Protection of Safeguards Information, 7196-7217 [05-2665]

Download as PDF 7196 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules any criminal statutes or other ethics rules. Employees are reminded that during the course of an otherwise approvable activity, situations may arise, or actions may be contemplated, that nevertheless, pose ethical concerns. SSA ethics officials are available to provide advice and guidance to SSA employees as to such situations. [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, VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00005 Fmt 4702 Sfmt 4702 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 E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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). VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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. PO 00000 2 See 69 FR 3397 (January 23, 2004). Frm 00006 Fmt 4702 Sfmt 4702 7197 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). E:\FR\FM\11FEP1.SGM 11FEP1 7198 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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 VerDate jul<14>2003 12:45 Feb 10, 2005 Jkt 205001 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). PO 00000 Frm 00007 Fmt 4702 Sfmt 4702 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 E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00008 Fmt 4702 Sfmt 4702 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. E:\FR\FM\11FEP1.SGM 11FEP1 7200 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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. VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00009 Fmt 4702 Sfmt 4702 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 E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules § 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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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, PO 00000 Frm 00010 Fmt 4702 Sfmt 4702 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. E:\FR\FM\11FEP1.SGM 11FEP1 7202 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules ‘‘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. VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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). PO 00000 Frm 00011 Fmt 4702 Sfmt 4702 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 E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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, PO 00000 Frm 00012 Fmt 4702 Sfmt 4702 7203 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. E:\FR\FM\11FEP1.SGM 11FEP1 7204 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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 VerDate jul<14>2003 12:45 Feb 10, 2005 Jkt 205001 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). PO 00000 Frm 00013 Fmt 4702 Sfmt 4702 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 E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules § 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. VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 PO 00000 Frm 00014 Fmt 4702 Sfmt 4702 7205 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 E:\FR\FM\11FEP1.SGM 11FEP1 7206 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. VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00015 Fmt 4702 Sfmt 4702 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, E:\FR\FM\11FEP1.SGM 11FEP1 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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00016 Fmt 4702 Sfmt 4702 7207 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. * * * * * E:\FR\FM\11FEP1.SGM 11FEP1 7208 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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. * * * * * VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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, PO 00000 Frm 00017 Fmt 4702 Sfmt 4702 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 E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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 12:06 Feb 10, 2005 Jkt 205001 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 VerDate jul<14>2003 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 PO 00000 Frm 00018 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: E:\FR\FM\11FEP1.SGM 11FEP1 7210 § 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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00019 Fmt 4702 Sfmt 4702 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 E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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: VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 § 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 PO 00000 Frm 00020 Fmt 4702 Sfmt 4702 7211 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 E:\FR\FM\11FEP1.SGM 11FEP1 7212 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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, VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00021 Fmt 4702 Sfmt 4702 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, E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules (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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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. PO 00000 Frm 00022 Fmt 4702 Sfmt 4702 7213 (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 E:\FR\FM\11FEP1.SGM 11FEP1 7214 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00023 Fmt 4702 Sfmt 4702 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: E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules (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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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. PO 00000 Frm 00024 Fmt 4702 Sfmt 4702 7215 (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 E:\FR\FM\11FEP1.SGM 11FEP1 7216 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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 VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00025 Fmt 4702 Sfmt 4702 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. E:\FR\FM\11FEP1.SGM 11FEP1 Federal Register / Vol. 70, No. 28 / Friday, February 11, 2005 / Proposed Rules 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, VerDate jul<14>2003 12:06 Feb 10, 2005 Jkt 205001 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 PO 00000 Frm 00026 Fmt 4702 Sfmt 4702 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). E:\FR\FM\11FEP1.SGM 11FEP1

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]


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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.

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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.
---------------------------------------------------------------------------

    \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.
---------------------------------------------------------------------------

    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.
---------------------------------------------------------------------------

    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.
---------------------------------------------------------------------------

    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.
---------------------------------------------------------------------------

    \8\ In the exercise of this authority, the Commission would make 
certain determinations and apply the minimum restrictions necessary 
to protect SGI.
---------------------------------------------------------------------------

    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.
---------------------------------------------------------------------------

    \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).
---------------------------------------------------------------------------

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.
---------------------------------------------------------------------------

    \11\ In the exercise of this authority, the Commission would 
make certain determinations and apply the minimum restrictions 
necessary to protect 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 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
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