORTATION OF RADIOACTIVE
MATERIAL
26. The authority citation for part 71
continues to read as follows:
Authority: Secs. 53, 57, 62, 63, 81, 161,
182, 183, 68 Stat. 930, 932, 933, 935, 948,
953, 954, as amended, sec. 1701, 106 Stat.
2951, 2952, 2953 (42 U.S.C. 2073, 2077, 2092,
2093, 2111, 2201, 2232, 2233, 2297f); secs.
201, as amended, 202, 206, 88 Stat. 1242, as
amended, 1244, 1246 (42 U.S.C. 5841, 5842,
5846); sec. 1704, 112 Stat. 2750 (44 U.S.C.
3504 note). Section 71.97 also issued under
sec. 301, Pub. L. 96–295, 94 Stat. 789–790.
27. § 71.11 is added to read as follows:
§ 71.11 Protection of Safeguards
Information.
Each licensee, certificate holder, or
applicant for a Certificate of Compliance
for a transportation package for
transport of spent fuel, strategic special
nuclear material, critical mass of special
nuclear material, or byproduct material
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28. The authority citation for Part 72
continues to read as follows:
Authority: Secs. 51, 53, 57, 62, 63, 65, 69,
81, 161, 182, 183, 184, 186, 187, 189, 68 Stat.
929, 930, 932, 933, 934, 935, 948, 953, 954,
955, as amended, sec. 234, 83 Stat. 444, as
amended (42 U.S.C. 2071, 2073, 2077, 2092,
2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2238, 2282); sec. 274, Pub.
L. 86–373, 73 Stat. 688, as amended (42
U.S.C. 2021); sec. 201, as amended, 202, 206,
88 Stat. 1242, as amended, 1244, 1246 (42
U.S.C. 5841, 5842, 5846); Pub. L. 95–601, sec.
10, 92 Stat. 2951 as amended by Pub. L. 102–
486, sec. 7902, 106 Stat. 3123 (42 U.S.C.
5851); sec. 102, Pub. L. 91–190, 83 Stat. 853
(42 U.S.C. 4332); secs. 131, 132, 133, 135,
137, 141, Pub. L. 97–425, 96 Stat. 2229, 2230,
2232, 2241, sec. 148, Pub. L. 100–203, 101
Stat. 1330–235 (42 U.S.C. 10151, 10152,
10153, 10155, 10157, 10161, 10168); sec.
1704, 112 Stat. 2750 (44 U.S.C. 3504 note).
Section 72.44(g) also issued under secs.
142(b) and 148(c), (d), Pub. L. 100–203, 101
Stat. 1330–232, 1330–236 (42 U.S.C.
10162(b), 10168(c), (d)). Section 72.46 also
issued under sec. 189, 68 Stat. 955 (42 U.S.C.
2239); sec. 134, Pub. L. 97–425, 96 Stat. 2230
(42 U.S.C. 10154). Section 72.96(d) also
issued under sec. 145(g), Pub. L. 100–203,
101 Stat. 1330–235 (42 U.S.C. 10165(g)).
Subpart J also issued under secs. 2(2), 2(15),
2(19), 117(a), 141(h), Pub. L. 97–425, 96 Stat.
2202, 2203, 2204, 2222, 2224 (42 U.S.C.
10101, 10137(a), 10161(h)). Subparts K and L
are also issued under sec. 133, 98 Stat. 2230
(42 U.S.C. 10153) and sec. 218(a), 96 Stat.
2252 (42 U.S.C. 10198).
29. In § 72.22, paragraph (f) is added
to read as follows:
§ 72.22 Contents of application: General
and financial information.
*
*
*
*
*
(f) Each applicant for a license under
this part to receive, transfer, and possess
power reactor spent fuel, power reactorrelated Greater than Class C (GTCC)
waste, and other radioactive materials
associated with spent fuel storage in an
independent spent fuel storage
installation (ISFSI) shall protect
Safeguards Information against
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unauthorized disclosure in accordance
with the requirements in § 73.21 and the
requirements of § 73.22 or § 73.23, as
applicable.
30. In § 72.44, paragraph (h) is added
to read as follows:
§ 72.44
License conditions.
*
*
*
*
*
(h) Each licensee subject to the
requirements of part 73 of this chapter
shall protect Safeguards Information
against unauthorized disclosure in
accordance with the requirements of
§ 73.21 and the requirements of § 73.22
or § 73.23, as applicable.
31. In § 72.212, paragraph (b)(5)(v) is
re-designated as (b)(5)(vi) and a new
paragraph (b)(5)(v) is added to read as
follows:
§ 72.212 Conditions of general license
issued under § 72.210.
*
*
*
*
*
(b) * * *
(5) * * *
(v) Each general licensee that receives,
transfers, and possesses power reactor
spent fuel, power reactor-related Greater
than Class C (GTCC) waste, and other
radioactive materials associated with
spent fuel storage shall protect
Safeguards Information against
unauthorized disclosure in accordance
with the requirements of § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable.
*
*
*
*
*
32. In § 72.236, paragraph (n) is added
to read as follows:
§ 72.236 Specific requirements for spent
fuel storage cask approval and fabrication.
*
*
*
*
*
(n) Safeguards Information shall be
protected against unauthorized
disclosure in accordance with the
requirements of § 73.21 and the
requirements of § 73.22 or § 73.23 of this
chapter, as applicable.
PART 73—PHYSICAL PROTECTION OF
PLANTS AND MATERIALS
33. The authority citation for part 73
continues to read as follows:
Authority: Secs. 53, 161, 68 Stat. 930, 948,
as amended, sec. 147, 94 Stat. 780 (42 U.S.C.
2073, 2167, 2201); sec. 201, as amended, 204,
88 Stat. 1242, as amended, 1245, sec. 1701,
106 Stat. 2951, 2952, 2953 (42 U.S.C. 5841,
5844, 2297f); sec. 1704, 112 Stat. 2750 (44
U.S.C. 3504 note). Section 73.1 also issued
under secs. 135, 141, Pub. L. 97–425, 96 Stat.
2232, 2241 (42 U.S.C, 10155, 10161). Section
73.37(f) also issued under sec. 301, Pub. L.
96–295, 94 Stat. 789 (42 U.S.C. 5841 note).
Section 73.57 is issued under sec. 606, Pub.
L. 99–399, 100 Stat. 876 (42 U.S.C. 2169).
34. In § 73.1, paragraph (b)(7) is
revised to read as follows:
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§ 73.1
Purpose and scope.
*
*
*
*
*
(b) * * *
(7) This part prescribes requirements
for the protection of Safeguards
Information (including the designation
or marking: Safeguards Information—
Modified Handling) in the hands of any
person, whether or not a licensee of the
Commission, who produces, receives, or
acquires that information.
*
*
*
*
*
35. In § 73.2, new definitions
Individual Authorized Access to
Safeguards Information, Individual
Authorized Access to Safeguards
Information—Modified Handling,
Safeguards Information—Modified
Handling Requirements and
Trustworthiness and reliability, are
added in alphabetical order and the
definition of Safeguards Information is
revised to read as follows:
§ 73.2
Definitions.
*
*
*
*
*
Individual Authorized Access to
Safeguards Information is an individual
authorized to have access to and handle
such information pursuant to the
requirements of §§ 73.21 and 73.22 of
this chapter.
Individual Authorized Access to
Safeguards Information—Modified
Handling Requirements is an individual
authorized to have access to and handle
such information pursuant to the
requirements of §§ 73.21 and 73.23 of
this chapter.
*
*
*
*
*
Safeguards Information means
information not otherwise classified as
National Security Information or
Restricted Data which specifically
identifies detailed control and
accounting procedures for special
nuclear material in quantities
determined by the Commission through
order or regulation to be significant to
the public health and safety or the
common defense and security; detailed
security measures (including security
plans, procedures, and equipment) for
the physical protection of source,
byproduct, or special nuclear material
in quantities determined by the
Commission through order or regulation
to be significant to the public health and
safety or the common defense and
security; security measures for the
physical protection and location of
certain plant equipment vital to the
safety of production or utilization
facilities; and any other information the
unauthorized disclosure of which, as
determined by the Commission through
order or regulation, could reasonably be
expected to have a significant adverse
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effect on the health and safety of the
public or the common defense and
security by significantly increasing the
likelihood of radiological sabotage or
theft or diversion of source, byproduct,
or special nuclear material.
Safeguards Information—Modified
Handling is the designation or marking
applied to Safeguards Information
which the Commission has determined
requires handling requirements
modified from those for other
Safeguards Information.
*
*
*
*
*
Trustworthiness and reliability means
positive attributes as an indication of an
individual’s background and character
demonstrating a high level of
confidence that the individual can be
properly authorized to have access to
and handle Safeguards Information and
Safeguards Information—Modified
Handling.
*
*
*
*
*
36. Section 73.21 is revised to read as
follows:
§ 73.21 Protection of Safeguards
Information: Performance Requirements.
(a) General performance requirement.
(1) Each licensee, applicant, or other
person who produces, receives, or
acquires Safeguards Information shall
ensure that it is protected against
unauthorized disclosure. To meet this
general performance requirement, such
licensees, applicants, or other persons
subject to this section shall:
(i) For Safeguards Information related
to power reactors, licensees authorized
to possess a formula quantity of strategic
special nuclear material, transportation
of or delivery to a carrier for
transportation of a formula quantity of
strategic special nuclear material or
more than 100 grams of irradiated
reactor fuel, and fuel cycle facilities
required to implement security
measures, establish, implement and
maintain an information protection
system that includes the applicable
measures specified in § 73.22.
(ii) For Safeguards Information related
to certain quantities of source and
byproduct material and special nuclear
material of moderate or low strategic
significance, establish, implement, and
maintain an information protection
system that includes the measures
specified in § 73.23.
(2) Information protection procedures
employed by State and local police
forces are deemed to meet the general
performance requirement in
§ 73.21(a)(i).
(b) Commission Authority. Pursuant
to section 147 of the Atomic Energy Act
of 1954, as amended, (42 U.S.C. 2167),
the Commission may impose, by order
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or regulation, Safeguards Information
handling requirements different from
those specified in § 73.21(a)(1) and (2)
on any person who produces, receives,
or acquires Safeguards Information.
37. Section 73.22 is added to read as
follows:
§ 73.22 Protection of Safeguards
Information: Specific Requirements.
This section contains specific
requirements for the protection of
Safeguards Information related to power
reactors, licensees authorized to possess
a formula quantity of strategic special
nuclear material, transportation of or
delivery to a carrier for transportation of
a formula quantity of strategic special
nuclear material or more than 100 grams
of irradiated reactor fuel, and fuel cycle
facilities.
(a) Information to be protected. The
types of information and documents
that must be protected as Safeguards
Information include security-related
requirements such as protective
measures, interim compensatory
measures, additional security measures,
and the following, as applicable:
(1) Physical Protection at fixed sites.
Information not otherwise classified as
Restricted Data or National Security
Information relating to the protection of
power reactors, transportation of or
delivery to a carrier for transportation of
a formula quantity of strategic special
nuclear material, spent irradiated fuel in
excess of 100 grams, and licensees
authorized to possess a formula quantity
of strategic nuclear material, including:
(i) All portions of the composite
physical security plan for the facility or
site.
(ii) Site specific drawings, diagrams,
sketches, or maps that substantially
represent the final design features of the
physical security system.
(iii) Alarm system layouts showing
the location of intrusion detection
devices, alarm assessment equipment,
alarm system wiring, emergency power
sources, and duress alarms.
(iv) Written physical security orders
and procedures for members of the
security organization, duress codes, and
patrol schedules.
(v) On-site and off-site
communications systems in regard to
their use for security purposes.
(vi) Lock combinations, mechanical
key design, or passwords integral to the
physical security system.
(vii) Documents and other matter that
contain lists or locations of certain
safety-related equipment explicitly
identified in the documents as vital for
purposes of physical protection, as
contained in physical security plans,
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safeguards contingency plans, or plant
specific safeguards analyses.
(viii) All portions of the composite
safeguards contingency plan for the
facility or site.
(ix) All portions of the composite
facility guard qualification and training
plan disclosing features of the physical
security system or response procedures.
(x) Information concerning onsite or
offsite response forces, including size,
identity, armament, and arrival times of
such forces committed to respond to
safeguards or security emergencies.
(xi) The elements and characteristics
of the Design Basis Threat in a level of
detail greater than as specified in § 73.1
or other information that would disclose
the Design Basis Threat, including the
tactics and capabilities required to
defend against that threat.
(xii) Engineering and safety analyses,
emergency planning procedures or
scenarios, and other information related
to the physical protection of the facility
or materials if the unauthorized
disclosure of such information could
reasonably be expected to have a
significant adverse effect on the health
and safety of the public or the common
defense and security by significantly
increasing the likelihood of theft,
diversion, or sabotage of material or a
facility.
(xiii) Information required by the
Commission pursuant to 10 CFR
73.55(c)(8) and (9).
(2) Physical protection in transit.
Information not otherwise classified as
Restricted Data or National Security
Information related to the protection of
transportation of, or delivery to a carrier
for transportation of a formula quantity
of strategic special nuclear material or
more than 100 grams of irradiated
reactor fuel, including:
(i) All portions of the composite
transportation physical security plan.
(ii) Schedules and itineraries for
specific shipments. (Routes and
quantities for shipments of spent fuel
are not withheld from public disclosure.
Schedules for spent fuel shipments may
be released 10 days after the last
shipment of a current series.)
(iii) Vehicle immobilization features,
intrusion alarm devices, and
communications systems.
(iv) Arrangements with and
capabilities of local police response
forces, and locations of safe havens.
(v) Limitations of communications
during transport.
(vi) Procedures for response to
safeguards or security emergencies.
(vii) Information concerning the
tactics and capabilities required to
defend against attempted radiological
sabotage, or theft and diversion of
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formula quantities of special nuclear
material, or related information.
(viii) Engineering or safety analyses,
emergency planning procedures or
scenarios related to the protection of the
transported material if the unauthorized
disclosure of such information could
reasonably be expected to have a
significant adverse effect on the health
and safety of the public or the common
defense and security by significantly
increasing the likelihood of theft,
diversion, or sabotage of such material.
(3) Inspections, audits and
evaluations. Information not otherwise
classified as National Security
Information or Restricted Data
pertaining to inspections and reports
that could affect the specific
requirements for Safeguards Information
related to power reactors, licensees
authorized to possess a formula quantity
of strategic special nuclear material,
transportation of or delivery to a carrier
for transportation of a formula quantity
of strategic special nuclear material or
more than 100 grams of irradiated
reactor fuel, and fuel cycle facilities
required to implement security
measures including:
(i) Portions of inspection reports,
evaluations, audits, or investigations
that contain details of a licensee’s or
applicant’s physical security system or
that disclose uncorrected defects,
weaknesses, or vulnerabilities in the
system.
(ii) Reports of investigations
containing general information may be
released after the investigation has been
completed, unless withheld pursuant to
other authorities, e.g., the Freedom of
Information Act (5 U.S.C. 552).
(4) Correspondence. Portions of
correspondence insofar as they contain
Safeguards Information as defined in
paragraphs (a)(1) through (a)(3) of this
paragraph.
(5) Other information that the
Commission determines by order or
regulation could reasonably be expected
to have a significant adverse effect on
the health and safety of the public or the
common defense and security by
significantly increasing the likelihood of
theft, diversion, or sabotage of material
or a facility.
(b) Conditions for access. (1) Except as
the Commission may otherwise
authorize, no person may have access to
Safeguards Information unless the
person has an established ‘‘need to
know’’ for the information and is:
(i) An employee, agent, or contractor
of an applicant, a licensee, the
Commission, or the Executive Branch of
the United States Government.
However,
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(A) An individual to be authorized
access to Safeguards Information by a
nuclear power reactor applicant or
licensee must demonstrate
trustworthiness and reliability and
undergo a Federal Bureau of
Investigation criminal history check to
the extent required by 10 CFR 73.57
prior to such access;
(B) Other individuals to be authorized
access to Safeguards Information by an
applicant or licensee covered by this
section must demonstrate
trustworthiness and reliability through a
comprehensive background check or
other means as approved by the
Commission prior to such access;
(ii) A member of Congress;
(iii) The Governor of a State or
designated representatives;
(iv) Representatives of the
International Atomic Energy Agency
(IAEA) engaged in activities associated
with the U.S./IAEA Safeguards
Agreement who has been certified by
the NRC;
(v) Employees of a state or local law
enforcement authority that are
responsible for responding to requests
for assistance during safeguards or
security emergencies;
(vi) State Radiation Control Program
Directors and State Homeland Security
Advisors or their designated
representatives; or
(vii) An individual to whom
disclosure is ordered pursuant to
§ 2.709(f) of this chapter.
(2) The individuals described in
(b)(1)(ii) through (vi) of this section are
deemed to be trustworthy and reliable
by virtue of their occupational status.
For non-governmental individuals in
(b)(1)(i) and (vii) of this section, a
determination of trustworthiness and
reliability is required.
(3) Except as the Commission may
otherwise authorize, no person may
disclose Safeguards Information to any
other person except as set forth in
paragraph (b)(1) of this section.
(c) Protection while in use or storage.
(1) While in use, matter containing
Safeguards Information must be under
the control of an individual authorized
access to Safeguards Information. This
requirement is satisfied if the
Safeguards Information is attended by
such an individual even though the
information is in fact not constantly
being used. Safeguards Information
within alarm stations, continuously
manned guard posts or ready rooms
need not be locked in a locked security
storage container.
(2) While unattended, Safeguards
Information must be stored in a locked
security storage container. The
container may not identify the contents
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of the matter contained and must
preclude access by individuals not
authorized access in accordance with
the provisions of this section.
Knowledge of lock combinations
protecting Safeguards Information must
be limited to a minimum number of
personnel for operating purposes who
have a ‘‘need to know’’ and are
otherwise authorized access to
Safeguards Information in accordance
with the provisions of this Part. Access
to lock combinations must be strictly
controlled so as to prevent disclosure to
an unauthorized individual not
authorized access to Safeguards
Information.
(d) Preparation and marking of
documents or other matter. (1) Each
document or other matter that contains
Safeguards Information as described in
§ 73.21(a)(1)(i) and this section must be
marked ‘‘Safeguards Information’’ in a
conspicuous manner on the top and
bottom of each page to indicate the
presence of protected information. The
first page of each document must also
contain:
(i) The name, title, and organization of
the individual authorized to make a
Safeguards Information determination,
and who has determined that the
document contains Safeguards
Information;
(ii) The date the determination was
made; and
(iii) An indication that unauthorized
disclosure would be subject to civil and
criminal sanctions.
(2) In addition to the ‘‘Safeguards
Information’’ markings at the top and
bottom of each page, transmittal letters
or memoranda which do not in
themselves contain Safeguards
Information shall be marked to indicate
that attachments or enclosures contain
Safeguards Information but that the
transmittal document does not (e.g.,
‘‘When separated from Safeguards
Information enclosure(s), this document
is decontrolled).
(3) Any transmittal document
forwarding Safeguards Information must
alert the recipient that protected
information is enclosed. Certification
that a document or other media contains
Safeguards Information must include
the name and title of the certifying
official and date designated. Portion
marking of documents or other
information is required for
correspondence to and from the NRC.
The portion marking must be sufficient
to allow the recipient to identify and
distinguish those sections of the
document or other information
containing the Safeguards Information
from non-Safeguards Information.
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(4) Documents and other matter
containing Safeguards Information in
the hands of contractors and agents of
licensees that were produced more than
one year prior to the effective date of
this amendment need not be marked
unless they are removed from storage
containers for use.
(5) The marking ‘‘SGI’’ must be used
for Safeguards Information designated
as such for the protection of facilities
and material covered by 10 CFR 73.22.
(e) Reproduction of matter containing
Safeguards Information. Safeguards
Information may be reproduced to the
minimum extent necessary consistent
with need without permission of the
originator. If Safeguards Information is
reproduced on a digital copier that
would retain Safeguards Information in
its memory, then the copier may not be
connected to a network.
(f) External transmission of
documents and material. (1) Documents
or other matter containing Safeguards
Information, when transmitted outside
an authorized place of use or storage,
must be packaged in two sealed
envelopes or wrappers to preclude
disclosure of the presence of protected
information. The inner envelope or
wrapper must contain the name and
address of the intended recipient and be
marked on both sides, top and bottom,
with the words ‘‘Safeguards
Information.’’ The outer envelope or
wrapper must be opaque, addressed to
the intended recipient, must contain the
address of the sender, and may not bear
any markings or indication that the
document contains Safeguards
Information.
(2) Safeguards Information may be
transported by any commercial delivery
company that provides nationwide
overnight service with computer
tracking features, U.S. first class,
registered, express, or certified mail, or
by any individual authorized access
pursuant to these requirements.
(3) Except under emergency or
extraordinary conditions, Safeguards
Information must be transmitted
electronically only by protected
telecommunications circuits (including
facsimile) or encryption (Federal
Information Processing Standard [FIPS]
140–2) approved by the appropriate
NRC office. For the purpose of this
section, emergency or extraordinary
conditions are defined as any
circumstances that require immediate
communications in order to report,
summon assistance for, or respond to a
safeguards or security event or an event
that has potential security significance.
Physical security events required to be
reported pursuant to § 73.71 are
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considered to be extraordinary
conditions.
(g) Processing of Safeguards
Information on electronic systems. (1)
Safeguards Information may be stored,
processed or produced on a stand-alone
computer (or computer system) for
processing of Safeguards Information.
‘‘Stand-alone’’ means a computer or
computer system to which access is
limited to individuals authorized access
to Safeguards Information. A standalone computer or computer system
may not be physically or in any other
way connected to a network accessible
by users who are not authorized access
to Safeguards Information.
(2) Each computer not located within
an approved and lockable security
storage container that is used to process
Safeguards Information must have a
removable storage medium with a
bootable operating system. The bootable
operating system must be used to load
and initialize the computer. The
removable storage medium must also
contain the software application
programs, and all data must be
processed and saved on the same
removable storage medium. The
removable storage medium must be
secured in a locked security storage
container when not in use.
(3) A mobile device (such as a laptop
computer) may also be used for the
automated processing of Safeguards
Information provided the device is
secured in a locked security storage
container when not in use. Other
systems may be used if approved for
security by the appropriate NRC office.
(h) Removal from Safeguards
Information category. Documents
originally containing Safeguards
Information must be removed from the
Safeguards Information category
whenever the information no longer
meets the criteria contained in this part.
Care must be exercised to ensure that
any document decontrolled not disclose
Safeguards Information in some other
form or be combined with other
unprotected information to disclose
Safeguards Information. The authority
to determine that a document may be
decontrolled shall be exercised only by
the NRC or with NRC approval, or in
consultation with the individual or
organization that made the original
determination, if possible.
(i) Destruction of matter containing
Safeguards Information. Documents or
other media containing Safeguards
Information must be destroyed when no
longer needed. The information can be
destroyed by tearing into small pieces,
burning, shredding or any other method
that precludes reconstruction by means
available to the public at large. Piece
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sizes one half inch or smaller composed
of several pages or documents and
thoroughly mixed would be considered
completely destroyed.
38. Section 73.23 is added to read as
follows:
§ 73.23 Protection of Safeguards
Information-Modified Handling: Specific
Requirements.
This section contains specific
requirements for the protection of
Safeguards Information related to
certain quantities of source and
byproduct material and special nuclear
material of moderate or low strategic
significance, except for those materials
covered under § 73.22. The
requirements of this section distinguish
Safeguards Information requiring
modified protection requirements (SGIM) from Safeguards Information for
facilities and materials needing a higher
level of protection, as set forth in
§ 73.22.
(a) Information to be protected. The
types of information and documents
that must be protected as Safeguards
Information include security-related
requirements such as protective
measures, interim compensatory
measures, additional security measures,
and the following, as applicable:
(1) Physical Protection at fixed sites.
Information not otherwise classified as
Restricted Data or National Security
Information relating to source material,
byproduct material, special nuclear
material of moderate strategic
significance, or special nuclear material
of low strategic significance, in
quantities determined by the
Commission through order or regulation
to be significant to the public health and
safety or the common defense and
security, including:
(i) All portions of the composite
physical security plan for the facility or
site.
(ii) Site specific drawings, diagrams,
sketches, or maps that substantially
represent the final design features of the
physical security system.
(iii) Alarm system layouts showing
location of intrusion detection devices,
alarm assessment equipment, alarm
system wiring, emergency power
sources, and duress alarms.
(iv) Written physical security orders
and procedures for members of the
security organization, duress codes, and
patrol schedules.
(v) On-site and off-site
communications systems in regard to
their use for security purposes.
(vi) Lock combinations, mechanical
key design, or passwords integral to the
physical security system.
(vii) Facility guard qualification and
training procedures disclosing features
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of the physical security system or
response procedures.
(viii) Descriptions of security
activities which disclose features of the
physical security system or response
measures.
(ix) Information concerning offsite
response forces, including size, identity,
armament, and arrival times of such
forces committed to respond to
safeguards or security emergencies.
(x) Engineering and safety analyses,
emergency planning procedures or
scenarios, and other information related
to the physical protection of the facility
or materials if the unauthorized
disclosure of such information could
reasonably be expected to have a
significant adverse effect on the health
and safety of the public or the common
defense and security by significantly
increasing the likelihood of theft,
diversion, or sabotage of material or a
facility.
(2) Physical protection in transit.
Information not otherwise classified as
Restricted Data or National Security
Information related to the protection of
shipments of certain quantities of source
material and byproduct material and
special nuclear material of moderate or
low strategic significance, except for
those materials covered under § 73.22,
and in quantities determined by the
Commission through order or regulation
to be significant to the public health and
safety or the common defense and
security, including:
(i) Information regarding security
features of a transportation physical
security plan (Scheduling and itinerary
information may be shared with others
on a ‘‘need to know’’ basis and is not
designated as Safeguards InformationModified Handling).
(ii) Arrangements with and
capabilities of local police response
forces, and locations of safe havens.
(iii) Limitations of communications
during transport.
(iv) Procedures for response to
safeguards or security emergencies.
(v) Engineering or safety analyses,
emergency planning procedures or
scenarios related to the protection of the
transported material if the unauthorized
disclosure of such information could
reasonably be expected to have a
significant adverse effect on the health
and safety of the public or the common
defense and security by significantly
increasing the likelihood of theft,
diversion, or sabotage of such material.
(3) Inspections, audits and
evaluations. Information not otherwise
classified as National Security
Information or Restricted Data relating
to inspections and reports, such as:
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(i) Portions of inspection reports,
evaluations, audits, or investigations
that contain details of a licensee’s or
applicant’s physical security system or
that disclose uncorrected defects,
weaknesses, or vulnerabilities in the
system.
(ii) Reports of investigations
containing general information may be
released after the investigation has been
completed, unless withheld pursuant to
other authorities, e.g., the Freedom of
Information Act (5 U.S.C. 552).
(4) Correspondence. Portions of
correspondence insofar as they contain
Safeguards Information, including the
information in paragraphs (a)(1) through
(a)(3) of this section.
(5) Other information that the
Commission determines by order or
regulation could reasonably be expected
to have a significant adverse effect on
the health and safety of the public or the
common defense and security by
significantly increasing the likelihood of
theft, diversion, or sabotage of material
or a facility.
(b) Conditions for access. (1) Except as
the Commission may otherwise
authorize, no person may have access to
Safeguards Information unless the
person has an established ‘‘need to
know’’ for the information and is:
(i) An employee, agent, or contractor
of an applicant, a licensee, the
Commission, or the Executive Branch of
the United States Government.
Individuals authorized access to
Safeguards Information by a source,
byproduct, or special nuclear material
applicant or licensee must demonstrate
trustworthiness and reliability through a
comprehensive background check or
other means as approved by the
Commission prior to such access;
(ii) A member of Congress;
(iii) The Governor of a State or
designated representatives;
(iv) Representatives of the
International Atomic Energy Agency
(IAEA) engaged in activities associated
with the U.S./IAEA Safeguards
Agreement who has been certified by
the NRC;
(v) Employees of a state or local law
enforcement authority that are
responsible for responding to requests
for assistance during safeguards or
security emergencies;
(vi) State Radiation Control Program
Directors and State Homeland Security
Advisors or their designated
representatives; or
(vii) An individual to whom
disclosure is ordered pursuant to
§ 2.709(f) of this chapter.
(2) The individuals described in
paragraph (b)(1)(ii) through (vi) of this
section are deemed to be trustworthy
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and reliable by virtue of their
occupational status. For nongovernmental individuals in (b)(1)(i)
and (vii) of this section, a determination
of trustworthiness and reliability is
required.
(3) Except as the Commission may
otherwise authorize, no person may
disclose Safeguards Information to any
other person except as set forth in
paragraph (b)(1) of this section.
(c) Protection while in use or storage.
(1) While in use, matter containing
Safeguards Information must be under
the control of an individual authorized
access to such information. This
requirement is satisfied if the
Safeguards Information is attended by
such an individual even though the
information is in fact not constantly
being used. Safeguards Information
within alarm stations, continuously
manned guard posts or ready rooms
need not be locked in a file drawer or
cabinet.
(2) While unattended, Safeguards
Information must be stored in a locked
file drawer or cabinet. The container
may not identify the contents of the
matter contained and must preclude
access by individuals not authorized
access in accordance with the
provisions of this section. Knowledge of
lock combinations or access to keys
protecting Safeguards Information must
be limited to a minimum number of
personnel for operating purposes who
have a ‘‘need to know’’ and are
otherwise authorized access to
Safeguards Information in accordance
with the provisions of this Part. Access
to lock combinations must be strictly
controlled so as to prevent disclosure to
an individual not authorized access to
Safeguards Information.
(d) Preparation and marking of
documents or other matter. (1) Each
document or other matter that contains
Safeguards Information as described in
§ 73.23(a) and in this section must be
marked ‘‘SGI—Modified Handling’’ in a
conspicuous manner on the top and
bottom of each page to indicate the
presence of protected information. The
first page of the document must also
contain:
(i) The name, title, and organization of
the individual authorized to make a
Safeguards Information—Modified
Handling safeguards information
designation, and who has determined
that the document contains Safeguards
Information;
(ii) The date the determination was
made; and
(iii) An indication that unauthorized
disclosure would be subject to civil and
criminal sanctions.
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(2) In addition to the ‘‘SGI—Modified
Handling’’’ markings at the top and
bottom of each page, transmittal letters
or memoranda which do not in
themselves contain Safeguards
Information must be marked to indicate
that attachments or enclosures contain
Safeguards Information but that the
transmittal does not (e.g., ‘‘When
separated from Safeguards
Information—Modified Handling
enclosure(s), this document is
decontrolled’’).
(3) Any transmittal document
forwarding Safeguards Information must
alert the recipient that protected
information is enclosed. Certification
that a document or other media contains
Safeguards Information must include
the name and title of the certifying
official and date designated. Portion
marking of documents or other
information is required for
correspondence to and from the NRC.
The portion marking must be sufficient
to allow the recipient to identify and
distinguish those sections of the
document or other information
containing the Safeguards Information
from non-Safeguards Information.
Documents and other matter containing
Safeguards Information in the hands of
contractors and agents of licensees that
were produced more than one year prior
to the effective date of this amendment
need not be marked unless they are
removed from storage containers for use.
(e) Reproduction of matter containing
Safeguards Information. Safeguards
Information may be reproduced to the
minimum extent necessary, consistent
with need, without permission of the
originator. If Safeguards Information is
reproduced on a digital copier that
would retain Safeguards Information in
its memory, then the copier may not be
connected to a network.
(f) External transmission of
documents and material. (1) Documents
or other matter containing Safeguards
Information, when transmitted outside
an authorized place of use or storage,
must be packaged in two sealed
envelopes or wrappers to preclude
disclosure of the presence of protected
information. The inner envelope or
wrapper must contain the name and
address of the intended recipient and be
marked on both sides, top and bottom,
with the words ‘‘SGI—Modified
Handling.’’ The outer envelope or
wrapper must be opaque, addressed to
the intended recipient, must contain the
address of the sender, and must not bear
any markings or indication that the
document contains Safeguards
Information.
(2) Safeguards Information may be
transported by any commercial delivery
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company that provides nationwide
overnight service with computer
tracking features, U.S. first class,
registered, express, or certified mail, or
by any individual authorized access
pursuant to these requirements.
(3) Except under emergency or
extraordinary conditions, Safeguards
Information must be transmitted
electronically only by protected
telecommunications circuits (including
facsimile) or encryption (Federal
Information Processing Standard [FIPS]
140–2) approved by the appropriate
NRC office. For the purpose of this
section, emergency or extraordinary
conditions are defined as any
circumstances that require immediate
communications in order to report,
summon assistance for, or respond to a
security event or an event that has
potential security significance. Physical
security events required to be reported
pursuant to § 73.71 are considered to be
extraordinary conditions.
(g) Processing of Safeguards
Information on electronic systems. (1)
Safeguards Information designated for
modified handling may be stored,
processed or produced on a computer or
computer system, provided that the
system is assigned to the licensee’s or
contractor’s facility. Each file containing
Safeguards Information must be
protected, either by a password or
encryption, to prevent unauthorized
individuals from gaining access. Word
processors such as typewriters are not
subject to these requirements as long as
they do not transmit information offsite. (Note: if Safeguards Information is
produced on a typewriter, the ribbon
must be removed and stored in the same
manner as other Safeguards Information
or media.)
(2) Safeguards Information files may
be transmitted over a network if the file
is encrypted. In such cases, the licensee
will select a commercially available
encryption system that the National
Institute of Standards and Technology
(NIST) has validated as conforming to
Federal Information Processing
Standards (FIPS). Safeguards
Information files shall be properly
labeled as ‘‘SGI-Modified Handling’’
and saved to removable media and
stored in a locked file drawer or cabinet.
(3) A mobile device (such as a laptop
computer) may also be used for the
automated processing of Safeguards
Information provided the device is
secured in an appropriate locked storage
container when not in use. Other
systems may be used if approved for
security by the appropriate NRC office.
(h) Removal from Safeguards
Information category. Documents
originally containing Safeguards
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Information must be removed from the
Safeguards Information category
whenever the information no longer
meets the criteria contained in this part.
Care must be exercised to ensure that
any document decontrolled shall not
disclose Safeguards Information in some
other form or be combined with other
unprotected information to disclose
Safeguards Information. The authority
to determine that a document may be
decontrolled must be exercised only by
the NRC or with NRC approval or in
consultation with the individual or
organization that made the original
determination, if possible.
(i) Destruction of matter containing
Safeguards Information. Documents or
other media containing Safeguards
Information shall be destroyed when no
longer needed. The information can be
destroyed by tearing into small pieces,
burning, shredding or any other method
that precludes reconstruction by means
available to the public at large. Piece
sizes one half inch or smaller composed
of several pages or documents and
thoroughly mixed would be considered
completely destroyed.
39. In § 73.57 paragraphs (b)(2)(i) and
(ii) are revised to read as follows:
§ 73.57 Requirements for criminal history
checks of individuals granted unescorted
access to a nuclear power facility or access
to Safeguards Information by power reactor
licensees.
*
*
*
*
*
(b) * * *
(2) * * *
(i) For unescorted access to the
nuclear power facility or for access to
Safeguards Information (but must
adhere to provisions contained in
§§ 73.21 and 73.22): NRC employees
and NRC contractors on official agency
business; individuals responding to a
site emergency in accordance with the
provisions of § 73.55(a); a representative
of the International Atomic Energy
Agency (IAEA) engaged in activities
associated with the U.S./IAEA
Safeguards Agreement at designated
facilities who has been certified by the
NRC; law enforcement personnel acting
in an official capacity; State or local
government employees who have had
equivalent reviews of FBI criminal
history data; and individuals employed
at a facility who possess ‘‘Q’’ or ‘‘L’’
clearances or possess another active
government granted security clearance,
i.e., Top Secret, Secret, or Confidential;
(ii) For access to Safeguards
Information only but must adhere to
provisions contained in §§ 73.21 and
73.22: Employees of other agencies of
the United States Government; a
member of the Congress; the Governor
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of a State or his or her designated
representatives; individuals to whom
disclosure is ordered pursuant to
§ 2.709(f) of this chapter;
*
*
*
*
*
PART 76—CERTIFICATION OF
GASEOUS DIFFUSION PLANTS
40. The authority citation for part 76
continues to read as follows:
Authority: Secs. 161, 68 Stat. 948, as
amended, secs. 1312, 1701, as amended, 106
Stat. 2932, 2951, 2952, 2953, 110 Stat. 1321–
349 (42 U.S.C. 2201, 2297b–11, 2297f); secs.
201, as amended, 204, 206, 88 Stat. 1244,
1245, 1246 (42 U.S.C. 5841, 5842, 5845,
5846). Sec 234(a), 83 Stat. 444, as amended
by Pub. L. 104–134, 110 Stat. 1321, 1321–349
(42 U.S.C. 2243(a)); sec. 1704, 112 Stat. 2750
(44 U.S.C. 3504 note). Sec. 76.7 also issued
under Pub. L. 95–601. sec. 10, 92 Stat 2951
(42 U.S.C. 5851). Sec. 76.22 is also issued
under sec. 193(f), as amended, 104 Stat. 2835,
as amended by Pub. L. 104–134, 110 Stat.
1321, 1321–349 (42 U.S.C. 2243(f)). Sec.
76.35(j) also issued under sec. 122, 68 Stat.
939 (42 U.S.C. 2152).
41. In § 76.113, paragraph (c) is
revised to read as follows:
§ 76.113 Formula quantities of strategic
special nuclear material—Category I.
*
*
*
*
*
(c) The requirements for the
protection of Safeguards Information
pertaining to formula quantities of
strategic special nuclear material
(Category I) are contained in §§ 73.21
and 73.22 of this chapter. Information
designated by the U.S. Department of
Energy as Unclassified Controlled
Nuclear Information must be protected
at a level equivalent to that accorded
Safeguards Information.
*
*
*
*
*
42. In § 76.115, paragraph (d) is added
to read as follows:
§ 76.115 Special nuclear material of
moderate strategic significance—Category
II.
*
*
*
*
*
(d) The requirements for the
protection of Safeguards Information
pertaining to special nuclear material of
moderate strategic significance—
Category II are contained in §§ 73.21
and 73.22 of this chapter.
43. In § 76.117, paragraph (c) is added
to read as follows:
§ 76.117 Special nuclear material of low
strategic significance—Category III.
*
*
*
*
*
(c) The requirements for the
protection of Safeguards Information
pertaining to special nuclear material of
low strategic significance-Category III
are contained in §§ 73.21 and 73.22 of
this chapter.
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PART 150—EXEMPTIONS AND
CONTINUED REGULATORY
AUTHORITY IN AGREEMENT STATES
AND IN OFFSHORE WATERS UNDER
SECTION 274
44. The authority citation for part 150
continues to read as follows:
Authority: Sec. 161, 68 Stat. 948, as
amended, sec. 274, 73 Stat. 688 (42 U.S.C.
2201, 2021); sec. 201, 88 Stat. 1242, as
amended (42 U.S.C. 5841); sec. 1704, 112
Stat. 2750 (44 U.S.C. 3504 note). Sections
150.3, 150.15, 150.15a, 150.31, 150.32 also
issued under secs. 11e(2), 81, 68 Stat. 923,
935, as amended, secs. 83, 84, 92 Stat. 3033,
3039 (42 U.S.C. 2014e(2), 2111, 2113, 2114).
Section 150.14 also issued under sec. 53, 68
Stat. 930, as amended (42 U.S.C. 2073).
Section 150.15 also issued under secs. 135,
141, Pub. L. 97–425, 96 Stat. 2232, 2241 (42
U.S.C. 10155, 10161). Section 150.17a also
issued under sec. 122, 68 Stat. 939 (42 U.S.C.
2152). Section 150.30 also issued under sec.
234, 83 Stat. 444 (42 U.S.C. 2282).
45. In § 150.15, paragraph (a)(9) is
added to read as follows:
§ 150.15
Persons not exempt.
*
*
*
*
*
(a) * * *
(9) The requirements for the
protection Safeguards Information in
§§ 73.21 and 73.23 of this chapter.
*
*
*
*
*
Dated at Rockville, Maryland this 7th day
of February 2005.
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. 05–2665 Filed 2–10–05; 8:45 am]
BILLING CODE 7590–01–P
DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 39
[Docket No. FAA–2004–20006; Directorate
Identifier 2004–CE–49–AD]
RIN 2120–AA64
Airworthiness Directives; Pilatus
Aircraft Limited Models B4–PC11, B4–
PC11A, and B4–PC11AF Sailplanes
Federal Aviation
Administration (FAA), DOT.
ACTION: Notice of proposed rulemaking
(NPRM).
AGENCY:
SUMMARY: The FAA proposes to adopt a
new airworthiness directive (AD) for all
Pilatus Aircraft Limited (Pilatus) Models
B4–PC11, B4–PC11A, and B4–PC11AF
sailplanes. This proposed AD would
require you to repetitively inspect the
control-column support for cracks and,
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if any cracks are found, replace the
control-column support with a new
support. This proposed AD results from
mandatory continuing airworthiness
information (MCAI) issued by the
airworthiness authority for Switzerland.
We are issuing this proposed AD to
detect and correct cracks in the controlcolumn support, which could result in
failure of the support. This failure could
lead to loss of the primary flight control
system.
DATES: We must receive any comments
on this proposed AD by March 18, 2005.
ADDRESSES: Use one of the following to
submit comments on this proposed AD:
• DOT Docket Web site: Go to
https://dms.dot.gov and follow the
instructions for sending your comments
electronically.
• Government-wide rulemaking Web
site: Go to https://www.regulations.gov
and follow the instructions for sending
your comments electronically.
• Mail: Docket Management Facility;
U.S. Department of Transportation, 400
Seventh Street, SW., Nassif Building,
Room PL–401, Washington, DC 20590–
001.
• Fax: 1–202–493–2251.
• Hand Delivery: Room PL–401 on
the plaza level of the Nassif Building,
400 Seventh Street, SW., Washington,
DC, between 9 a.m. and 5 p.m., Monday
through Friday, except Federal holidays.
To get the service information
identified in this proposed AD, contact
Pilatus Aircraft Ltd., Customer Liaison
Manager, CH–6371 Stans, Switzerland;
telephone: +41 41 619 6208; facsimile:
+41 41 619 7311; e-mail:
fodermatt@pilatus-aircraft.com or from
Pilatus Business Aircraft Ltd., Product
Support Department, 11755 Airport
Way, Broomfield, Colorado 80021;
telephone: (303) 465–9099; facsimile:
(303) 465–6040.
To view the comments to this
proposed AD, go to https://dms.dot.gov.
This is docket number FAA–2004–
20006.
FOR FURTHER INFORMATION CONTACT:
Doug Rudolph, Aerospace Engineer,
FAA, Small Airplane Directorate, 901
Locust, Room 301, Kansas City,
Missouri 64106; telephone: (816) 329–
4059; facsimile: (816) 329–4090.
SUPPLEMENTARY INFORMATION:
Comments Invited
How do I comment on this proposed
AD? We invite you to submit any
written relevant data, views, or
arguments regarding this proposal. Send
your comments to an address listed
under ADDRESSES. Include the docket
number, ‘‘FAA–2004–20006; Directorate
Identifier 2004–CE–49–AD’’ at the
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7217
beginning of your comments. We will
post all comments we receive, without
change, to https://dms.dot.gov, including
any personal information you provide.
We will also post a report summarizing
each substantive verbal contact with
FAA personnel concerning this
proposed rulemaking. Using the search
function of our docket Web site, anyone
can find and read the comments
received into any of our dockets,
including the name of the individual
who sent the comment (or signed the
comment on behalf of an association,
business, labor union, etc.). This is
docket number FAA–2004–20006. You
may review the DOT’s complete Privacy
Act Statement in the Federal Register
published on April 11, 2000 (65 FR
19477–78) or you may visit https://
dms.dot.gov.
Are there any specific portions of this
proposed AD I should pay attention to?
We specifically invite comments on the
overall regulatory, economic,
environmental, and energy aspects of
this proposed AD. If you contact us
through a nonwritten communication
and that contact relates to a substantive
part of this proposed AD, we will
summarize the contact and place the
summary in the docket. We will
consider all comments received by the
closing date and may amend this
proposed AD in light of those comments
and contacts.
Docket Information
Where can I go to view the docket
information? You may view the AD
docket that contains the proposal, any
comments received, and any final
disposition in person at the DMS Docket
Offices between 9 a.m. and 5 p.m.
(eastern standard time), Monday
through Friday, except Federal holidays.
The Docket Office (telephone 1–800–
647–5227) is located on the plaza level
of the Department of Transportation
Nassif Building at the street address
stated in ADDRESSES. You may also view
the AD docket on the Internet at
https://dms.dot.gov. The comments will
be available in the AD docket shortly
after the DMS receives them.
Discussion
What events have caused this
proposed AD? The Federal Office for
Civil Aviation (FOCA), which is the
airworthiness authority for Switzerland,
recently notified FAA that an unsafe
condition may exist on all Pilatus
Aircraft Limited (Pilatus) Models B4–
PC11, B4–PC11A, and B4–PC11AF
sailplanes. The FOCA reports nine
occurrences of cracks in the support of
the control-column (part number (P/N)
112.35.11.072).
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Agencies
[Federal Register Volume 70, Number 28 (Friday, February 11, 2005)]
[Proposed Rules]
[Pages 7196-7217]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 05-2665]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Parts 2, 30, 40, 50, 52, 60, 63, 70, 71, 72, 73, 76 and 150
RIN: 3150-AH57
Protection of Safeguards Information
AGENCY: Nuclear Regulatory Commission.
ACTION: Proposed rule.
-----------------------------------------------------------------------
SUMMARY: The Nuclear Regulatory Commission (NRC) is proposing to amend
its regulations for the protection of Safeguards Information (SGI) to
protect SGI from inadvertent release and unauthorized disclosure which
might compromise the security of nuclear facilities and materials. The
proposed amendments are consistent with recent Commission practices
reflected in orders and threat advisories, issued since September 11,
2001. The proposed amendments would affect certain licensees,
information, and materials not currently specified in the regulations,
but which are within the scope of Commission authority under the Atomic
Energy Act of 1954, as amended (AEA).
DATES: The comment period expires March 28, 2005. Submit comments
specific to the information collections aspects of this rule March 14,
2005. Comments received after that date will be considered if it is
practical to do so, but the NRC is able to ensure consideration only
for comments received on or before this date.
ADDRESSES: You may submit comments by any one of the following methods.
Please include the following number (RIN 3150-AH57) in the subject line
of your comments. Comments on this rulemaking 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 personal
information such as social security numbers and birth dates in your
submission.
Mail comments to: Secretary, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, Attn: Rulemakings and Adjudications Staff.
E-mail comments to: SECY@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. You may also submit comments via the NRC's
rulemaking Web site at https://ruleforum.llnl.gov. Address questions
about our rulemaking Web site to Carol Gallagher at (301) 415-5905; e-
mail cag@nrc.gov. Comments can also be submitted via the Federal
Rulemaking Portal https://www.regulations.gov.
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. Publicly available documents related to this rulemaking
may be examined and copied for a fee at the NRC's Public Document Room
(PDR), Public File Area O1F21, One White Flint North, 11555 Rockville
Pike, Rockville, Maryland. Selected documents, including comments, can
be reviewed and downloaded electronically via the NRC rulemaking Web
site at https://ruleforum.llnl.gov.
You may submit comments on the information collections by the
methods indicated in the Paperwork Reduction Act Statement.
Publicly available documents created or received at the NRC after
November 1, 1999, are available electronically at the NRC's Electronic
Reading Room at https://www.nrc.gov/NRC/ADAMS/. From this
site, the public can gain entry into the NRC's Agencywide Document
Access and Management System (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 1-800-397-4209, 301-415-4737
or by e-mail to pdr@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Marjorie Rothschild, Office of the
General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone (301) 415-1633, e-mail MUR@nrc.gov or Bernard
Stapleton, Office of Nuclear Security and Incident Response, Nuclear
Regulatory Commission, Washington, DC 20555-0001, (301) 415-2432, e-
mail BWS2@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
II. Need for Rule
III. Purpose of Rulemaking
IV. Request for Specific Comment
V. Discussion of Proposed Amendments by Section
VI. Criminal Penalties
VII. Agreement State Issues
VIII. Plain Language
IX. Voluntary Consensus Standards
X. Finding of No Significant Impact: Environmental Assessment
XI. Paperwork Reduction Act Statement
XII. Regulatory Analysis
XIII. Regulatory Flexibility Analysis
XIV. Backfit Analysis
I. Background
Safeguards Information (SGI) is a special category of sensitive
unclassified information to be protected from unauthorized disclosure
under section 147 of the Atomic Energy Act of 1954, as amended (AEA).
Although SGI is considered to be sensitive unclassified information, it
is handled and protected more like classified National Security
Information than like other sensitive unclassified information (e.g.,
privacy and proprietary information). Part 73, ``Physical Protection of
Plants and Materials,'' of the Commission's regulations in Title 10 of
the Code of Federal Regulations contains requirements for the
protection of SGI. Commission orders issued since September 11, 2001,
have also imposed requirements for the designation and protection of
SGI. These requirements apply to SGI in the hands of any person,
whether or not a licensee of the Commission, who produces, receives, or
acquires SGI. An individual's access to SGI requires both a valid
``need to know'' such information and authorization based on an
appropriate background investigation. Power reactors, certain research
and test reactors, and spent fuel storage installations are examples of
the categories of licensees currently within the scope of the
provisions of part 73 for the protection of SGI. Examples of the types
of information designated as SGI include the physical security plan for
a licensee's facility; the design features of such a licensee's
physical protection system; and operational procedures for the
licensee's security organization.
The Commission has authority under section 147 of the AEA to
designate, by regulation or order, other types of information as SGI.
For example, section 147.a.(2) allows the Commission to designate as
SGI a licensee's or applicant's detailed security measures (including
security plans, procedures and equipment) for the physical protection
of source material or byproduct material in quantities determined by
the Commission to be significant to the public health and
[[Page 7197]]
safety or the common defense and security. The Commission has, by
order, imposed SGI handling requirements on certain categories of these
other licensees. An example is a November 25, 2003 order issued to
certain materials licensees.\1\
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\1\ This order was published in the Federal Register as ``All
Licensees Authorized to Manufacture or Initially Transfer Items
Containing Radioactive Material for Sale or Distribution and Who
Possess Certain Radioactive Material of Concern and All Persons Who
Obtain Safeguards Information Described Herein; Order Issued on
November 25, 2003 Imposing Requirements for the Protection of
Certain Safeguards Information (Effective Immediately),'' (69 FR
3397 (January 23, 2004).
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Violations of SGI handling and protection requirements, whether
those specified in part 73 or those imposed by order, are subject to
the applicable civil and criminal sanctions. Employees, past or
present, and all persons who have had access to SGI have a continuing
obligation to protect SGI in order to prevent inadvertent release and
unauthorized disclosure. Information designated as SGI must be withheld
from public disclosure and must be physically controlled and protected.
Protection requirements include (1) secure storage; (2) document
marking; (3) restriction of access; (4) limited reproduction; (5)
protected transmission; and (6) controls for information processing on
electronic systems.
Inadequate protection of SGI, including inadvertent release and
unauthorized disclosure, may result in civil and/or criminal penalties.
The AEA explicitly provides in section 147.a. that ``any person,
whether or not a licensee of the Commission, who violates any
regulations adopted under this section shall be subject to the civil
monetary penalties of section 234 of this Act.'' Furthermore, willful
violation of any regulation or order governing SGI is a felony subject
to criminal penalties in the form of fines or imprisonment, or both, as
prescribed in section 223 of the AEA.
II. Need for Rule
Changes in the threat environment have revealed the need to protect
additional types of security information held by a broader group of
licensees as SGI. Under the current regulations, some categories of
licensees are not explicitly included in the categories of licensees
subject to the general performance requirements in 10 CFR 73.21(a).
Similarly, the current regulations do not specify all of the types of
information that are now recognized to be significant to the public
health and safety or the common defense and security. The unauthorized
release of this information could result in harm to the public health
and safety and the Nation's common defense and security, as well as
damage to the Nation's critical infrastructure, including nuclear power
plants and other facilities and materials licensed and regulated by the
NRC.
Since September 11, 2001, the NRC has issued orders that have
increased the number of licensees whose security measures will be
protected as SGI and have added additional types of security
information considered to be SGI. Orders have been issued to power
reactor licensees, fuel cycle facility licensees, certain source
material licensees, and certain byproduct material licensees. Some of
the orders expanded the types of information to be protected by
licensees who already have an SGI protection program, such as nuclear
power reactor licensees. Other orders were issued to licensees that
have not previously been explicitly subject to SGI protection
requirements in the regulations, such as certain licensees authorized
to manufacture or initially transfer items containing radioactive
material.\2\ Some orders impose a new designation: Safeguards
Information--Modified Handling (SGI-M). SGI-M pertains to certain SGI
subject to handling requirements that are modified from what part 73
itself currently requires. This designation for SGI applies to certain
quantities of source, byproduct, and special nuclear materials for
which the risk of unauthorized disclosure of information is relatively
low. In contrast, more stringent requirements are imposed for the
protection of SGI pertaining to licensees such as power reactors and
certain fuel cycle facilities.
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\2\ See 69 FR 3397 (January 23, 2004).
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Some of the requirements imposed by orders that have increased the
types of information to be considered SGI are not covered by the
current regulations. Although new SGI requirements could continue to be
imposed through the issuance of orders, the regulations would not
reflect current Commission SGI policy and/or requirements. Orders apply
only to the licensees named in the orders, and enforcement orders do
not apply prospectively to applicants for new licenses such as a rule
would. Duke Energy Corp. (Catawba Nuclear Station, Units 1 and 2), CLI-
04-6, 59 NRC 62 (2004) (February 18, 2004). Finally, it has been
Commission policy to codify requirements in the regulations and not to
rely on orders indefinitely to impose requirements that should have
generic application.
III. Purpose of Rulemaking
NRC staff review of the SGI regulatory program indicates that
changes in the regulations are needed to address issues such as access
to SGI, types of security information to be protected, and handling and
storage requirements.\3\
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\3\ The NRC staff is in the process of revising the guidance for
designation of SGI and has issued a draft document for comment
(Nuclear Regulatory Commission Draft Guide for the Designation of
Safeguards Information, July 2004).
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This rulemaking would:
Codify the SGI requirements imposed by the orders;
Expand the scope of part 73 to include additional categories of
licensees (e.g., source and byproduct material licensees, research and
test reactors not previously covered, and fuel cycle facilities not
previously covered);
Expand the types of security information covered by the definition
of SGI in Sec. 73.21 to include access authorization for background
screening, detailed emergency planning scenarios and implementing
procedures, vulnerabilities or weaknesses corrected in a security
system, and some training and qualification information; and
Update Sec. 73.21 to address advanced technology, such as new
types of portable communication devices and copiers using digital
technology.
A graded approach based on the risks and consequences of
information disclosure is being used in determining which category of
licensee or type of information will be subject to certain protection
requirements. This graded approach can be applied to such issues as the
type of information to be protected, the classes of licensees subject
to the rule, and the level of handling requirements necessary for the
various licensees. For example, the graded approach allows certain
licensees, whose quantities and forms of material pose a low risk from
unauthorized information disclosure, to employ the modified-handling
procedures introduced in recent orders for Safeguards Information
designated as SGI-M.
The requirements set forth in this proposed rule are the minimum
restrictions the Commission believes to be necessary in the current
threat environment to protect Safeguards Information against
inadvertent release or unauthorized disclosure which might compromise
the health and safety of the public or the common defense and security.
The proposed rule covers those facilities and materials the Commission
has already determined need to be protected against theft or sabotage.
The
[[Page 7198]]
categories of information constituting SGI relate to the types of
facilities and the quantities of special nuclear material, source
material and byproduct material determined by the Commission to be
significant and therefore subject to protection against unauthorized
disclosure pursuant to section 147 of the AEA. Unauthorized release of
Safeguards Information could reduce the deterrence value of systems and
measures used to protect nuclear facilities and materials and allow for
the possible compromise of those facilities and materials. Such
disclosures could also facilitate advance planning by an adversary
intent on committing acts of theft or sabotage against the facilities
and materials within the scope of the rule. The rule requirements
satisfy the minimum restrictions provision of section 147.a.(3)(A) of
the AEA. Further, the Commission has determined, pursuant to section
147.a.(3)(B) of the AEA, that the unauthorized disclosure of the
information that is the subject of the proposed rule could reasonably
be expected to have a significant adverse effect on the health and
safety of the public or the common defense and security by
significantly increasing the likelihood of theft, diversion, or
sabotage of nuclear material or a facility.
IV. Request for Specific Comment
The NRC is soliciting specific public comment on the following
issue associated with the proposed rulemaking action:
Differing Requirements for Access to SGI and SGI-M--sections
73.22(b)(1) and 73.23(b)(1) contain differing requirements for
performing background checks and making trustworthiness and reliability
determinations for granting personnel access to SGI or SGI-M.
Specifically, under Sec. 73.22(b)(1)(i)(A), an individual to be
authorized access to SGI by a nuclear power reactor applicant or
licensee must demonstrate trustworthiness and reliability and undergo a
Federal Bureau of Investigation criminal history check to the extent
required by Sec. 73.57, which includes fingerprinting. Individuals to
be authorized access to SGI by other applicants or licensees covered by
Sec. 73.22 or by a source, byproduct, or special nuclear material
applicant or licensee pursuant to Sec. 73.23(b)(1)(i) must demonstrate
trustworthiness and reliability through a comprehensive background
check or other means approved by the Commission. These different
requirements are based on the statutory authorization in section 149 of
the AEA for the NRC to require fingerprinting of individuals to be
granted access to SGI by nuclear power reactor applicants or licensees.
There is not a similar statutory authorization to require
fingerprinting by other applicants or licensees.
The NRC specifically invites comment on whether stakeholders would
perceive difficulties in complying with these varying requirements. If
so, the Commission would welcome stakeholder's suggestions, comments,
and/or proposals which would provide a more uniform approach to
background checks and trustworthiness and reliability determinations.
V. Discussion of Proposed Amendments by Section
Conforming changes to 10 CFR part 2, ``Rules of practice for
domestic licensing proceedings and issuance of orders,'' would be made
to the following sections to include citation of 10 CFR 73.22 and
73.23, in addition to citation of current Sec. 73.21, as applicable
appropriate: paragraph (f) of Sec. 2.709, ``Discovery against NRC
staff;'' \4\ paragraph (a)(4)(iii) of Sec. 2.1003, ``Availability of
material;'' and paragraph (b)(6) of Sec. 2.1010, ``Pre-License
application presiding officer.''
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\4\ In Sec. 2.709(f), which replaces former Sec. 2.744(e), a
few changes in the language and citations in former Sec. 2.744(e),
not relevant here, were made as part of a separate rulemaking
amending 10 CFR part 2. ``Changes to Adjudicatory Process; Final
Rule,'' 69 FR 2182, 2262 (January 14, 2004).
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Conforming changes are also being proposed to 10 CFR part 30,
``Rules of general applicability to domestic licensing of byproduct
material,'' and 10 CFR part 40, ``Domestic licensing of source
material.'' The proposed changes would add provisions to the sections
of those parts addressing applications for specific licenses and terms
and conditions of licenses. In part 30, Sec. Sec. 30.32, ``Application
for specific licenses'' and 30.34, ``Terms and conditions of
licenses,'' would be amended to include citation of Sec. Sec. 73.21
and 73.23. In part 40, corresponding sections (Sec. Sec. 40.41 and
40.31) would be amended to include citation of Sec. 73.21 and the
requirements of Sec. 73.22 or Sec. 73.23, as applicable. With these
additions, it should be clear that part 30 and part 40 licensees and
applicants (subject to 10 CFR part 73), under each part would be
required to protect categories of documents and information in
accordance with the requirements of part 73.
Conforming changes to 10 CFR part 50, ``Domestic licensing of
production and utilization facilities,'' would add to Sec. 50.34,
``Contents of applications; technical information'' and Sec. 50.54,
``Conditions of licenses,'' citations to Sec. 73.22, ``Protection of
Safeguards Information: Specific Requirements'' and Sec. 73.23,
``Protection of Safeguards Information-Modified Handling: Specific
Requirements.'' The purpose of these changes would be to reflect that
specific requirements for protecting SGI relating to such licensees and
materials would be moved from Sec. 73.21 to proposed Sec. 73.22 and
Sec. 73.23, of this chapter, as applicable.
Conforming changes are also being proposed to 10 CFR part 52,
``Early site permits; standard design certifications; and combined
licenses for nuclear power plants.'' Specifically, Sec. 52.47,
``Contents of applications,'' relating to standard design
certifications, would be amended to add as paragraph (c) the
requirement that an applicant for a standard design certification under
part 52 shall protect SGI against unauthorized disclosure in accordance
with the requirements of Sec. Sec. 73.21 and 73.22 of this chapter, as
applicable. A similar conforming change is being proposed for Sec.
52.79, ``Contents of application; technical information,'' relating to
combined licenses for nuclear power facilities.
Part 60, ``Disposal of high-level Radioactive wastes in geologic
repositories,'' would be amended to add in Sec. 60.21, ``Content of
application,'' new paragraph (d). That paragraph would state that the
application for a license for a geologic repository operations area
shall protect as SGI detailed security measures and related
information, in accordance with the requirements of Sec. 73.21 and the
requirements of Sec. 73.22 or Sec. 73.23 of this chapter, as
applicable. A parallel change would be made to a new paragraph (d) to
Sec. 60.42, ``Conditions of license.''
Part 63, ``Disposal of high-level radioactive wastes In a geologic
repository at Yucca Mountain, Nevada,'' would be amended to add new
paragraph (d) to Sec. 63.21, ``Content of application.'' That section
would state that the applicant for a license to receive and possess
source, byproduct, and special nuclear material at a geologic
repository at Yucca Mountain, Nevada shall protect the detailed
security measures for the physical protection of high-level radioactive
waste as SGI in accordance with Sec. Sec. 73.21 and 73.22. A
corresponding change (i.e., adding new paragraph (e)) would be made to
Sec. 63.42, ``Conditions of license.''
Conforming changes are being proposed for 10 CFR part 70,
``Domestic licensing of special nuclear material,'' subpart D--
``License applications.'' Specifically, Sec. 70.22, ``Contents of
applications,'' and Sec. 70.32 ``Conditions of licenses,'' would be
modified to add citation of proposed Sec. 73.23. These modifications
are being proposed to be
[[Page 7199]]
consistent with the addition of proposed Sec. 73.23 containing
specific requirements for Safeguards Information--Modified Handling
related to certain quantities of source and byproduct material and
special nuclear material of moderate or low strategic significance,
except for those materials covered under Sec. 73.22.
Part 71, ``Packaging and transportation of radioactive material,''
would be amended to add new Sec. 71.11, ``Protection of Safeguards
Information'' because licensees, certificate holders, or applicants for
a Certificate of Compliance for transport of radioactive material would
be required to protect Safeguards Information in accordance with the
applicable amended requirements in part 73. The proposed revision does
not address the protection of design-related information with respect
to transportation packages.
Part 72, ``Licensing requirements of the independent storage of
spent nuclear fuel, high-level radioactive waste, and reactor-related
greater than Class C waste,'' would also be amended. A new paragraph
(f) would be added to Sec. 72.22, ``Contents of application; General
and financial information,'' to require that each applicant for a
license under part 72 would be required to protect SGI against
unauthorized disclosure in accordance with Sec. 73.21 and the
requirements of Sec. 73.22 or Sec. 73.23, of this chapter, as
applicable. In Sec. 72.44, ``License conditions,'' paragraph (h) would
include a similar requirement for each licensee subject to part 73.
Section 72.212 would be changed to designate paragraph (b)(5)(v) as
paragraph (b)(5)(vi) and a new paragraph (b)(5)(v) would be added to
require that each general licensee that receives, transfers, and
possesses power reactor spent fuel, power reactor-related Greater than
Class C (GTCC) waste, and other radioactive materials associated with
spent fuel storage shall protect Safeguards Information against
unauthorized disclosure in accordance with the requirements of Sec.
73.21 and the requirements of Sec. 73.22 or Sec. 73.23, of this
chapter, as applicable. A new paragraph (n) would be added to Sec.
72.236, ``Specific requirements for spent fuel storage cask approval
and fabrication,'' to note that Safeguards Information shall be
protected against unauthorized disclosure in accordance with the
requirements of Sec. 73.21 and the requirements of Sec. 73.22 or
Sec. 73.23 of this chapter, as applicable.
Section 73.1 Purpose and Scope
Paragraph (b)(7) of this section would be amended to include a
reference to ``Safeguards Information-Modified Handling'' (SGI-M), the
designation for marking of documents containing Safeguards Information
(SGI) to which the Commission has determined modified protection
requirements apply. Orders to certain materials licensees contain this
new SGI-M designation and the handling requirements for such
information.
Section 73.2 Definitions
This section would be amended to add definitions of the terms
Individual Authorized Access to Safeguards Information and Individual
Authorized Access to Safeguards Information-Modified Handling;
Trustworthiness and Reliability, and Safeguards Information-Modified
Handling Requirements. In addition, the definition of the term
Safeguards Information would be modified.
The new terms Individual Authorized Access to Safeguards
Information and Individual Authorized Access to Safeguards Information-
Modified Handling, would be added to distinguish such individuals from
an ``authorized individual,'' which is defined now to apply only to the
control of and access to special nuclear material, without reference to
handling of information or documents.
The new term, Safeguards Information-Modified Handling, would be
added to reflect the new designation for marking of SGI subject to this
regulation. This marking has been previously established through
Commission orders.
The new term, Trustworthiness and Reliability, would be added to
reflect Commission expectations regarding positive character attributes
for access to SGI and SGI-M handling in addition to an individual's
``need to know'' such information. This expectation is embodied
elsewhere in part 73 (Sec. 73.56, ``Personnel access authorization
requirements for nuclear power plants.'') and in 10 CFR 26.10,
``General performance objectives,'' for fitness-for-duty. Specifically,
Sec. 73.56(b) requires, as a performance objective of a licensee's
access authorization program, ``high assurance'' that individuals
granted unescorted access to a nuclear power plant's protected and
vital areas are trustworthy and reliable. Similarly, under Sec.
26.10(a), a licensee's fitness-for-duty program must provide reasonable
assurance that covered personnel will perform their tasks in a
``trustworthy and reliable manner.''
The definition of ``Safeguards Information'' would be changed to
reflect that certain categories of information relating to source and
byproduct material are subject to protection as SGI against
unauthorized disclosure pursuant to section 147 of the AEA. In
addition, this definition would embody the Commission's authority under
section 147 of the AEA to determine, by order or regulation, that the
unauthorized disclosure of other information could reasonably be
expected to have an adverse effect on the health and safety of the
public or the common defense and security by significantly increasing
the likelihood of theft, diversion, or sabotage of materials and
facilities. The Commission may from time to time exercise its authority
under section 147.a.\5\ of the AEA to define additional information as
SGI. Thus, the public and other stakeholders would, through orders or
new regulations, be given notice of any additional definitions of SGI.
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\5\ In the exercise of this authority, the Commission makes
certain determinations and applies the minimum restrictions
necessary to protect SGI, in compliance with section 147 of the AEA.
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The proposed definition of SGI would also delete the words
``licensee's or applicant's'' [information]. This change is being
proposed to reflect in the regulations the Commission's authority under
section 147 of the AEA to determine that other information involving
the materials described in that provision shall be protected as SGI.
This authority can be exercised if the unauthorized disclosure of that
information could reasonably be expected to have an adverse effect on
the health and safety of the public or the common defense and security
by significantly increasing the likelihood of theft, diversion, or
sabotage of materials and facilities regulated by the Commission. The
proposed change is also based on the Commission's very broad authority
under section 161.b. of the AEA to regulate the use and possession of
source, byproduct, and special nuclear material in order to promote the
common defense and security or to protect health and minimize danger to
life or property.
Section 73.21 Protection of Safeguards Information: Performance
Requirements
This section would be revised as follows:
Section 73.21(a) General Performance Requirements
The language in paragraph (a) would be simplified and revised to
state at the outset that any person, including a licensee or an
applicant, who produces, receives or acquires SGI shall ensure that it
is protected against unauthorized disclosure. Although this is not a
new requirement under Sec. 73.21(a), the current language and format
of that paragraph does not emphasize this as an
[[Page 7200]]
obligation that extends to any person who produces, receives, or
acquires SGI.
Revised paragraphs Sec. 73.21(a)(1)(i) and (a)(1)(ii) would embody
the general performance requirement in paragraph (a) of current Sec.
73.21 that licensees, applicants, and persons subject to that section
must establish, implement, and maintain an information protection
system that includes specified measures. However, the proposed rule
presents separate requirements for the different categories of
licensees.
Proposed Sec. 73.22 contains the specific requirements for
Safeguards Information related to power reactors, licensees authorized
to possess a formula quantity of strategic special nuclear material,
transportation of or delivery to a carrier for transportation of a
formula quantity of strategic special nuclear material or more than 100
grams of irradiated reactor fuel, and fuel cycle facilities required to
implement security measures. Measures for protecting SGI relating to
certain quantities of source and byproduct material, and special
nuclear material of moderate or low strategic significance are
specified in proposed Sec. 73.23.\6\
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\6\ The quantities are those determined by the Commission
through order or regulation to be significant to the public health
and safety or the common defense and security.
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Although the measures for the protection of SGI are applicable if
the information is produced, received, or acquired, if licensees do not
have such information then the associated requirements would not apply.
For example, research and test reactors are not required to implement
the power reactor Design Basis Threat (DBT),\7\ and therefore, in all
likelihood would not possess DBT-related information. However, should a
research and test reactor receive or acquire such information, it would
be required to protect the information in accordance with applicable
measures.
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\7\ The DBTs, as described in 10 CFR 73.1, provide specific
adversary characteristics which power reactor and Category I fuel
cycle facilities need to protect against. The DBTs form the basis
for site-specific defensive strategies as set forth in a site's
physical security plan and contingency plan.
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Including the references to source, byproduct, and special nuclear
material in these new paragraphs would reflect the full scope of
section 147 of the AEA. That section authorizes the Commission to
protect against the unauthorized disclosure of SGI which specifically
identifies a licensee's or applicant's detailed procedures or security
measures relating to special nuclear material, byproduct material, and
source material, in quantities determined by the Commission through
order or regulation to be significant. This change would lessen the
need for the Commission to issue orders to licensees for the protection
of SGI relating to categories of licensees, information, or materials
not currently within the scope of part 73.
Section 73.21(a)(1)(i) and (a)(1)(ii) would also add the word
``implement'' to the requirement in current Sec. 73.21(a) that
licensees and persons subject to this section must establish and
maintain an information protection system to protect against the
unauthorized disclosure of SGI.
Section 73.21(b) Commission Authority
This is a new paragraph that recognizes the Commission's broad
authority and flexibility under section 147 of the AEA to designate
information as SGI or SGI-M and to impose levels of handling
requirements on any person who produces, receives, or acquires SGI. In
exercising this authority, the Commission is required to make a finding
that the unauthorized disclosure of such information could reasonably
be expected to have a significant adverse effect on the health and
safety of the public or the common defense and security by
significantly increasing the likelihood of the theft, diversion, or
sabotage of a facility or source, byproduct, and special nuclear
material. In addition, the Commission is to impose the minimum
restrictions necessary to protect the health and safety of the public
or the common defense and security.
The remaining paragraphs of Sec. 73.21 will be renumbered into new
Sec. Sec. 73.22 and 73.23, and modified as noted.
Section 73.22 Protection of Safeguards Information: Specific
Requirements
New Sec. 73.22 would be added, containing specific requirements
for Safeguards Information related to power reactors, licensees
authorized to possess a formula quantity of strategic special nuclear
material, transportation of or delivery to a carrier for transportation
of a formula quantity of strategic special nuclear material or more
than 100 grams of irradiated reactor fuel, and fuel cycle facilities
required to implement security measures.
Section 73.22(a) Information To Be Protected
Current Sec. 73.21(b) ``Information To Be Protected,'' would be
renumbered as Sec. 73.22(a) and be revised to add specificity to the
types of information and documents that must be protected as SGI. Such
information and documents would include the elements and
characteristics of the DBT in a level of detail greater than that
specified in Sec. 73.1, as well as security-related requirements to be
protected against unauthorized disclosure such as protective measures,
interim compensatory measures, and additional security measures. These
changes are necessary to codify in the regulations the recent practices
of the Commission as reflected in orders and threat advisories issued
since September 11, 2001.
Section 73.21(a)(1), ``Physical Protection at Fixed Sites,'' would
be changed to be consistent with the language in section 147.a.(1),
(2), and (3) of the AEA to include information relating to all of the
materials there specified. As revised, paragraph (a)(1) of Sec. 73.21
would not be limited to information concerning the protection of power
reactors authorized to operate and facilities that possess formula
quantities of strategic special nuclear material, as is current Sec.
73.21(b)(1). Section (a)(1)(i) would be revised to delete the word
``nuclear'' to be consistent with the terminology in section 147 of the
AEA. In addition, the words ``All portions of'' would be added at the
beginning of this category to make clear the broader scope of this
category of information intended to be protected as SGI.
Sections 73.22(a)(1)(iii) and 73.22(a)(1)(v) embody changes to
current Sec. 73.21(b)(1)(iii) and current Sec. 73.21(b)(1)(v). The
new Sec. 73.22(a)(ii) would delete the words ``Details of'' at the
beginning of these categories of information to make clear the broader
scope of the information intended to be protected as SGI.
Section 73.22(a)(1)(vi) would be current Sec. 73.21(b)(1)(vi) and
would be amended to include the phrase ``passwords integral to the
physical security system'' because such passwords constitute the type
of information that should be protected as SGI.
Section 73.22(a)(1)(viii), current Sec. 73.21(b)(1)(viii), and
Sec. 73.22(a)(1)(ix), current Sec. 73.21(b)(1)(ix), would be revised
to add at the beginning of each category the words ``All portions of.''
This change would make it clear that the referenced plans in their
entirety and subparts are intended to be designated as SGI. In
addition, current Sec. 73.21(a)(1)(ix) would be changed to recognize
the importance of the licensee's overall facility guard training and
qualification plan as a ``composite'' plan.
New Sec. 73.22(a)(1)(x) would reflect a combination of current
paragraphs Sec. 73.21(b)(1)(x), Sec. 73.21(b)(1)(xi), and
[[Page 7201]]
Sec. 73.21(b)(1)(xii). As revised, this paragraph would specify the
enumerated aspects of response forces.
Proposed Sec. 73.22(a)(1)(xi) would be added to cover information
concerning the size, tactics and capabilities required to defend
against the DBT or information that would disclose elements and
characteristics of the DBT in a greater level of detail than that
specified in Sec. 73.1.
Proposed Sec. 73.22(a)(1)(xii) would be added to specify for
protection as SGI engineering and safety analyses, emergency planning
procedures or scenarios, and other similar information relating to the
physical protection of a facility or materials if the unauthorized
disclosure of such information could reasonably be expected to have a
significant adverse effect on the health and safety of the public or
the common defense and security by significantly increasing the
likelihood of theft, diversion, or sabotage of such material or such
facility.
Proposed Sec. 73.22(a)(1)(xiii) is the current Sec.
73.21(b)(1)(xiii).
Section 73.22(a)(2) Physical Protection in Transit
The introductory paragraph in current Sec. 73.21(b)(2) and Sec.
73.21(b)(2)(i), Sec. 73.21(b)(2)(iii) and Sec. 73.21(b)(2)(iv) are
renumbered as new introductory paragraph Sec. 73.22(a)(2), Sec.
73.22(a)(2)(i), Sec. 73.22(a)(2)(iii) and Sec. 73.22(a)(2)(iv). The
introductory paragraph would be changed to reflect the applicability of
Sec. 73.22 to the transportation of or delivery to a carrier for
transportation of a formula quantity of strategic special nuclear
material or more than 100 grams of irradiated reactor fuel.
Section 73.22(a)(2)(i) would be revised to include the words ``All
portions of'' to make it clear that these plans in their entirety and
subparts are intended to be designated as SGI.
Current Sec. 73.21(b)(2)(ii) would be re-numbered as Sec.
73.22(a)(2)(ii) but would otherwise be unchanged.
Current Sec. 73.21(b)(2)(iii) would be renumbered as Sec.
73.22(a)(2)(iii) and changed to delete the words ``Details of'' to
clarify that the features, devices, and systems in their entirety are a
category of SGI to be protected as such.
Current Sec. 73.21(b)(2)(iv) would be renumbered as Sec.
73.22(a)(2)(iv) and would be otherwise unchanged.
Current Sec. 73.21(b)(2)(v) would be renumbered as Sec.
73.22(a)(2)(v) and would delete the words ``radio-telephone'' so as to
encompass the more modern means of communications. This section would
also delete the words ``Details regarding'' to clarify that all aspects
of communications during transport are included in this category of
information.
Current Sec. 73.21(b)(2)(vi) would be re-numbered as Sec.
73.22(a)(2)(vi) and would add the word ``security'' before the word
``emergencies'.
Section 73.22(a)(2)(vii) is new and its purpose would be to
encompass information concerning the tactics and capabilities required
to defend against attempted radiological sabotage or theft and
diversion of formula quantities of special nuclear material or related
information.
Section 73.22(a)(2)(viii) would be added to include as information
to be protected as SGI, engineering or safety analyses and emergency
planning procedures or scenarios relating to the protection of a
facility or material if the unauthorized disclosure of that information
could reasonably be expected to have a significant adverse effect on
the health and safety of the public or the common defense and security
by significantly increasing the likelihood of theft, diversion, or
sabotage of such facility or material.
Section 73.22(a)(3) is based on current Sec. 73.21(b)(3),
``Inspections, audits and evaluations,'' and would be broadened to
cover specific requirements for Safeguards Information related to power
reactors, licensees authorized to possess a formula quantity of
strategic special nuclear material, transportation of or delivery to a
carrier for transportation of a formula quantity of strategic special
nuclear material or more than 100 grams of irradiated reactor fuel, and
fuel cycle facilities required to implement security measures. Detailed
information regarding defects, weaknesses or vulnerabilities is
generally not released because identical circumstances may apply to a
licensee or applicant employing similar security measures. In addition,
the types of inspections and reports within the scope of the section
would not be limited to safeguards inspections and reports. This
language would recognize that documents concerning other types of
inspections could contain SGI.
Current Sec. 73.21(b)(4), Correspondence, would be renumbered
Sec. 73.22(a)(4) and would be otherwise unchanged.
Section 73.22(a)(5) would be new and would reflect the authority of
the Commission under Section 147.a. of the AEA to designate as SGI such
other information as the Commission may determine by order or
regulation could reasonably be expected to have a significant adverse
effect on the health and safety of the public or the common defense and
security by significantly increasing the likelihood of theft,
diversion, or sabotage of material or a facility (within the scope of
Sec. 73.22). The Commission, may from time to time, exercise its
authority under section 147.a.\8\ of the AEA to define additional
information as SGI and the public and other stakeholders would have
notice as to what these additional definitions of SGI are, through
orders or new regulations, that would specifically define SGI.
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\8\ In the exercise of this authority, the Commission would make
certain determinations and apply the minimum restrictions necessary
to protect SGI.
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Section 73.22(b) is based on current Sec. 73.21(c) through (i),
which address access to SGI and specific requirements for protecting it
from unauthorized disclosure. The Commission is proposing to re-
structure part 73 to accommodate the separate handling requirements for
SGI-M, imposed by order or regulation on certain byproduct, source, and
special nuclear materials licensees. Proposed Sec. 73.22 would contain
the specific requirements for Safeguards Information related to power
reactors, licensees authorized to possess a formula quantity of
strategic special nuclear material, transportation of or delivery to a
carrier for transportation of a formula quantity of strategic special
nuclear material or more than 100 grams of irradiated reactor fuel, and
fuel cycle facilities required to implement security measures.
Corresponding specific requirements for SGI-M relating to certain
quantities of source and byproduct material, and special nuclear
material of low or moderate strategic significance would be set forth
in proposed Sec. 73.23.
Section 73.22(b)(1) would state, as does current Sec. 73.21(c)(1),
the requirement that no person may have access to SGI unless the person
has an established ``need to know'' the information and fits within
described occupational categories (proposed Sec. 73.22(b)(1)(i)
through (vii)). The new Sec. 73.22(b)(1)(i)(A) and (B) add the
requirement that individuals authorized access to SGI by a nuclear
power reactor licensee and non-power reactor licensees and applicants,
demonstrate ``trustworthiness and reliability'' prior to such access.
The Commission has also updated the descriptions in Sec.
73.21(c)(1)(ii) through (vi) of some of the occupational groups and
added a new group, as described below.
The description of the occupational category in Sec.
73.22(b)(1)(i), (Commission, U.S. government, or licensee or applicant
employee, agent, or contractor) would change the language in current
Sec. 73.21(c)(1)(i) from
[[Page 7202]]
``U.S. Government'' to ``Executive Branch'' of the U.S. Government.
This change is necessary because for purposes of access to SGI, members
of Congress are covered separately in the occupational category
specified in proposed Sec. 73.22(b)(1)(i).
Additionally, new Sec. 73.22(b)(1)(i)(A) would require that an
individual authorized access to SGI by a nuclear power reactor facility
applicant or licensee must undergo an FBI criminal history check and
must demonstrate trustworthiness and reliability. Another new
paragraph, Sec. 73.22(b)(1)(i)(B) would be added, mandating that
individuals to be authorized access to SGI by a non-power reactor
facility applicant or licensee must also demonstrate trustworthiness
and reliability. However, this demonstration would be based on a
comprehensive background check or other means approved by the
Commission in lieu of the FBI criminal history check.
Section 73.22(b)(1)(ii) is based on current Sec. 73.21(c)(1)(ii)
but would delete the phrase ``a duly authorized committee of'' [the
Congress]. Under the Commission's current regulations in Sec.
73.21(c)(1)(ii), a member of a ``duly authorized committee of the
Congress'' with a ``need to know'' SGI is given access to such
information. This section of the regulations does not set forth the
meaning of a ``duly authorized committee.'' If narrowly interpreted,
this occupational category might only apply to members of Congress who
serve on NRC oversight committees. The deletion in the proposed rule of
the phrase ``a duly authorized committee'' [of the Congress] would mean
that the authorization would extend to all members of Congress (with a
``need to know'' SGI). This change would be made because many members
of Congress are not on NRC oversight committees, yet they may need
access to SGI because of the presence of nuclear facilities or
materials in their states or districts. As amended, the language would
not alter the Commission's current practices in responding to requests
from members of Congress for access to SGI.
In addition, the authorization in current Sec. 73.21(c)(1)(ii)
does not extend to congressional staff. The Commission is not proposing
to extend the authorization to congressional staff. On a case-by-case
basis, with explicit authorization from the appropriate NRC office, the
NRC staff could share SGI with a Congressional staff member with a
``need to know'' SGI and who otherwise meets the requirements for
access to such information.
Section 73.22(b)(1)(iii) renumbers current Sec. 73.21(c)(1)(iii)
and would be otherwise unchanged.
Section 73.22(b)(1)(iv) is based on current Sec. 73.21(c)(1)(iv)
but the word ``representative'' is being made plural to account for the
fact that more than one representative may be designated under this
occupational category. The plural form is consistent with similar
language in the descriptions of occupational categories in current
Sec. 73.21(c)(1).
Current Sec. 73.21(c)(1)(v) would be re-numbered as paragraph
(b)(1)(v) and the description of this occupational category would be
changed to ``employees'' (which would include the current term
``member'') of a state or local law enforcement authority who are
responsible for responding to requests for assistance during safeguards
or securities emergencies.
Section 73.22(b)(1)(vi) includes as an occupational category, State
Radiation Control Program Directors and Homeland Security Advisors or
their designated representatives. This category corresponds to Sec.
73.23(b)(1)(iii).
Section 73.22(b)(1)(vii) is current Sec. 73.21(c)(1)(vi) and
substitutes the citation of 10 CFR Sec. 2.709(f) for Sec. 2.744(e)
because the latter citation is outdated.
Section 73.22(b)(2) contains a statement contained in a recent
Commission order \9\ that finds that individuals in the occupational
categories described in Sec. 73.22(b)(1)(ii) through Sec.
73.22(b)(1)(vii) \10\ are considered to be trustworthy and reliable by
virtue of their occupational status. For non-governmental individuals
described in Sec. 73.22(b)(1)(i), a determination of trustworthiness
and reliability is required prior to granting access to SGI. Discretion
must be exercised in granting access to these individuals. If there is
any indication that the recipient would be unwilling or unable to
provide proper protection for the SGI, they are not authorized to
receive SGI-M.
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\9\ e.g., ``All Licensees Authorized to Manufacture or Initially
Transfer Items Containing Radioactive Material for Sale or
Distribution and Possess Certain Radioactive Material of Concern and
All Other Persons Who Obtain Safeguards Information; Order Imposing
Requirements for the Protection of Certain Safeguards Information
(Effective Immediately) (69 FR 3397, 3399; January 23, 2004).
\10\ Individuals (or in some cases, their designated
representatives) in the following occupational groups are included:
State Governors, representatives of the IAEA, employees of state or
local law enforcement, State Radiation Control Program Directors and
State Homeland Security Advisors, and individuals to whom disclosure
is ordered pursuant to 10 CFR 2.709(f). (69 FR 3399; January 23,
2004).
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Section 73.22(c) Protection While in Use or Storage
Section 73.22(c)(1) contains the identical requirement in current
Sec. 73.21(d), that while in use, matter containing SGI shall be under
the control of an individual authorized access to SGI.
Under certain conditions the general control exercised over
security zones or areas would be considered to meet this requirement.
Some examples of these areas would be: Alarm stations, guard posts and
guard ready rooms; engineering or drafting areas if visitors are
escorted and information is not clearly visible; plant maintenance
areas if access is restricted and information is not clearly visible;
administrative offices (e.g., central records or purchasing) if
visitors are escorted and information is not clearly visible. The
primary consideration is limiting access to those who have a ``need to
know'' and are authorized to have access. Section 73.22(c)(2) would be
revised to limit access to lock combinations.
Section 73.22(d) Preparation and Marking of Documents or Other Matter
Section 73.22(d) would revise current Sec. 73.21(e) to add in the
title ``or other matter,'' to be consistent with the language in the
substantive paragraphs that follow. In addition, a new provision would
be added to require certification that a document or other matter
contains SGI and the certification must set forth the name and title of
the certifying official and the certification date. Also, portion
marking would be required for correspondence to NRC. Such marking would
have to be sufficient to allow the recipient to identify and
distinguish those sections of the document or other matter containing
the protected information from the information that is otherwise
unprotected.
Section 73.22(e) Reproduction of Matter Containing Safeguards
Information
Section 73.21(f) is renumbered to become Sec. 73.22(e) and the
text is revised to include direction for the use of digital copiers and
to delete language regarding destruction of SGI, which has been
relocated to Sec. 73.22(i).
Section 73.22(f) External Transmission of Documents and Material
Section 73.22(f)(1) would amend Sec. 73.21(g)(1) to set forth
detailed requirements for packaging SGI when transmitted outside an
authorized place of use or storage. These prescriptive requirements are
consistent with the current practices of nuclear power
[[Page 7203]]
reactor licensees and the Commission now deems it necessary to require
them to adequately protect SGI or SGI-M when such information is
transmitted externally.
Section 73.22(f)(2) would amend Sec. 73.21(g)(2) to conform to
other changes made by this rulemaking.
Section 73.22(f)(3) would add language to current Sec. 73.21(g)(3)
to permit transmission of SGI by protected telecommunication circuits
(including facsimile) or encryption (Federal Information Processing
Standard). Both of these means of transmission must be approved by the
appropriate NRC office.
Section 73.22(g) Processing of SGI on Electronic Systems
This section updates the title and expands the content of current
Sec. 73.21(h), ``Use of automatic data processing (ADP) systems,'' to
refer to the processing of SGI on electronic systems and to add
specific requirements applicable to the computer processing of SGI.
Section 73.22(h) Removal From Safeguards Information Category
Section 73.22(h) revises current Sec. 73.21(i) to add further
restrictions on decontrolling SGI. One proposed change concerns the
degree of care that must be exercised in removing information from the
SGI category. The other new requirement would specify that the
authority to determine that a document may be decontrolled shall be
exercised only by the NRC or with NRC approval, or in consultation with
the individual or organization that made the original determination, if
possible. Removal from the SGI-M category is addressed in Sec.
73.23(h).
Section 73.22(i) Destruction of Matter Containing SGI
Section 73.22(i) contains revised language from current Sec.
73.21(f) to be consistent with the policies set forth in the orders
regarding the destruction of documents.
New Section 73.23 Protection of Safeguards Information-Modified
Handling: Specific Requirements.
This is a new section which would set forth the specific
requirements for Safeguards Information--Modified Handling related to
certain quantities of source and byproduct material and special nuclear
material of moderate or low strategic significance, except for those
materials covered under section 73.22. The term ``SGI-M'' would be used
as the distinguishing marking for SGI relating to certain source,
byproduct, and special nuclear material licensees. Section 73.23 is
based on the Commission's orders and threat advisories issued to
certain byproduct materials licensees.
Section 73.23(a) Information To Be Protected
Section 73.23(a) sets forth the information to be protected in
accordance with the handling requirements specified in Sec. 73.23(c)
through (i). In general terms, information deemed SGI-M is information
the disclosure of which could reasonably be expected to have a
significant adverse effect on the health and safety of the public or
the common defense and security by significantly increasing the
likelihood of theft, diversion, or sabotage of materials or facilities
subject to NRC jurisdiction. SGI-M is the designation and marking for
SGI which is subject to these requirements. The overall measure for
consideration of SGI-M is the usefulness of the information (security
or otherwise) to an adversary in planning or attempting a malevolent
act; the more specific the information, the more likely that it will be
useful to an adversary.
Section 73.23(a) states that the specific types of information and
documents to be protected as SGI-M include security-related
requirements that must be protected from unauthorized disclosure such
as protective measures, interim compensatory measures, and additional
safety features. Sections 73.23(a)(1) through (a)(4) enumerate and
describe the specific categories of SGI-M to be protected. These
categories of information are based on those proposed in Sec.
73.22(a)(1) through (a)(5), as applicable, which in turn update the
types of information specified in current Sec. 73.21(b)(1) through
(b)(4). In reference to proposed Sec. 73.23(a)(3)(i), regarding
portions of certain inspection reports, evaluations, audits, or
investigations, detailed information regarding defects, weaknesses or
vulnerabilities is generally not released because identical
circumstances may apply to licensees or applicants employing similar
security measures. Section 73.23(a)(4) references correspondence as it
pertains to this section.
Section 73.23(a)(5) would be new and would reflect the authority of
the Commission under section 147a of the AEA to designate as SGI such
other information as the Commission may determine by order or
regulation could reasonably be expected to have a significant adverse
effect on the health and safety of the public or the common defense and
security by significantly increasing the likelihood of theft,
diversion, or sabotage of material or a facility (within the scope of
Sec. 73.22). The Commission, may from time to time, exercise its
authority under section 147.a.\11\ of the AEA to define additional
information as SGI and the public and other stakeholders would have
notice as to what these additional definitions of SGI are, through
orders or new regulations, that would specifically define SGI.
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\11\ In the exercise of this authority, the Commission would
make certain determinations and apply the minimum restrictions
necessary to protect SGI.
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Section 73.23(b)(1) addresses conditions for access to SGI-M.
Authorization for access to SGI-M by licensee employees, agents, or
contractors must be based on both an appropriate ``need to know''
determination by the licensee, as well as a determination concerning
the trustworthiness and reliability of individuals having access to the
information. Employees of an organization associated with the
licensee's company, for example, a parent company, may be considered as
employees of the licensee for access purposes. A recipient of SGI-M
should be made aware that the information is SGI-M and those having
access to it are subject to the requirements for its protection as well
as civil and criminal sanctions for mishandling the information.
Section 73.23(b)(1)(ii) through (vi) describes occupational groups
who are deemed to be trustworthy and reliable by virtue of their
employment status. For non-governmental individuals in Sec.
73.23(b)(1)(i) and (vii), a determination of trustworthiness and
reliability is required. Discretion must be exercised in granting
access to these individuals. If there is any indication that the
recipient would be unwilling or unable to provide proper protection of
the SGI-M, they are not authorized to receive SGI-M.
Section 73.23(b)(1)(ii) is identical to the current Sec.
73.21(c)(1)(ii), except the phrase ``a duly authorized committee of''
[the Congress] would be deleted. Under the Commission's current
regulations in Sec. 73.21(c)(1)(ii), a member of a ``duly authorized
committee of the Congress'' with a ``need to know'' SGI is given access
to such information. This section of the regulations does not set forth
the meaning of a ``duly authorized committee.'' The deletion in the
proposed rule of the phrase ``a duly authorized committee'' [of the
Congress] would mean that the authorization would extend to all members
of Congress (with a ``need to know'' SGI-
[[Page 7204]]
M). This change would be made because many members of Congress are not
on NRC oversight committees, yet may need access to SGI-M because
nuclear facilities or materials are located in their states or
districts. As amended, the language would not alter the Commission's
current practices in responding to requests from members of Congress
for access to SGI.
In addition, the authorization in current Sec. 73.21(c)(1)(ii)
does not extend to Congressional staff. The Commission is not proposing
to extend the authorization to Congressional staff. On a case-by-case
basis, with explicit authorization from the appropriate NRC office, the
NRC staff could share SGI-M with a Congressional staff member with a
``need to know'' SGI and who otherwise meets the requirements for
access to such information.
Section 73.23(b)(1)(iii) corresponds to Sec. 73.22(b)(1)(iii),
which includes the Governor of a state or designated representatives as
an occupational category presumed to be trustworthy and reliable for
access to SGI.
Section 73.23(b)(1)(iv) is based on Sec. 73.21(c)(1)(iv) and the
only change is to make ``representative'' plural because that would be
consistent with language for other occupational categories in which the
plural form is used.
Section 73.23(b)(1)(v) corresponds to proposed Sec.
73.22(b)(1)(v), in which the description of this occupational category
would be changed to ``employees'' (which would include the current term
``member'') of a state or local law enforcement authority who are
responsible for responding to requests for assistance during safeguards
or securities emergencies.
Section 73.23(b)(1)(vi) is the same occupational category of
individuals in Sec. 73.22(b)(1)(vi). Because homeland security
advisors is the correct title of the individuals to be included in this
occupational category, that title is contained in proposed rule text.
Section 73.23(b)(1)(vii) corresponds to proposed Sec.
73.22(c)(1)(vi), which is based on current Sec. 73.21(c)(1)(vi). As
proposed, this paragraph substitutes the citation of 10 CFR 2.709(f)
for Sec. 2.744(e) because the latter citation is outdated.
The subject of Sec. 73.23(c) is protection of SGI-M while in use
or storage. While in use, SGI-M shall be under the control of an
individual authorized access to Safeguards Information Modified
Handling. This requirement is satisfied if the SGI-M is attended by an
authorized individual in certain locations even though the information
is in fact not constantly being used. Examples of such locations
include: Engineering or drafting areas, plant maintenance areas, or
administrative offices (e.g., central records or purchasing) if
visitors are escorted and information is not clearly visible in these