Amendments to Material Control and Accounting Regulations

Federal Register, Volume 78 Issue 217 (Friday, November 8, 2013)

Federal Register Volume 78, Number 217 (Friday, November 8, 2013)

Proposed Rules

Pages 67225-67252

From the Federal Register Online via the Government Printing Office www.gpo.gov

FR Doc No: 2013-25617

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NUCLEAR REGULATORY COMMISSION

10 CFR Parts 40, 70, 72, 74, and 150

NRC-2009-0096

RIN 3150-AI61

Amendments to Material Control and Accounting Regulations

AGENCY: Nuclear Regulatory Commission.

ACTION: Proposed rule.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations for material control and accounting (MC&A) of special nuclear material (SNM). The goal of this rulemaking is to revise and consolidate the MC&A requirements in order to update, clarify, and strengthen them. The proposed amendments add new requirements that would apply to NRC licensees who are authorized to possess SNM in a quantity greater than 350 grams.

DATES: Submit comments on the rule by February 18, 2014. Submit comments specific to the information collections aspects of this rule by December 9, 2013. Comments received after these dates will be considered if it is practical to do so, but the NRC is able to assure consideration only for comments received on or before these dates.

ADDRESSES: You may submit comments by any of the following methods (unless this document describes a different method for submitting comments on a specific subject):

Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2009-0096. Address questions about NRC dockets to Carol Gallagher; telephone: 301-287-

3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.

Email comments to: Rulemaking.Comments@nrc.gov. If you do not receive an automatic email reply confirming receipt, then contact us at 301-415-1677.

Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at 301-415-1101.

Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff.

Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. (Eastern Time) Federal workdays; telephone: 301-415-1677.

For additional direction on accessing information and submitting comments, see ``Accessing Information and Submitting Comments'' in the SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Thomas Young, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-

5795, email: Thomas.Young@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Accessing Information and Submitting Comments

II. Introduction and Summary of Proposed Revisions to MC&A Regulations

III. Specific Request for Comments on the Proposed New Requirements

IV. Discussion

1. Whom would this action affect?

2. Why are the requirements being revised?

3. When would these actions become effective?

4. How does the NRC use a graded approach for MC&A?

5. What are the changes to the general performance objectives?

6. Are sealed sources included in the general performance requirements for Category II and III facilities?

7. Why would newly defined terms be added to 10 CFR 74.4?

8. Why would the term, ``effective kilograms of special nuclear material,'' be removed from 10 CFR part 74?

   I. Why would appendix A to 10 CFR part 74 be added?

10. Why would references to the MC&A ``system'' be changed to the MC&A ``program,'' and why would ``MC&A plan'' replace ``FNMC plan?''

11. What would change in the reporting requirements to the NMMSS, including those that ISFSIs are subject to?

    L. Is a two-person rule included as part of this proposed rule?

13. Why would requirements be added to designate material balance areas, item control areas, and custodians?

14. Why would calendar days be inserted into 10 CFR part 74?

15. Would the implementation guidance documents be updated for the MC&A program?

16. Would there be changes for item controls or physical inventories?

17. Why would an exception be added to 10 CFR 74.15(b)(2)?

18. Are there any cumulative effects of regulation associated with this rule?

19. What should I consider as I prepare my comments to the NRC?

    V. Discussion of Proposed Amendments by Section

    VI. Availability of Documents

    VII. Criminal Penalties

    VIII. Agreement State Compatibility

    IX. Plain Writing

    X. Voluntary Consensus Standards

    XI. Environmental Assessment and Finding of No Significant Environmental Impact: Availability

    XII. Paperwork Reduction Act Statement

    XIII. Regulatory Analysis

    XIV. Regulatory Flexibility Certification

    XV. Backfitting and Issue Finality

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    I. Accessing Information and Submitting Comments

1. Accessing Information

   Please refer to Docket ID NRC-2009-0096 when contacting the NRC about the availability of information for this proposed rule. You may access publicly available information related to this proposed rule by any of the following methods:

   Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2009-0096.

   NRC's Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and then select ``Begin Web-

   based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-

   4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced in this document (if that document is available in ADAMS) is provided the first time that a document is referenced. In addition, for the convenience of the reader, the ADAMS accession numbers are provided in a table in the section of this document entitled, ``Availability of Documents.''

   NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.

2. Submitting Comments

   Please include Docket ID NRC-2009-0096 in the subject line of your comment submission, in order to ensure that the NRC is able to make your comment submission available to the public in this docket.

   The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information.

   If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment submissions into ADAMS.

   II. Introduction and Summary of Proposed Revisions to MC&A Regulations

   The NRC's regulations specify requirements for control and accounting of SNM that is held by a licensee. The MC&A regulations ensure that the information about SNM is accurate, authentic, and sufficiently detailed to enable a licensee to maintain current knowledge of its SNM and manage its program for securing and protecting SNM. The MC&A, together with physical protection of facilities and information security requirements, make up the primary elements of the NRC's SNM safeguards program. The MC&A component of the larger safeguards program helps ensure that SNM within a fuel cycle facility is not stolen or otherwise diverted from the facility and promotes the NRC's strategic goal of maintaining adequate protection over the use and management of radioactive materials.

   The MC&A requirements for an independent spent fuel storage installation (ISFSI) would be consolidated with MC&A regulations applicable to other types of facilities authorized to possess SNM. General performance objectives (GPOs) would be made applicable to an additional set of NRC licensees who are authorized to possess more than 350 grams of SNM. Some current exemptions in the MC&A regulations would be removed or modified to strengthen the requirements, and defined terms would be added to clarify the regulations. Plain language revisions would also be made. Guidance documents would be updated as necessary to reflect these proposed changes. Concurrently with this proposed rule, in this issue of the Federal Register, the NRC published a document (NRC-2013-0195) requesting comment on the following draft NUREGs: NUREG-1280, Revision 2, ``Acceptable Standard Format and Content for the Material Control and Accounting (MC&A) Plan Required for Strategic Special Nuclear Material;'' NUREG-2159, ``Acceptable Standard Format and Content for the Material Control and Accounting (MC&A) Plan Required for Special Nuclear Material of Moderate Strategic Significance;'' NUREG-1065, Revision 3, ``Acceptable Standard Format and Content for the Material Control and Accounting (MC&A) Plan Required for Special Nuclear Material of Low Strategic Significance;'' NUREG-2158 (formerly NUREG/CR-5734), ``Acceptable Standard Format and Content for the Material Control and Accounting (MC&A) Plan Required for Low Enriched Uranium Enrichment Facilities;'' and NUREG/BR-0096, Revision 2, ``Instructions and Guidance for Completing Physical Inventory Summary Reports.''

   The NRC seeks input on several specific aspects of the proposed rule, including the appropriate threshold amount of SNM on which item control requirements should be imposed. With respect to these and other proposed requirements that go beyond consolidation and clarification of existing requirements, the NRC seeks input on the need for the requirements in relation to the proportionate levels of risk represented by the processes and material quantities and forms that are used at different types of licensee facilities. The NRC also seeks input on whether there are less burdensome alternatives to the proposed requirements that would still ensure the adequate control and accurate accounting of SNM.

   In a future rulemaking, the NRC will consider a two-person rule to verify the accuracy of MC&A information within a fuel cycle facility. Interested stakeholders will then have the opportunity to comment regarding a two-person rule.

   The NRC plans to amend Title 10 of the Code of Federal Regulations (10 CFR) to consolidate the MC&A provisions in 10 CFR part 74. Conforming changes would be made to 10 CFR parts 40, 70, 72 and 150. The changes are intended to update, clarify, and strengthen MC&A requirements.

   The existing 10 CFR part 74 regulations contain subparts A through F, and the MC&A requirements are organized in a graded fashion with subpart E containing the most rigorous set of MC&A requirements. General MC&A reporting and recordkeeping requirements in subpart B apply to all materials licensees authorized to possess SNM under 10 CFR part 70, reactor licensees under 10 CFR parts 50 or 52, and ISFSI licensees under 10 CFR part 72. Licensees authorized to possess SNM of ``low strategic significance'' (defined in 10 CFR 74.4) are subject to the more rigorous MC&A requirements in subpart C. Such licensees operate what are known as Category III facilities, which include licensed uranium enrichment facilities and the three fuel fabrication facilities supplying fresh fuel assemblies (containing low enriched uranium) to commercial power reactors.

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   Licensees authorized to possess SNM of ``moderate strategic significance'' (defined in 10 CFR 74.4) are subject to the MC&A requirements in subpart D, and are authorized to operate Category II facilities (no such facilities currently operate). The most rigorous MC&A requirements are in subpart E, and apply to licensees authorized to possess a ``formula quantity'' (defined in 10 CFR 74.4) of strategic special nuclear material (SSNM). Such 10 CFR part 70 licensees operate what are known as Category I facilities. Only two such facilities now operate, and they fabricate fuel (containing high enriched uranium) for use by the U.S. Navy and in research and test reactors. One potential Category I facility may operate in the future as a mixed oxide fuel fabrication facility.

   Table 1 shows the location of the proposed MC&A requirements within 10 CFR part 74 and the types of facilities that are licensed to possess SNM. A list of specific questions about the proposed requirements is provided in Section III of this document.

   Table 1--Location of Proposed MC&A Requirements for Certain Types of Facilities

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   Location in proposed 10 CFR part 74 by type of facility

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   Subparts A and B

   New requirement ------------------------------------------------------------

   Part 70 license Subpart C Subpart D Subpart E

   authorizing > 350 Part 50 or 52 Part 72 ISFSI

   grams reactor facility

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   Part 70 Fuel Cycle Facility

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   Category III Category II Category I

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   General performance objectives.. 74.3 modified the modified the modified the

   existing existing existing

   requirements in requirement in requirement in

   74.31(a) and 74.41(a) to refer 74.51(a) to refer

   74.33(a) to refer to 74.3. to 74.3 and

   to 74.3; retained retain unique

   the unique performance

   performance objectives

   objectives in 74.51(a).

   74.33(a) for an

   enrichment

   facility.

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   Item control system............. no requirement.... 74.19(d) modified the modified the no modification

   existing existing would be needed

   requirements in requirement in for existing

   74.31(c)(6) and 74.43(b)(5) to 74.55, Item

   74.33(c)(6) to remove some Monitoring.

   remove some exemptions.

   exemptions.

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   Tamper-safing of containers or no requirement 74.31(c)(9)....... clarified the clarified the

   vaults. 74.33(c)(9)....... existing existing

   requirement in requirement in

   74.43(c)(3). 74.59(f)(2)(i).

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   MBA/ICA and custodians.......... no requirement 74.31(c)(10)...... 74.43(c)(9)....... 74.59(h)(5).

   74.33(c)(10)......

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   In 2008, the NRC developed an MC&A rulemaking plan (SECY-08-0059, Rulemaking Plan: Part 74--Material Control and Accounting of Special Nuclear Material, ADAMS Accession No. ML080580307) and submitted it to the Commission for its consideration. In accordance with the Commission's approval of the rulemaking plan's Option 4 in the Staff Requirements Memorandum (SRM) for SECY-08-0059 (ADAMS Accession No. ML090360473), various changes would be made to 10 CFR part 74. The considerations on which this rulemaking action are based, and the proposed substantive changes to the MC&A requirements, may be summarized as follows:

   General Performance Objectives

   The existing GPO requirements are set forth for each type of facility in 10 CFR 74.31(a), 74.33(a), 74.41(a), and 74.51(a). Building on these existing GPOs, the NRC proposes to list five GPOs in a new 10 CFR 74.3 that would apply to all licensees authorized to possess more than 350 grams of SNM--a set of licensees that includes power reactors and ISFSIs. The 10 CFR 74.3 GPOs would largely replace the existing GPOs for Category I, II, and III facilities. Some GPOs that are unique to the Category III enrichment facilities, and to the Category I fuel fabrication facilities, would remain in revised 10 CFR 74.33(a) and 74.51(a), respectively. The NRC does not expect that Category I, II, and III licensees would need to alter their MC&A programs in response to the 10 CFR 74.3 GPOs, because these GPOs are similar to the existing GPOs.

   Proposed 10 CFR 74.3(e) would require that information related to MC&A be stored in a locked file cabinet or office.

   Licensees authorized to possess 350 grams of SNM or less would not be made subject to the GPO requirements, because such licensees are not required to implement a formal MC&A program. These licensees are subject to the existing reporting requirements in 10 CFR 74.11, 74.13, and 74.15, which are applicable to licensees authorized to possess 1 gram or more of SNM. Agreement State licensees are similarly subject to the corresponding reporting requirements in 10 CFR 150.16 and 150.17.

   Item Control System

   Existing subparts C and D of 10 CFR part 74 contain item control provisions applicable to Category III and II facilities, respectively, that would be modified. The NRC additionally proposes to add clarifying definitions of two related terms to 10 CFR 74.4. Item

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   control system would be defined as a system for tracking the creation, identity, element and isotopic content, location, and disposition of all items, which would enable the licensee to maintain current knowledge of each item in its possession. Item control area (ICA) would be defined as a designated administrative area within the controlled access area, in which SNM would be maintained in such a way that, at any time, a count of the items and the related material quantities can be obtained using the accounting system. Control of items moving into, out of, and within an ICA would be indicated by the identity of an item and its assigned material quantity.

   As is the case for the GPO requirements previously discussed, licensees authorized to possess 350 grams of SNM or less would not be subject to item control requirements. Starting in 2009, such licensees were required to submit material balance and physical inventory reports on an annual basis under 10 CFR 74.13 (or 10 CFR 150.17 for Agreement State licensees). As there have been no reports of lost SNM items from these licensees, the NRC's view is that imposing item control requirements on them is not necessary.

   In a new 10 CFR 74.19(d), the NRC is proposing to expand the requirement to establish an item control system to include reactor facilities licensed under 10 CFR part 50 or 52, and ISFSIs licensed under 10 CFR part 72. This requirement is consistent with guidance developed for the reactor industry by the American National Standards Institute (ANSI) in ANSI N15.8 (``Methods of Nuclear Material Control--

   Material Control Systems--Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants''), dated February 18, 2009. In June 2013, the NRC published Regulatory Guide (RG) 5.29, ``Nuclear Material Control Systems for Nuclear Power Plants'' (Revision 2), which endorses use of the ANSI N15.8 guidance. Requiring item control systems at reactors and ISFSIs would ensure that SNM is adequately accounted for at these sites.

   Licensed Category III fuel fabrication and uranium enrichment facilities are already subject to item control requirements under 10 CFR 74.31(c)(6) and 74.33(c)(6), respectively. Similarly, licensees of Category II facilities are subject to item control requirements under 10 CFR 74.43(b)(6). These requirements are being modified, in part, by removing the exemption provisions for items existing for less than 14 days. These exemptions date from when most facilities did not have, as part of their MC&A programs, automated tracking systems and computer-

   based accounting systems to help track SNM items. Today, licensees have the ability to track items immediately upon creation instead of waiting for hand-written ledgers to be updated. Removing these exemptions will require tracking of items that could contain large quantities of SNM but are not now subject to a facility's item control system.

   The 10 CFR 74.31(c)(6) and 74.33(c)(6) requirements would further be modified by removing the exemptions for individual items containing less than 500 grams of uranium-235, which may contain up to a cumulative total of 50 kilograms of uranium-235. Similarly, for a Category II facility, the exemption (in 10 CFR 74.43(b)(6)) for individual items containing less than 200 grams of plutonium or uranium-233; or 300 grams or more of uranium-235 up to a cumulative total of one formula kilogram of strategic SNM; or 17 kilograms of uranium-235 contained in uranium enriched to 10 percent or more but less than 20 percent in the uranium-235 isotope, would be removed. By not allowing large quantities of SNM to be exempt from a Category II or Category III facility's item control system, a more complete and comprehensive inventory would be achieved. Further, since all licensees are required by existing 10 CFR 74.11 to report the loss of 1 gram or more of SNM, removing these item control exemptions increases the internal consistency of the MC&A requirements.

   Category I facilities are subject to the item monitoring requirements in 10 CFR 74.55, which are not being changed in this rulemaking. Consistent with the present graded approach, these subpart E item monitoring requirements are part of the more stringent MC&A program that applies to Category I facilities. Item monitoring differs significantly from item control. As compared to the item control requirements applicable to Category II and III facilities, the item monitoring requirements in 10 CFR 74.55 are more stringent and rigorous with respect to the scope of item test frequencies, statistical sampling plans, and detection limits. The NRC has found no problems with the item monitoring programs used by Category I licensees, and therefore no changes to 10 CFR 74.55 are proposed.

   Tamper-Safing

   The NRC proposes to strengthen the existing MC&A requirements related to tamper-safing containers and vaults that contain SNM. The term tamper-safing would be defined as the use of devices on containers or vaults in a manner and at a time that ensures a clear indication of any violation of the integrity of previously made measurements of SNM within the container or vault.

   Category I and II facilities are required to follow tamper-safing requirements by existing 10 CFR 74.59(f)(2)(i) and 10 CFR 74.43(c)(3), respectively. By adding 10 CFR 74.31(c)(9) and 74.33(c)(9), the NRC proposes to make tamper-safing requirements applicable to licensed Category III fuel fabrication and uranium enrichment facilities as well. Such licensees would be required to develop tamper-safing procedures and use tamper-safing devices on containers or vaults holding SNM. These procedures must ``include control of access to, and distribution of, unused seals and records.'' The quoted language is part of existing 10 CFR 74.43(c)(3), and would be added to existing 10 CFR 74.59(f)(2)(i) so that the tamper-safing requirements in subparts C, D, and E of 10 CFR part 74 would be similarly worded. As the intent of the tamper-safing requirement remains the same, the changes in wording are not expected to affect the MC&A programs at Category I and II facilities.

   The proposed 10 CFR 74.31(c)(9) and 74.33(c)(9) would incorporate as requirements common practices and procedures already used at Category III facilities, and would supplement and strengthen their existing SNM item control and inventory programs that help to protect against the unauthorized and unrecorded removal of SNM. All Category III facilities routinely tamper-safe containers of SNM, so this regulatory change is not expected to be a burden for the affected licensees.

   The use of tamper-safing procedures would not be required at other types of NRC-licensed facilities, since SNM at such facilities is generally not in forms where tamper-safing seals can be applied. At reactors, for example, fuel assemblies are not amenable to tamper-

   safing because the fuel assemblies are not stored in containers where unauthorized opening of a container could be detected with a tamper-

   safing device. Containers for spent fuel at ISFSIs are welded shut and are sufficiently difficult to open that tamper-safing is not required. At facilities where only sealed sources are used (e.g., at industrial, academic, and research facilities authorized to possess 350 grams or less of SNM), tamper-safing is not required because the manner in which the sealed sources are manufactured and sealed adequately prevents removal of the SNM.

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   Material Balance Areas, Item Control Areas, and Custodians

   As previously discussed, the NRC proposes to add a definition of an ICA to 10 CFR 74.4. Similarly, the NRC proposes to add a definition of an MBA to 10 CFR 74.4. The term material balance area would be defined as a designated contiguous area in which the control of SNM is such that the quantity of material being moved into, out of, and within the MBA is an assigned value based on measurements of both the element content and the isotopic content, if known.

   The proposed rule adds requirements that all Category I, II, and III licensees must designate ICAs and MBAs at their facilities, and identify custodians who would be responsible for monitoring these areas. The proposed requirements are set forth in 10 CFR 74.59(h)(5), 74.43(c)(9), 74.31(c)(10), and 74.33(c)(10). These required areas form the basis for nuclear material accounting and control of all SNM within a Category I, II, or III facility's boundaries, and these new requirements are expected to enhance the capability of licensees to detect the unauthorized removal of SNM. In general, smaller accounting areas make control of SNM easier, and reduce the size of the area in which detected losses of SNM can be attributed.

   All Category I and III facilities (there are no operating Category II facilities) are voluntarily using MBAs and ICAs and have designated custodians assigned to them, so these proposed regulations are not expected to result in significant operating changes.

   The rule change would require future facilities to follow this best practice for ensuring that timely and accurate information is kept within a designated area to adequately account for and control SNM.

   Licensees at other types of NRC-licensed facilities do not use complex processing operations involving large quantities of SNM in multiple forms and their operations do not involve moving SNM frequently throughout the facility. Accordingly, the NRC is proposing to make these MBA, ICA, and custodian requirements applicable only to licensed Category I, II, and III facilities.

   Other Proposed Changes to the Material Control and Accounting Requirements

   Other proposed changes to the MC&A requirements are considered to be non-substantive (in that they are either plain language revisions to improve clarity, conforming changes, or are otherwise organizational or administrative in nature) are summarized as follows:

   The MC&A requirements for ISFSIs that are currently located in 10 CFR part 72 would be relocated to 10 CFR part 74, including requirements for reporting to the Nuclear Materials Management and Safeguards System (NMMSS). These 10 CFR part 72 requirements duplicate reporting requirements in existing subpart B of 10 CFR part 74 and duplicate similar reporting requirements applicable to certain types of source material as specified in 10 CFR 40.64. The following list shows how 10 CFR part 74 requirements relate to the 10 CFR part 72 requirements being removed:

   The requirement for recordkeeping at 10 CFR 72.72(a) would be covered in proposed 10 CFR 74.19(d).

   The requirement for physical inventory at 10 CFR 72.72(b) would be covered in 10 CFR 74.19(c).

   The requirement for written MC&A procedures at 10 CFR 72.72(c) would be covered in 10 CFR 74.19(b).

   The requirement for recordkeeping at 10 CFR 72.72(d) would be removed.

   The requirement to report loss of SNM at 10 CFR 72.74 would be covered in 10 CFR 74.11.

   The requirement for submitting material status reports to NMMSS at 10 CFR 72.76 would be covered in 10 CFR 74.13.

   The requirement for submitting nuclear material transaction reports to NMMSS at 10 CFR 72.78 would be covered in 10 CFR 74.15.

   Revisions are proposed to 10 CFR 72.72 and 72.74, and 10 CFR 72.76 and 72.78 would be deleted. Revisions would be made to 10 CFR 40.64 and 150.17(b) to remove their references to 10 CFR part 72 material status reports.

   Because some licensees have expressed confusion as to what MC&A requirements apply to a particular facility, the NRC proposes to revise the 10 CFR part 74 definitions of formula quantity, special nuclear material of moderate strategic significance, and special nuclear material of low strategic significance by conforming them to the existing definitions in 10 CFR parts 70 and 73, making clear that these classes of SNM are what is referred to, respectively, as Category I, II, and III quantities of material. Licensees authorized to possess Category I material are subject to the 10 CFR part 74 subpart E requirements, while licensees authorized to possess Category II and III material are subject to the subpart D and C requirements, respectively. To further clarify these divisions, the staff proposes to add appendix A (``Categories of SNM'') to 10 CFR part 74. Also for purposes of clarification, the NRC proposes to add defined terms for accounting and material control and accounting.

   Plain language revisions are reflected in the proposed regulations, and include replacing the existing references to the fundamental nuclear material control (FNMC) plan with references to an MC&A plan. The staff's view is that FNMC is an outdated term and does not include ``accounting;'' thus, it does not fully describe the accounting aspects of an MC&A program. Licensees would not be required to change the name of their FNMC plans to MC&A plans.

   The defined term effective kilograms of special nuclear material (and references to it in several provisions) would be removed from 10 CFR part 74. Quantities of SNM would instead be expressed in gram units to simplify the accounting requirements in 10 CFR part 74 and provide consistency with the existing 10 CFR part 74 definitions of the various types of SNM, all of which specify quantities in gram units. This proposed change would also correct an inconsistency within the current 10 CFR 74.19 provisions. Existing 10 CFR 74.19(b) refers to a quantity of SNM ``exceeding one effective kilogram'' in specifying the set of licensees that must establish written MC&A procedures. Existing 10 CFR 74.19(c) refers to a quantity of SNM ``greater than 350 grams'' in specifying the set of licensees that must conduct physical inventories. Removing effective kilograms of special nuclear material from 10 CFR part 74 would also eliminate confusion caused by a conflict between the regulatory thresholds for the SNM categories (Category I, Category II, and Category III) and an effective kilogram of SNM. Effective kilograms of special nuclear material would remain as a defined term in 10 CFR parts 40, 70, 75, 76, and 110, to ensure the continued effective implementation of the U.S./International Atomic Energy Agency (IAEA) Safeguards Agreement.

   Other proposed changes include revising 10 CFR 150.17(a) to conform with the proposed plain language revisions to 10 CFR 74.13. The instructions for material status reporting would be clarified in 10 CFR 74.13. The intervals and due dates for each type of facility would also be clarified in 10 CFR 74.13. No substantive changes are being proposed in this regard and licensees authorized to possess SNM under a license from an Agreement State would continue to submit material status reports to the NRC via the NMMSS. References to due dates and reporting frequencies would be made more uniform by expressing most timeframes in terms of calendar days (e.g., 7, 30, 60, 65, 95, 185, or 370

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   calendar days). The interval for the number of months assigned to a licensee`s assessment of the MC&A program would be retained (e.g., 12 months, 18 months, or 24 months). The retention period for records would be retained (e.g., 3 years). An appendix A, ``Categories of Special Nuclear Material,'' would be added to 10 CFR part 74. The appendix would be based on existing appendix M to 10 CFR part 110, and would show the SNM quantity limits for Category I, Category II, and Category III facilities. The new appendix would also show the corresponding subpart in 10 CFR part 74 for each category, and the formulae to calculate any combination of SSNM within the quantity limits for a category. A conforming change would be made to replace the reference to 10 CFR 74.51(c) with 10 CFR 74.51(b) because the paragraph designation regarding implementation of an MC&A plan would then be consistent with the other citations listed in 10 CFR 70.32(c)(1)(i) and (iii) that refer to paragraph (b) in 10 CFR 74.31, 74.33, and 74.41.

   The SECY-09-0082 (``Update on Reprocessing Regulatory Framework--

   Summary of Gap Analysis,'' ADAMS Accession No. ML091520280), dated May 28, 2009, included the NRC staff's recommendation that the existing 10 CFR 74.51(a) exemption for an irradiated fuel reprocessing plant be removed as part of this rulemaking. Proposed 10 CFR 74.51(a)(2) reflects the removal of this exemption.

   The NRC placed on www.regulations.gov a preliminary version of the proposed rule language to inform stakeholders of the status of the proposed rulemaking and invited stakeholders to provide informal comments by June 30, 2011. Thirteen comment letters were received by this date, and were considered. Public input at this stage helped to develop the proposed rule in its current form.

   III. Specific Request for Comments on the Proposed New Requirements

   In addition to the general opportunity to submit comments on the proposed rule, the NRC also requests comments on the following questions about the proposed new requirements:

   General Performance Objectives:

   In 10 CFR 74.3, the NRC proposes GPOs that would apply to all licensees authorized to possess greater than 350 grams of SNM. Are there other GPOs that the NRC should consider adding? Do the proposed GPOs impose unnecessary expenses or burdens on licensees? Should the regulatory threshold for GPOs be higher or lower than 350 grams, and if so, why? If this threshold amount is lower than 350 grams, the NRC would add a similar set of GPO requirements to 10 CFR part 150 to apply to Agreement State licensees. If that were done, how could the NRC best ensure compliance with the GPOs in Agreement States?

   Item Control System:

   In 10 CFR 74.19(d), the NRC proposes to make item control requirements applicable to licensed reactors and ISFSIs. Licensees of fuel cycle facilities authorized to possess Category III amounts of SNM are subject to existing item control requirements in subpart C of 10 CFR part 74, and subpart D of 10 CFR part 74 contains item control requirements that would be applicable to any future fuel cycle facility that may be authorized to possess Category II amounts of SNM. Are such requirements necessary at reactor and ISFSI sites? Are there alternatives that should be considered? Should other types of licensees be required to have an item control system? What is the appropriate regulatory threshold for requiring an item control system under 10 CFR part 74? Should there be a threshold for the amount of material that is required to be tracked under an item control system?

   Tamper-Safing:

   In 10 CFR 74.31(c)(9) and 74.33(c)(9), the NRC proposes a new requirement for tamper-safing containers and vaults. The NRC also proposes clarifying the existing requirements for tamper-safing in 10 CFR 74.43(c)(3) and 74.59(f)(2)(i) to provide a consistent approach for all Category I, II, and III licensees. Should tamper-safing be required for Category III licensees? Are there alternative measures that should be considered?

   Material Balance Areas, Item Control Areas, and Custodians:

   In 10 CFR 74.31(c)(10), 74.33(c)(10), and 74.43(c)(9), the NRC proposes a new requirement to identify specific MBAs and ICAs, and to designate custodians for these areas. The NRC also proposes that the existing requirement for custodians in 10 CFR 74.59(h)(5) be revised to match the new language to provide a consistent approach for all Category I, II, and III licensees. Should use of MBAs and ICAs be required? Should other facilities be required to have MBAs and ICAs? Are there alternatives that should be considered?

   Alternatives resulting in equivalent outcome and less burden:

   Throughout this proposed rule, the NRC is proposing measures that would strengthen MC&A requirements at licensee sites. Are there alternative ways to strengthen existing MC&A requirements that would impose less burden on NRC licensees while still maintaining adequate control and accounting of SNM? What specific alternatives should be considered? For the proposed requirements that go beyond consolidation and clarification, the NRC is seeking input on the need for such requirements in relation to the proportionate levels of risk represented by the processes and material quantities and forms of SNM that are used at different types of licensee facilities.

   IV. Discussion

   To further describe this proposed rulemaking the following series of questions and answers is set forth.

1. Whom would this action affect?

   Licensees authorized by the NRC to possess SNM in a quantity greater than 350 grams would be affected by the proposed rule. For example, the proposed 10 CFR 74.3 would require a licensee authorized to possess a quantity of SNM greater than 350 grams to implement and maintain a material control and accounting program that enables the licensee to achieve the GPOs provided in the new 10 CFR 74.3.

   Agreement State licensees authorized to possess SNM are subject to the 10 CFR 150.17 material status reporting requirements. The proposed changes to these requirements are plain language revisions, and conform with the proposed plain language revisions to the 10 CFR 74.13 material status reporting requirements. These changes do not require any action by the Agreement State licensees.

2. Why are the requirements being revised?

   Many of the current MC&A requirements were developed over 20 years ago and need to be updated to include commonly used terms. Item control system requirements would be strengthened by including items that are currently exempted from these requirements. The requirements for general performance objectives to deter, detect, or aid in responding to any loss, theft, diversion or misuse of SNM need to be extended to NRC licensees who are not authorized to possess Category I, II, or III amounts of material, but who are authorized to possess SNM in a quantity greater than 350 grams. The NRC's view is that all MC&A regulations governing SNM held by NRC licensees should be in 10 CFR part 74 in order to provide a focal point and a complete framework/

   umbrella for controlling and accounting for all SNM under NRC oversight.

   Page 67231

3. When would these actions become effective?

   The NRC expects that the final rule would be published within 12 months of the publication of the proposed rule for comment. The revisions to the regulations would become effective 90 days after the publication of the final rule. Question R in this section requests comments on the cumulative effects of this rulemaking and specifically asks whether an effective date of 6 months from the date the final rule is published in the Federal Register would provide sufficient time to implement the new proposed requirements.

4. How does NRC use a graded approach for MC&A?

   The NRC currently uses a graded, risk-informed approach for MC&A. Based on the quantity and form of material a licensee possesses, the licensee is subject to specific requirements that increase with the amount of SNM the licensee is authorized to possess. Table 2 shows the requirements that apply to various types of licensed facilities based on their possession limits and how the NRC proposes to strengthen requirements through this rulemaking.

   Table 2--NRC's Graded, Risk-Informed Approach to Material Control and Accounting

   ----------------------------------------------------------------------------------------------------------------

   Grams of SNM the licensee is Current MC&A requirements in 10 CFR Proposed changes to strengthen MC&A

   authorized to possess Part 74 requirements in 10 CFR Part 74

   ----------------------------------------------------------------------------------------------------------------

   1 gram or more of SNM (all 74.11/150.16 Reporting loss and Existing 74.19(d) would be moved to

   licensees, including part 70 theft. 74.19(e) to accommodate a new item

   licensees authorized to possess 350 74.13/150.17 Material status reports control requirement for reactors

   grams or less and licensees for NMMSS. and ISFSIs.

   authorized by an Agreement State). 74.15/150.16 Material transaction

   reports for NMMSS.

   74.19(a) Recordkeeping.

   74.19(d) Retention of records.

   ----------------------------------------------------------------------------------------------------------------

   >350 grams of SNM (part 70 licensees 74.11 Reporting loss and theft. New GPOs in 74.3.

   authorized for industrial, 74.13 Material status reports for To replace the term ``one effective

   academic, and research types of NMMSS. kilogram,'' 74.19(b) would apply to

   use. 74.15 Material transaction reports licensees possessing greater than

   for NMMSS. 350 grams of SNM.

   74.19(a) Recordkeeping. Existing 74.19(d) would be moved to

   74.19(b) Written procedures. 74.19(e) to accommodate a new item

   74.19(c) Physical inventory. control requirement for reactors

   74.19(d) Retention of records. and ISFSIs.

   ----------------------------------------------------------------------------------------------------------------

   Reactors licensed under part 50 or 74.11 Reporting loss and theft. New GPOs in 74.3.

   part 52 and ISFSIs licensed under 74.13 Material status reports for New requirement for item control in

   part 72. NMMSS. 74.19(d).

   74.15 Material transaction reports Existing 74.19(d) would be

   for NMMSS. designated as 74.19(e).

   74.19(a) Recordkeeping.

   74.19(b) Written procedures.

   74.19(c) Physical inventory.

   74.19(d) Retention of records.

   ----------------------------------------------------------------------------------------------------------------

   >350 grams of SNM of low strategic 74.11 Reporting loss and theft. 74.31(a)(1)-(3) GPOs would be

   significance (also known as 74.13 Material status reports for revised and relocated to 74.3.

   Category III facilities). NMMSS. 74.31(b) Replace FNMCP with MC&A

   Current threshold of one effective 74.15 Material transaction reports Plan.

   kilogram would be replaced with 350 for NMMSS. Remove two exemptions related to

   grams. 74.17 Physical inventory summary item control in 74.31(c)(6).

   report. New requirement for tamper-safing in

   74.31: 74.31(c)(9).

   (a) GPOs. New requirement for MBAs and ICAs

   (b) FNMCP. and for custodians in 74.31(c)(10).

   (c)(1) Management and procedures.

   (c)(2) Measurement.

   (c)(3) Measurement control.

   (c)(4) SEID.

   (c)(5) Physical inventory.

   (c)(6) Item control.

   (c)(7) Shipper-receiver differences.

   (c)(8) Assessments.

   (d) Recordkeeping and retention.

   ----------------------------------------------------------------------------------------------------------------

   Page 67232

   >350 grams of SNM of low strategic 74.11 Reporting loss and theft. 74.33(a)(1)-(9) GPOs revised and

   significance for uranium enrichment 74.13 Material status reports for relocated to 74.3, except for five

   facilities, (also known as Category NMMSS. retained in proposed 74.33(a)(1)-

   III enrichment facilities). 74.15 Material transaction reports (5).

   Current threshold of one effective for NMMSS. 74.33(b) Replace FNMCP with MC&A

   kilogram would be replaced with 350 74.17 Physical inventory summary Plan.

   grams. report. Remove two exemptions related to

   74.33: item control in 74.33(c)(6).

   (a) GPOs. New requirement for tamper-safing in

   (b) FNMCP. 74.33(c)(9).

   (c)(1) Management and procedures. New requirement for MBAs and ICAs

   (c)(2) Measurement. and custodians in 74.33(c)(10).

   (c)(3) Measurement control.

   (c)(4) Physical inventory.

   (c)(5) Detection program.

   (c)(6) Item control.

   (c)(7) Shipper-receiver differences.

   (c)(8) Assessments.

   (d) Recordkeeping and retention.

   ----------------------------------------------------------------------------------------------------------------

   >1000 grams of SNM of moderate 74.11 Reporting loss and theft. 74.41(a)(1)-(4) GPOs revised and

   strategic significance (there is 74.13 Material status reports for relocated to 74.3.

   currently no operating Category II NMMSS. 74.41(b) Replace FNMCP with MC&A

   facility or applicant for such a 74.15 Material transaction reports Plan.

   license). for NMMSS. Remove two exemptions related to

   Current threshold of one effective 74.17 Physical inventory summary item control in 74.43(b)(6).

   kilogram would be replaced with report. Reword the requirement for tamper-

   1000 grams. 74.41: safing in 74.43(c)(3).

   (a) GPOs. New requirement for MBAs and ICAs

   (b) FNMCP. and custodians in 74.43(c)(9).

   (c) Checks and balances.

   74.43:

   (b)(1)-(4) Management and

   procedures.

   (b)(5)-(6) Item control.

   (b)(7) Shipper-receiver differences.

   (b)(8) Assessments.

   (c)(1) Identification of items.

   (c)(2) Documenting transfers.

   (c)(3) Tamper-safing.

   (c)(4) Validity of prior

   measurements.

   (c)(5)-(8) Physical inventory.

   (d) Recordkeeping and retention.

   74.45:

   (b) Measurements.

   (c) Measurement control.

   ----------------------------------------------------------------------------------------------------------------

   >5000 grams of formula quantities of 74.11 Reporting loss and theft. 74.51(a)(1)-(5) GPOs revised and

   strategic SNM (also known as 74.13 Material status reports for relocated to 74.3, except for three

   Category I facilities). NMMSS. retained in proposed 74.33(a)(1)(i)-

   Current threshold of five formula 74.15 Material transaction reports (iii).

   kilograms would be replaced with for NMMSS. Removed the exemption for irradiated

   5000 grams. 74.17 Physical inventory summary fuel reprocessing plants in

   report. 74.51(a).

   74.51: Switching 74.51(b) and (c) for

   (a) GPOs. consistency with other sections of

   (b) Checks and balances. part 74.

   (c) FNMCP. New 74.51(b) Replace FNMCP with MC&A

   (d) Bimonthly physical inventory. Plan.

   74.53 Process monitoring. Reword the requirement for tamper-

   74.55 Item monitoring. safing in 74.59(f)(2)(i).

   74.57 Alarm resolution. Revise the requirement for

   74.59: custodians to include new

   (a) Quality assurance. requirement for MBAs and ICAs in

   (b) Management and procedures. 74.59(h)(5).

   (c) Qualification and training.

   (d) Measurements.

   (e) Measurement control.

   (f) Physical inventory.

   (f)(2)(i) Tamper-safing.

   (g) Accounting records retention.

   (h)(1) Shipper-receiver differences.

   (h)(2) Scrap control.

   (h)(3) Checks and balances for human

   error.

   (h)(4) Assessments.

   (h)(5) Custodians.

   ----------------------------------------------------------------------------------------------------------------

   Page 67233

5. What are the changes to the general performance objectives?

   The existing GPOs in 10 CFR 74.31(a) and 74.33(a) (applicable to licensees of Category III facilities), 74.41(a) (applicable to licensees of Category II facilities), and 74.51(a) (applicable to licensees of Category I facilities) would be revised by consolidating their common provisions into a new 10 CFR 74.3. In addition to being applicable to Category I, II, and III facilities, the 10 CFR 74.3 GPOs would be applicable to reactor licensees and two NRC materials licensees that are authorized to hold more than 350 grams of SNM, but are not Category I, II, or III facilities. The proposed 10 CFR 74.3 GPOs describe activities to deter, detect, or aid in responding to any loss, theft, diversion or misuse of SNM. The existing GPO provisions in 10 CFR 74.31, 74.33, 74.41, and 74.51 would be revised to refer to 10 CFR 74.3, but GPOs that are unique to uranium enrichment facilities and Category I fuel fabrication facilities would be retained in 10 CFR 74.33 and 74.51.

6. Are sealed sources included in the general performance objectives for Category II and III facilities?

   Yes. The current exclusion for sealed sources in the 10 CFR 74.31 and 74.41 GPO provisions would be relocated to appendix A (Note 1) to clarify that the sealed sources would not be considered for determining whether a facility is a Category III facility or a Category II facility, respectively. The change would be consistent with the current requirements, which were intended to exclude sealed sources from the material quantity calculations used to determine whether a facility is a Category III facility subject to subpart C requirements, or a Category II facility subject to the subpart D requirements of 10 CFR part 74. However, sealed sources would be within the scope of the proposed 10 CFR 74.3 GPOs. Sealed sources would continue to be subject to a licensee's MC&A program.

7. Why would newly defined terms be added to 10 CFR 74.4?

   Certain terms are commonly used by licensees in their internal procedures implementing their MC&A systems, plans and programs, including accounting, custodian, material control and accounting. Defining these terms in the NRC's regulations would clarify the requirements and improve under- standing of the regulations. Other newly defined terms (material balance area and item control area) and their related requirements are deemed necessary to strengthen the MC&A requirements at facilities holding significant amounts of SNM, thereby making diversion or misuse of SNM at such facilities less likely.

8. Why would the term ``effective kilograms of special nuclear material'' be removed from 10 CFR part 74?

   Doing so would allow quantities of SNM specified in 10 CFR part 74 to be expressed in gram units, which would simplify the accounting requirements and provide consistency with the existing definitions of formula quantity, special nuclear material of low strategic significance, and special nuclear material of moderate strategic significance, which specify quantities in gram units. The reference to one effective kilogram in the 10 CFR 74.19(b) written MC&A procedures provision would be replaced with a reference to a quantity of SNM greater than 350 grams. This 350-gram amount is referenced in existing 10 CFR 74.19(c) regarding the physical inventory provisions stated there. References to one effective kilogram in the GPO provisions of 10 CFR 74.31, 74.33, and 74.41 would be revised to reference gram units of material. The new appendix A would also use gram units. The effective kilogram term would remain in 10 CFR parts 40, 70, 75, 76, and 110, to ensure the continued effective implementation of the U.S./IAEA Safeguards Agreement.

   I. Why would appendix A to 10 CFR part 74 be added?

   Appendix A would be added to clarify the definitions and quantities and units of the various categories of SNM. Similar information is provided in existing appendix M to 10 CFR part 110 and would be appended to 10 CFR part 74 as well for the convenience of licensees, the NRC staff, and members of the public. Appendix A would clarify the elements, isotopic composition, and quantities of material that Category I, Category II, and Category III facilities are authorized to possess. Notes would be included to clarify that sealed sources are excluded from the quantity limits that are used to determine the category of a facility. An additional note is included to clarify that spent nuclear fuel is reduced one category level during the period of time that the radiation exposure exceeds 1 Sievert (Sv) per hour (100 rads per hour) at 1 meter, unshielded. Formulae are included to calculate a quantity of material for Category I, Category II, or Category III.

10. Why would references to the MC&A ``system'' be changed to the MC&A ``program,'' and why would ``MC&A plan'' replace ``FNMC plan?''

    Portions of existing 10 CFR part 74 that refer to the MC&A ``system'' (e.g., 10 CFR 74.31(c), 74.33(a), and 74.51(a)) would be revised to instead refer to the MC&A ``program.'' The term ``program'' better describes the over-arching, comprehensive set of methods licensees use to control and track SNM, and using ``program'' avoids confusion with the required material measurement systems (e.g., 10 CFR 74.31(c)(2), 74.33(c)(3), and 74.59(d)) that are part of the overall MC&A program. Similarly, existing references to the overall ``system'' capabilities would be changed to ``program'' capabilities. The existing requirements referring to an item control program (e.g., 10 CFR 74.31(c)(6), 74.33(c)(6) and 74.43(b)(5)) would be revised to instead refer to an item control system.

    Replacing the existing references to the ``FNMC plan'' with references to an ``MC&A plan'' is necessary in the NRC staff's view because FNMC is an outdated term and does not include accounting. It does not fully describe the accounting aspects of the MC&A program, and is not consistent with the general title of 10 CFR part 74 (``Material Control and Accounting of Special Nuclear Material''). The term MC&A plan is not intended to be an exact name that licensees are required to use and licensees will not be required to change the names of their existing plans.

11. What would change in the reporting requirements to NMMSS, including those that ISFSIs are subject to?

    The proposed addition of numbered subsections to 10 CFR 74.13(a) would make these reporting requirements easier to read and understand. The plain language revisions would make no substantive changes to the existing requirements.

    The NMMSS reporting requirements for an ISFSI currently in Sec. 72.76 for material status reports and in Sec. 72.78 for nuclear material transaction reports are duplicated in Sec. Sec. 74.13 and 74.15, respectively. Proposed 10 CFR 74.2 would include existing ISFSIs within the scope of 10 CFR part 74. Accordingly, Sec. Sec. 72.76 and 72.78 would be removed from 10 CFR part 72. The requirements in Sec. 72.72 for storage of source material (SM) and SNM would be revised to direct a licensee to refer to Sec. Sec. 40.61 and 40.64 for SM and to subparts A and B in 10 CFR part 74 for SNM.

    Page 67234

    L. Is a two-person rule included as part of this proposed rule?

    No. Earlier in this rulemaking process, the NRC staff developed proposed provisions that would have required Category I, II, and III licensees to have two qualified and authorized individuals present when--

    Tamper-safing devices are applied to SNM containers,

    physical inventories are performed,

    SNM is transferred, and

    SNM that is not under an active control measure is handled.

    The Commission in its May 10, 2013, SRM, disapproved publishing the proposed requirements. The SRM stated that the staff could conduct a backfit analysis on the proposed two-person rule or, to avoid a significant delay in publishing this MC&A rule for comment, remove these provisions and consider a two-person rule in a separate future MC&A rulemaking effort. Interested members of the public will have the opportunity to comment on a two-person rule in any such future rulemaking.

13. Why would requirements be added to designate material balance areas, item control areas, and custodians?

    The added MC&A requirements would strengthen and specifically define the terms for MBA, ICA, and custodians. The added requirements would be consistent in requiring licensees under subparts C, D, and E to designate MBAs and ICAs and custodians for these areas. The terms are widely used in the regulated community and 10 CFR part 74 would be clarified by setting forth the specific definition for the terms in 10 CFR 74.4. A licensee would be required to designate MBAs, ICAs, and assign custodial responsibilities for these areas to provide internal controls to deter or detect any diversion or misuse of SNM at the licensee's facility.

14. Why would calendar days be inserted into 10 CFR part 74?

    To clarify 10 CFR part 74, references to due dates and reporting frequencies would be made more uniform by expressing most timeframes in calendar days. Using calendar days avoids the existing uncertainty over whether weekends and holidays are counted in determining whether or not a licensee has taken timely action. The proposed clarifications are intended to make 10 CFR part 74 more internally consistent with existing 10 CFR 74.33(c)(4), which requires that annual static physical inventories be taken ``at least every 370 calendar days.'' Existing 10 CFR part 74 provisions referencing 6-month intervals would be changed to ``185 calendar days.''

15. Would the implementation guidance documents be updated for the MC&A program?

    The following guidance documents would be revised and updated in conjunction with the rulemaking effort. In addition, a guidance document for Category II facilities (SNM of Moderate Strategic Significance) would be updated and issued with the following existing guidance documents. All revised NUREG guidance documents will be available for public comment in parallel with the scheduled publication of the proposed rule.

    i. NUREG-1280, ``Standard Format and Content Acceptance Criteria for the MC&A Reform Amendment,''

    ii. NUREG-1065, ``Acceptable Standard Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Required for Low-

    Enriched Uranium Facilities,''

    iii. NUREG/CR-5734, ``Recommendations to the NRC on Acceptable Standard Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Required for Low-Enriched Uranium Enrichment Facilities,''

    iv. NUREG/BR-0096, ``Instructions and Guidance for Completing Physical Inventory Summary Report.''

16. Would there be changes for item controls or physical inventories?

    Subpart B in 10 CFR part 74 would be revised to include a new requirement in 10 CFR 74.19(d) that licensees of power reactors and ISFSIs must establish, document, implement, and maintain an item control system (as would be defined in 10 CFR 74.4).

    Some of the current exemption provisions for item controls would be removed. Specifically, the exemption provisions in 10 CFR 74.31(c)(6), 74.33(c)(6)(ii) and 74.43(b)(6) for items existing 14 days or less in Category III and II facilities would be removed. The 14-day exemption was put in the current regulations at a time when most Category III licensees did not have computer inventory controls and instead relied on manual ledger entries. In other words, the current regulation aligned the risk with what the licensees could do in a production environment.

    However, over the last several years, licensees have implemented business systems that track SNM containing items through the use of bar codes and entries to computer systems. This has had the secondary benefit of giving these licensees the ability to track individual items and total inventory in near real time. Licensees have demonstrated this ability numerous times during inspections by the NRC staff.

    Current requirements in 10 CFR part 74 recognize the importance of conducting timely inventories and reporting the results by requiring the reporting of shipments and receipts of a gram or more of material in 10 days (see 10 CFR 74.15) and through the reporting of lost, stolen, or diverted SNM of a gram or more within one hour (10 CFR 74.11). Inspections performed by the NRC have identified cases where there were ``near-misses'' associated with current exemptions. Removal of the exemptions from the item control requirements would align this regulation with other requirements in 10 CFR part 74 to better ensure accurate SNM item bearing inventories. These proposed regulatory changes are not expected to impact licensees significantly since licensees have in-house systems that track such items in near real time.

    Additionally, for Category III facilities, the exemption provisions (in 10 CFR 74.31(c)(6) and 74.33(c)(6)(ii)) for individual items each containing less than 500 grams of uranium-235, up to a total of 50 kilograms of uranium-235, would be removed. For a Category II facility, the exemption (in 10 CFR 74.43(b)(6)) for individual items containing less than 200 grams of plutonium or uranium-233; or 300 grams or more of uranium-235 up to a cumulative total of one formula kilogram of strategic SNM; or 17 kilograms of uranium-235 contained in uranium enriched to 10 percent or more but less than 20 percent in the uranium-

    235 isotope, would be removed. These exemptions were identified for removal in SECY-08-0059. Item control requirements that exclude kilogram amounts of SNM are not consistent with protection of the common defense and security.

17. Why would an exception be added to 10 CFR 74.15(b)(2)?

    The exception from performing independent tests when receiving unirradiated fuel rods or unirradiated fuel assemblies would be included to clarify the requirement for licensees under 10 CFR part 50 or 52. Similarly the requirement would be clarified for a licensee under 10 CFR part 70 receiving SNM contained in a sealed source that will not be opened. The NRC inspection program has indicated that a licensee will typically verify the contents of such shipments by reviewing the shipping papers and visual inspection of the

    Page 67235

    material because independent testing (e.g., destructive testing or sampling) is impractical for determining the contents of the shipment being received.

18. Are there any cumulative effects of regulation associated with this rule?

    Cumulative effects of regulation (CER) describe the challenges that licensees or other impacted entities (such as State partners) face while implementing new regulatory positions, programs, or requirements (e.g., rules, generic letters, backfits, inspections). The CER are organizational effectiveness challenges that result from a licensee or impacted entity implementing a number of complex regulatory positions, programs or requirements within a limited implementation period and with available resources (which may include limited available expertise to address a specific issue). The CER can potentially distract licensee or entity staff from executing other primary duties that ensure safety or security.

    The NRC is specifically requesting comment on the cumulative effects of this rulemaking. In developing comments on CER, consider the following questions:

    i. In light of any current or projected CER challenges, would an effective date 6 months from the date the final rule is published in the Federal Register provide sufficient time to implement the new proposed requirements?

    ii. If current or projected CER challenges exist, what should be done to address this situation (e.g., if more time is required to implement the new requirements, what period of time would be sufficient)?

    iii. Do other regulatory actions (e.g., orders, generic communications, license amendment requests, and inspection findings of a generic nature) influence the implementation of the proposed requirements?

    iv. Are there unintended consequences? Does the proposed rule create conditions that would be contrary to the proposed rule's purposes and objectives? If so, what are the unintended consequences and how should they be addressed?

    v. Please comment on the NRC's cost and benefit estimates in the regulatory analysis that supports this proposed rule.

19. What should I consider as I prepare my comments to the NRC?

    When submitting your comments, remember to:

    i. Identify the rulemaking (RIN 3150-AI61; NRC-2009-0096).

    ii. Explain why you agree or disagree; suggest alternatives and substitute language.

    iii. Describe any assumptions and include technical information or data that you used.

    iv. If you estimate potential costs or burdens, explain how you arrived at your estimate in sufficient detail to allow for it to be reproduced.

    v. Provide specific examples to illustrate your concerns, and suggest alternatives.

    vi. Explain your views as clearly as possible.

    vii. Submit your comments by the comment period deadline identified.

    viii. The NRC is particularly interested in your comments concerning the issues in Sections Il and III of this document about item controls, designating MBAs, ICAs and custodial responsibilities for these areas. Section VIII, Agreement State Compatibility, of this document contains a request for comment on the compatibility designations for the proposed rule; Section IX, Plain Writing, contains a request for comments on the use of plain language; Section XI, Environmental Assessment and Finding of No Significant Environmental Impact Availability, contains a request for comments on the draft environmental assessment; Section XII, Paperwork Reduction Act Statement, contains a request for comments on the information collection requirements; Section XIII, Regulatory Analysis, contains a request for comments on the draft regulatory analysis; and Section XIV, Regulatory Flexibility Certification, contains a request for comments on the impact of the proposed rule on small businesses.

    V. Discussion of Proposed Amendments by Section

    Section 40.64 Reports.

    Paragraphs (b)(1) and (2) would be revised to remove the reference to 10 CFR part 72.

    Section 70.32 Conditions of licenses.

    Paragraphs (c)(1)(i) and (iii) would be revised to replace the reference to Sec. 74.51(c) with Sec. 74.51(b). These sections were revised to provide consistent organization for subparts C, D, and E in 10 CFR part 74 and a conforming change would be completed in 10 CFR 70.32(c)(1)(i) and (iii).

    Section 72.9 Information collection requirements: OMB approval.

    The NRC proposes to remove Sec. Sec. 72.76 and 72.78 from the list of approved information collections in Sec. 72.9.

    Section 72.72 Material control and accounting requirements for source material and special nuclear material.

    The title of the section would be revised from ``Material balance, inventory, and records requirements for stored materials'' to ``Material control and accounting requirements for source material and special nuclear material.'' Paragraph (a) would be revised to only reference requirements for source material, and would reference Sec. Sec. 40.61 and 40.64 in this regard. The remainder of existing Sec. 72.72 (a), (b), (c), and (d) would be removed because these requirements are duplicated in 10 CFR part 74. As previously discussed, the Sec. 74.2 scoping provisions would be revised to include ISFSIs.

    New paragraph (b) would reference MC&A requirements for SNM in 10 CFR part 74.

    Section 72.74 Reports of accidental criticality.

    The title of this section would be revised from ``Reports of accidental criticality or loss of special nuclear material'' to ``Reports of accidental criticality.'' Paragraph (a) would be revised to remove the requirement that any loss of SNM be reported within 1 hour of discovery. The ISFSIs would be subject to 10 CFR 74.11(a) with regard to any loss of SNM that must be reported within 1 hour of discovery. Section 72.74 would retain its reporting requirement for accidental criticality.

    Paragraph (b) would be revised to state that required one-hour notifications be made to the NRC Headquarters Operations Center via any available telephone system. The outdated reference to the Emergency Notification System would be removed.

    Section 72.76 Material status reports.

    This section would be removed and reserved, and Sec. 72.9 would be changed accordingly.

    Section 72.78 Nuclear material transaction reports.

    This section would be removed and reserved, and Sec. 72.9 would be changed accordingly.

    Section 74.2 Scope.

    The last sentence of paragraph (a) would be revised to bring licensees who possess spent nuclear fuel at ISFSIs within the scope of the MC&A reporting and recordkeeping requirements in 10 CFR part 74.

    Section 74.3 General performance objectives.

    This section would be added to require a licensee authorized by the NRC to possess SNM in a quantity greater than 350 grams to implement and maintain an MC&A program that achieves the general performance objectives listed in paragraphs (a) through (e).

    Section 74.4 Definitions.

    Page 67236

    This section would be revised to remove the definition, Effective kilograms of special nuclear material. This section would be revised to add, in alphabetical order, definitions for the following terms: Accounting, Custodian, Item control area, Item control system, Material balance area, and Material control and accounting. The definitions of the following terms would be revised to conform with the existing definitions of these terms in 10 CFR parts 70 and 73, and to refer to appendix A of this part: Formula quantity, Special nuclear material of low strategic significance, and Special nuclear material of moderate strategic significance.

    Section 74.11 Reports of loss or theft or attempted theft or unauthorized production of special nuclear material.

    Paragraph (b) would be revised to state that required licensee notifications be made to the NRC Headquarters Operations Center via any available telephone system within 1 hour of the event, and an outdated reference to the Emergency Notification System would be removed.

    Section 74.13 Material status reports.

    As discussed further in the following paragraph, plain language revisions would be made to paragraph (a) by specifying eight numbered requirements, and new paragraphs (b), (c), and (e) would be added. Existing paragraph (b) would be designated as paragraph (d).

    Paragraph (a)(1) through (8) would specify deadlines by which various sets of licensees would be required to submit their material balance reports and physical inventory listing reports.

    Paragraph (b) would include the reporting instructions that are in existing Sec. 74.13(a), and would include references to the reporting forms (NUREG/BR-0007 and NMMSS Report D-24, ``Personal Computer Data Input for NRC Licensees'') referenced in existing Sec. 74.13(a).

    Paragraph (c) would retain the provision in existing Sec. 74.13(a) that the reports may be submitted at other times for good cause with prior NRC approval.

    As indicated previously, paragraph (d) restates the existing Sec. 74.13(b) provision regarding reports required under section 75.35 of this chapter (pertaining to implementation of the U.S./IAEA Safeguards Agreement).

    Paragraph (e) would retain the requirement in existing Sec. 74.13(a) regarding the resolution of any discrepancies identified during the report review.

    Section 74.15 Nuclear material transaction reports.

    Paragraph (b)(2) would be revised by adding an exception that independent testing is not required for receipt of unirradiated fuel rods, unirradiated fuel assemblies, or sealed sources containing SNM that will not be opened.

    Section 74.19 Recordkeeping, procedures, item controls, and physical inventories.

    This section's title would be revised to reference written MC&A procedures, item controls, and physical inventories.

    As previously discussed, paragraph (b) would be revised to replace its reference to a quantity of SNM ``exceeding one effective kilogram'' with ``a quantity greater than 350 grams of contained uranium-235, uranium-233, or plutonium, or any combination thereof.''

    Paragraph (d) would be re-designated as paragraph (e) and a new paragraph (d) would be added to require reactor facilities licensed under 10 CFR part 50 or 52 and ISFSIs licensed under 10 CFR part 72 to establish, document, implement, and maintain an item control system. A definition of the term item control system would be added to 10 CFR part 74.4.

    Section 74.31 Nuclear material control and accounting for special nuclear material of low strategic significance.

    The general performance objectives applicable to licensees of Category III fuel fabrication facilities would be set forth in proposed Sec. 74.3 as previously discussed. Revised Sec. 74.31(a)(1) would incorporate the Sec. 74.3 performance objectives by reference, thereby replacing the performance objectives set forth in existing Sec. 74.31(a)(1)-(3). Proposed paragraph (a)(2) would retain elements of the exemption in existing Sec. 74.31(a) applicable to production or utilization facilities, and any licensee operations involving waste disposal. Proposed paragraph (a)(2) would add an exemption for ISFSIs, thereby making it consistent with existing Sec. 74.51(a).

    Paragraph (b) would be revised by replacing the reference to ``a fundamental nuclear material control (FNMC) plan'' with a reference to ``a MC&A plan.'' The plan would need to achieve the general performance objectives in Sec. 74.3, and meet the program capability requirements set forth in revised Sec. 74.31(c).

    The introductory language of paragraph (c) would be revised to state that the MC&A plan must: Include the capabilities described in paragraphs (c)(1) through (10); and achieve the performance objectives in Sec. 74.3. The title of paragraph (c) would be changed from ``System capabilities'' to ``Program capabilities.'' Grammatical errors in existing paragraphs (c)(1) through (3) would be corrected. Paragraph (c)(4) would be clarified to state the standard error as the standard error of the inventory difference (SEID). The paragraph (c)(5) physical inventory timing provisions would be clarified by changing ``60 days'' to ``60 calendar days,'' and grammatical errors in the existing text would be corrected. Paragraph (c)(6) would be revised by referencing the item control system defined in Sec. 74.4. The 14-day provision in the first sentence of the existing requirement would be removed. The reference to detecting ``unauthorized removals of substantial quantities of material from items'' in the second sentence would be changed to require detecting the removal of ``any quantity of material.'' In the third sentence, the existing exemption from the detection requirements for ``items individually containing less than 500 grams of uranium-235 up to a total of 50 kilograms of uranium-235'' would be removed. The wording of paragraph (c)(7) would be revised to state as follows: ``Conduct and document shipper-receiver difference comparisons for all SNM receipts on a total shipment basis, and on an individual batch basis when required by 10 CFR part 75 of this chapter, and ensure that any shipper-receiver difference that is statistically significant and exceeds twice the estimated standard deviation of the difference estimator and 500 grams of uranium-235 is investigated and resolved.'' Paragraph (c)(8) would be revised by referencing the MC&A ``program'' rather than the MC&A ``system.'' Paragraphs (c)(9) and (10) would be added to require that the MC&A program include, respectively, tamper-safing procedures and the designation of material balance areas, item control areas, and custodians responsible for these areas.

    Section 74.33 Nuclear material control and accounting for uranium enrichment facilities authorized to produce special nuclear material of low strategic significance.

    The general performance objectives applicable to Category III uranium enrichment facilities would be set forth in proposed Sec. 74.3 as previously discussed, and revised Sec. 74.33(a) would reflect this. The general performance objectives stated in existing paragraphs (a)(1) through (9) would be replaced by new paragraphs (a)(1) through (4), which would only reference source material. These general performance objectives would parallel those set forth in proposed Sec. 74.3, which would apply only to SNM. New paragraph (a)(5) retains elements of existing paragraph

    Page 67237

    (a)(8), and retains the exemption for centrifuge enrichment facilities stated in existing (a)(5).

    Paragraph (b) would be revised by replacing the reference to ``a fundamental nuclear material control (FNMC) plan'' with a reference to ``an MC&A plan.'' The plan would need to achieve the general performance objectives in Sec. 74.3, the performance objectives in paragraph (a) as previously discussed, and meet the program capability requirements set forth in revised Sec. 74.33(c).

    The introductory language of paragraph (c) would be revised to state that the MC&A plan must: Include the capabilities described in paragraphs (c)(1) through (10); and achieve the performance objectives (as previously referenced). The title of paragraph (c) would be changed from ``System features and capabilities'' to ``Program capabilities.'' Existing paragraphs (c)(1) through (2) would remain unchanged. Paragraph (c)(3)(ii) would be clarified to include the acronym SEID in a parenthetical. Paragraph (c)(4)(i) would be clarified by changing ``65 days'' to ``65 calendar days.'' Paragraph (c)(4)(ii) would be clarified by changing ``60 days'' to ``60 calendar days,'' and a grammatical correction to the existing regulatory text would be made. Paragraph (c)(5) would be revised by adding ``resolving'' at the end of the introductory sentence, to read, ``A detection program, independent of production, that provides high assurance of detecting and resolving.'' Paragraph (c)(6) would be revised by deleting (c)(6)(i) and (ii). Paragraph (c)(6) would instead reference the item control system defined in Sec. 74.4. The requirement to have such an item control system replaces the existing Sec. 74.33(c)(6)(i) requirement. The reference to detecting the ``unauthorized removal of 500 grams or more of uranium-235'' in existing Sec. 74.33(c)(6)(ii) would be changed to require detecting the removal of ``any quantity of uranium-

    235.'' The existing exemption in Sec. 74.33(c)(6)(ii) from the detection requirements for items containing ``less than 500 grams of uranium-235 up to a cumulative total of 50 kilograms of uranium-235,'' and for items that ``exist for less than 14 calendar days,'' would be removed. This exemption would be replaced with a provision exempting items in solution with a concentration of less than 5 grams per liter, and waste items destined for burial or incineration (the proposed wording here tracks the portion of the Sec. 74.31(c)(6) exemption that is being retained). Paragraph (c)(7) would be clarified to state the requirements to conduct and document shipper-receiver difference comparisons for all SM and SNM receipts on a total shipment basis and on an individual batch basis when required by 10 CFR part 75 of this chapter, and that any shipper-receiver difference that is statistically significant and exceeds twice the estimated standard deviation of the difference and 500 grams of uranium-235 must be investigated and resolved. Paragraph (c)(8) would be revised by referencing the MC&A ``program'' rather than the MC&A ``system.'' Paragraphs (c)(9) and (10) would be added to require that the MC&A program include, respectively, tamper-safing procedures and the designation of MBAs, ICAs, and custodians responsible for these areas.

    Section 74.41 Nuclear material control and accounting for special nuclear material of moderate strategic significance.

    The general performance objectives applicable to Category II facilities would be set forth in proposed Sec. 74.3 as previously discussed. Revised Sec. 74.41(a)(1) would incorporate the Sec. 74.3 performance objectives by reference, thereby replacing the performance objectives set forth in existing Sec. 74.41(a)(1) through (4). Proposed paragraph (a)(2) would retain elements of the exemption in existing Sec. 74.41(a) applicable to production or utilization facilities, licensees using reactor irradiated fuels for research purposes, and any licensee operations involving waste disposal.

    Paragraph (b) would be revised by replacing the reference to ``a fundamental nuclear material control (FNMC) plan'' with a reference to ``an MC&A plan.'' The plan would need to achieve the general performance objectives in Sec. 74.3, meet the program capability requirements set forth in Sec. 74.41(c), and the requirements of Sec. Sec. 74.43 and 74.45 as previously discussed. The title of paragraph (b) would be changed from ``Implementation schedule'' to ``Implementation,'' and the existing paragraphs (b)(1) and (2) would be consolidated into a single paragraph consistent with the format used in existing Sec. 74.31(b).

    Paragraph (c) would be revised by changing its title from ``System capabilities'' to ``Program capabilities.'' The reference in existing Sec. 74.41(c) to the ``MC&A system'' would be changed to the ``MC&A plan,'' which must achieve the performance objectives in Sec. 74.3, and include the capabilities described in Sec. Sec. 74.43 and 74.45. The existing Sec. 74.41(c)(1) and (2) checks and balances requirements remain the same.

    Section 74.43 Internal controls, inventory, and records.

    Paragraph (b)(3) would be revised to replace the title, ``FNMC plan'' with ``MC&A plan.'' Paragraph (b)(5) would be revised by replacing the term ``item control program'' with ``item control system'' as newly defined in Sec. 74.4. The current paragraphs (b)(5)(i) and (b)(5)(ii) would be consolidated into proposed paragraph (b)(5). The current detection requirement in paragraph (5)(ii) would be revised to require the detection of ``unauthorized removals of individual items or any quantity of material (as defined in Sec. 74.4) from items,'' replacing the existing reference to the ``unauthorized removal of 200 grams or more of plutonium or uranium-233 or 300 grams or more of uranium-235, as one or more whole items and/or as SNM removed from containers.'' Paragraph (b)(6) would be revised to replace the exemptions stated in the current requirement. Only ``items in solution with a concentration of less than 5 grams of U-235 per liter, and items of waste destined for burial or incineration'' would be exempt from the detection requirements described previously. The reference to ``shipper-receiver comparisons'' in existing paragraph (b)(7) would be clarified to state ``shipper-receiver difference comparisons.''

    Paragraph (c)(3) would be clarified by removing the phrases, ``if tamper-safe seals are to be used for assuring the validity of prior measurements,'' and ``showing the date and time of seal application.'' These changes are proposed so that the tamper-safing requirements in subparts C, D, and E of 10 CFR part 74 will be worded in a consistent manner. Paragraph (c)(9) would be added to provide requirements that the MC&A plan capabilities must include the designation of MBAs, ICAs, and assigning custodial responsibilities for these areas.

    Paragraph (d)(5) would be revised to refer to the performance objectives of proposed Sec. Sec. 74.3 and 74.41(a)(1), as its current reference to Sec. 74.41(a)(1) through (4) would no longer be accurate if the proposed changes to Sec. 74.41(a) are made.

    Section 74.45 Measurements and measurement control.

    Paragraph (c)(4) would be clarified by spelling out the acronym SEID as the ``standard error of the inventory difference.''

    Section 74.51 Nuclear material control and accounting for strategic special nuclear material.

    The general performance objectives applicable to Category I facilities would

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    be set forth, in part, in proposed Sec. 74.3 as previously discussed. Revised Sec. 74.51(a)(1) would incorporate the Sec. 74.3 performance objectives by reference. Additionally, proposed Sec. 74.51(a)(1)(i) through (iii) would set forth the performance objectives stated in existing Sec. 74.51(a)(2) through (4).

    Proposed paragraph (a)(2) would retain the exemptions in existing Sec. 74.51(a) applicable to production or utilization facilities, ISFSIs, and any licensee operations involving waste disposal, but would remove the exemption for an irradiated fuel reprocessing plant. The removal of this exemption is in accordance with the NRC staff's recommendation in its regulatory framework gap analysis for irradiated fuel reprocessing documented in SECY-09-0082. The licensee of any future irradiated fuel reprocessing facility would likely be authorized to possess quantities of strategic SNM that need to be subject to the highest level of MC&A safeguards and security requirements, to ensure that this material would be adequately protected.

    To make the organization of requirements for Category I and Category III fuel fabrication facilities more consistent, changes in existing 10 CFR 74.51(b) and (c) are proposed, which would align the format with that used in existing 10 CFR 74.31(b) and (c). Thus, 10 CFR 74.51(b) would be retitled, ``Implementation,'' and would contain elements of existing 10 CFR 74.51(c). Proposed 10 CFR 74.51(b) would refer to an ``MC&A plan'' rather than a ``FNMC plan,'' for the reasons previously discussed. The MC&A plan would need to achieve the general performance objectives in Sec. Sec. 74.3 and 74.51(a), and meet the requirements of Sec. Sec. 74.53, 74.55, 74.57, and 74.59.

    Proposed 10 CFR 74.51(c) would be retitled, ``Program capabilities,'' and would contain elements of existing Sec. 74.51(b). In addition to the MC&A plan requirements discussed in revised 10 CFR 74.51(b), 10 CFR 74.51(c) would require that the plan incorporate checks and balances that are sufficient to detect falsification of data and reports that could conceal diversion of SNM or strategic SNM (SSNM). A plain language change to simplify paragraph (c)(1) would revise ``An individual'' to ``A single individual.'' A plain language change to simplify paragraph (c)(2) would revise ``Collusion between an individual with MC&A responsibilities and another individual who has responsibility or control within both the physical protection and the MC&A systems'' to ``Collusion between two individuals, one or both of whom have authorized access to SNM or SSNM.''

    Section 74.51(d) would be revised to replace ``FNMC'' plan with ``MC&A'' plan. Additionally, the times to perform physical inventories would be expressed in terms of calendar days.

    Section 74.53 Process monitoring.

    Paragraph (a)(3) would be clarified to replace ``a consecutive three-month period'' with ``a period of 95 calendar days.''

    Paragraph (a)(4) would be clarified to replace ``any seven-

    consecutive-day period'' with ``a period of 7 calendar days.''

    Paragraph (c)(1) would be clarified to replace ``monthly'' with ``at intervals not to exceed 30 calendar days.''

    Section 74.57 Alarm resolution.

    Paragraph (c) would be revised to replace ``fundamental nuclear material control plan'' with ``MC&A plan.''

    Section 74.59 Quality assurance and accounting requirements.

    In paragraph (e)(7), the requirement to correct SSNM measurement differences ``accumulated over a six-month period'' would be clarified to instead reference ``a period not to exceed 185 calendar days.''

    In paragraph (f)(1), the requirement to perform a physical inventory ``every six calendar months'' would be clarified to instead reference ``every 185 calendar days,'' and ``45 days'' would be clarified to specify ``45 calendar days.'' The paragraph (f)(2)(i) tamper-safing provision would be revised by adding at its end the phrase ``and that include control of access to, and distribution of, unused seals and records,'' in order to make this provision consistent across subparts C, D, and E of 10 CFR part 74.

    With respect to required internal controls regarding how frequently scrap material must be measured, paragraph (h)(2)(ii) would be clarified by replacing ``six months'' with ``185 calendar days.'' Paragraph (h)(5) would be revised by adding at its beginning a requirement to designate MBAs and ICAs, in order to make this provision consistent across subparts C, D, and E of 10 CFR part 74.

    Appendix A to 10 CFR Part 74--Categories of Special Nuclear Material.

    Appendix A would be added to provide a table stating the elements, isotopic composition, and quantities of material that Category I, Category II, and Category III facilities are authorized to possess. Notes are included to state that sealed sources are excluded from the quantity limits in the table and that spent nuclear fuel is reduced one category level during the period of time that the radiation exposure exceeds 1 Sv per hour (100 rads per hour) at 1 meter, unshielded. Formulae are included to calculate a quantity of SSNM for Category I, Category II, or Category III.

    Section 150.17 Submission to Commission of nuclear material status reports.

    The requirements in paragraph (a) would be clarified by arranging the requirements into numbered subsections (a)(1), (2), (3), and (4). The revised introductory paragraph would clarify the requirement to submit both a Material Balance Report and a Physical Inventory Listing Report to the NMMSS in accordance with the instructions in paragraph (a)(1). The reports would be due between January 1 and March 31 of each year.

    Paragraph (a)(1) would include the reporting instructions that are in the current requirements in paragraph (a) and would state that individual reports must be prepared for each Reporting Identification Symbol account using the information in NUREG/BR-0007 and NMMSS Report D-24, ``Personal Computer Data Input for NRC Licensees.'' Paragraph (a)(2) would include the provision that is currently in paragraph (a) stating that the NRC may permit reports to be submitted at other times for good cause. Paragraph (a)(3) would include the statement in existing paragraph (b) regarding the submittal of reports under 10 CFR 75.35 (pertaining to implementation of the U.S./IAEA Safeguards Agreement). Paragraph (a)(4) would include the requirement that is currently in paragraph (a) that a licensee must resolve any discrepancies identified during the report review and reconciliation process within 30 calendar days of being notified of a discrepancy identified by the NRC.

    Paragraph (b)(1) would be revised to remove the reference to 10 CFR part 72, and paragraph (b)(2) would also be revised to remove the reference to 10 CFR part 72.

    VI. Availability of Documents

    The following table indicates the proposed rule and some related background documents that are available to the public and how they may be obtained. See the information contained in the Accessing Information and Submitting Comments section of SUPPLEMENTARY INFORMATION on the physical locations and Web sites where the documents may be accessed.

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    ------------------------------------------------------------------------

    Document PDR Web NRC Library (ADAMS)

    ------------------------------------------------------------------------

    ``Draft Environmental X X ML13228A222

    Assessment and Finding of No

    Significant Impact for the

    Proposed Rule Amending 10 CFR

    Parts 40, 70, 72, 74, and

    150; Amendments to Material

    Control and Accounting

    Regulations''.

    ``Draft Regulatory Analysis X X ML13228A223

    for Proposed Rule: Amendments

    to Material Control and

    Accounting Regulations (10

    CFR part 74)''.

    SECY-08-0059, ``Rulemaking X X ML080580307

    Plan: Party 74--Material

    Control and Accounting of

    Special Nuclear Material''.

    Staff Requirements Memorandum X X ML090360473

    (SRM) for SECY-08-0059.

    SECY-09-0082, ``Update on X X ML091520280

    Reprocessing Regulatory

    Framework--Summary of Gap

    Analysis''.

    ------------------------------------------------------------------------

    VII. Criminal Penalties

    For the purpose of Section 223 of the Atomic Energy Act of 1954, as amended (AEA), the Commission is proposing to amend 10 CFR parts 40, 70, 72, 74, and 150 under one or more of Sections 161b, 161i, or 161o of the AEA. Willful violations of the rule would be subject to criminal enforcement.

    VIII. Agreement State Compatibility

    Under the ``Policy Statement on Adequacy and Compatibility of Agreement States Programs,'' approved by the Commission on June 20, 1997, and published in the Federal Register (62 FR 46517; September 3, 1997), the regulations affected by this rulemaking are classified as compatibility Category ''NRC.'' The NRC program elements in this category are those that relate directly to areas of regulation reserved to the NRC by the AEA, or the provisions of 10 CFR, and cannot be relinquished to the Agreement States. Thus, States should not adopt these program elements.

    IX. Plain Writing

    The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal agencies to write documents in a clear, concise, and well-organized manner. The NRC has written this document to be consistent with the Plain Writing Act as well as the Presidential Memorandum, ``Plain Language in Government Writing,'' published June 10, 1998 (63 FR 31883). The NRC requests comment on the proposed rule with respect to the clarity and effectiveness of the language used.

    X. Voluntary Consensus Standards

    The National Technology Transfer and Advancement 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 would revise and consolidate requirements for MC&A in 10 CFR part 74. The NRC is not aware of any comprehensive voluntary consensus standards that address the proposed subject matter of this proposed rule. The NRC will consider using a voluntary consensus standard if an appropriate standard is identified. If a voluntary consensus standard is identified for consideration, the submittal should explain why the standard should be used.

    XI. Environmental Assessment and Finding of No Significant Environmental Impact: Availability

    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 have any significant environmental impacts, and therefore this rulemaking does not warrant the preparation of an environmental impact statement. The proposed rule pertains to MC&A program requirements, which consist of administrative procedures and operations to track and control SNM and related information, in order to deter and detect any loss, theft, diversion, or unauthorized production of nuclear material. As the proposed amendments pertain to information collection and reporting requirements, adopting them would have no significant impact on the quality of the human environment. The draft environmental assessment, entitled ``Draft Environmental Assessment and Finding of No Significant Impact for the Proposed Rule Amending 10 CFR Parts 40, 70, 72, 74, And 150; Amendments to Material Control and Accounting Regulations,'' can be found at ADAMS Accession No. ML12291A792.

    XII. Paperwork Reduction Act Statement

    This proposed rule amends information collection requirements contained in 10 CFR parts 72 and 74 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq). These information collection requirements have been submitted to the Office of Management and Budget (OMB) for review and approval. The proposed changes to 10 CFR parts 40, 70, and 150 do not contain new or amended information collection requirements. Existing requirements were approved by the OMB, approval numbers 3150-0132 and 3150-0123.

    Type of submission, new or revision: Revision.

    The title of the information collection: 10 CFR part 72, ``Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste'' and 10 CFR part 74, ``Material Control and Accounting of Special Nuclear Material.''

    The form number if applicable: U.S. Department of Energy (DOE)/NRC Form 741, ``Nuclear Material Transaction Report,'' DOE/NRC Form 742, ``Material Balance Report,'' and DOE/NRC Form 742C, ``Physical Inventory Listing.''

    How often the collection is required: Licensee timeframes for reporting to the NRC have not changed for NRC Forms 741, 742, and 742C. Licensees under subparts B and C of 10 CFR part 74 would submit reports within 60 calendar days after the start of the physical inventory covered by the reports, at intervals not to exceed 370 calendar days or 12 months. Licensees under subpart D of 10 CFR part 74 would submit reports within 60 calendar days after the start of the physical inventory covered by the reports, at intervals not to exceed 9 months. Licensees under subpart E of 10 CFR part 74 would be required to submit reports within 30 calendar days after the start of the physical inventory covered by the reports, at intervals not to exceed 65 calendar days until performance acceptable to the NRC has been demonstrated and the Commission has issued formal approval to perform physical inventories at intervals not to exceed 185 calendar days. Forms are also submitted when a nuclear material transaction is made.

    Who will be required or asked to report: Persons licensed under 10 CFR parts 50, 52, 70, 72, and 76 who possess and use certain forms and quantities of SNM.

    An estimate of the number of annual responses: 68 responses (0 reporting responses + 68 record keepers).

    Page 67240

    The estimated number of annual respondents: 68.

    An estimate of the total number of hours needed annually to complete the requirement or request: 1,213 hours (0 hours reporting plus 1,213 hours recordkeeping).

    Abstract: The NRC is proposing to amend its regulations to revise and consolidate the requirements for MC&A of SNM in 10 CFR part 74. The proposed amendments relocate the NMMSS-related reporting requirements for a licensee operating an ISFSI from 10 CFR part 72 to 10 CFR part 74; however, no changes have been made to the reporting requirements for NRC Forms 741, 742, or 742C. The proposed rule would change recordkeeping requirements in subparts B, C, and D. The reactor licensees have already implemented item control systems to document, control, and account for discrete items and thus would not be impacted by the proposed requirement. The ISFSI licensees would be impacted by the proposed item control requirement. Licensees under subpart C would include currently exempted items in their item controls. Currently there is no licensee operating a facility under subpart D.

    The NRC 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?

    The public may examine and have copied, for a fee, publicly available documents, including the OMB supporting statement, at the NRC's PDR, One White Flint North, 11555 Rockville Pike, Room O-1 F21, Rockville, MD 20852. The OMB clearance package and rule are available on the NRC's Web site, http://www.nrc.gov/public-involve/doc-comment/omb/index.html, for 60 days after the signature date of this document.

    Send comments on any aspect of these proposed regulations related to information collections, including suggestions for reducing the burden and on the previously stated issues, by December 9, 2013 to the Information Services Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet electronic mail to Infocollects.Resource@NRC.gov and to the Desk Officer, Chad Whiteman, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0132 and 3150-0123), Office of Management and Budget, Washington, DC 20503. Comments can also be emailed to Chad_S_Whiteman@omb.eop.gov or submitted by telephone to (202) 395-4718. Comments on the proposed information collections may also be submitted via the Federal rulemaking Web site http://www.regulations.gov, Docket ID NRC-2009-

    0096. 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.

    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.

    XIII. 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 Commission requests public comment on the draft regulatory analysis (RA), which can be found at ADAMS Accession No. ML13228A223.

    XIV. Regulatory Flexibility Certification

    In accordance with the Regulatory Flexibility Act of 1980 (5 U.S.C. 605(b)), the Commission certifies that this rule would not, if promulgated, have a significant economic impact on a substantial number of small entities. The majority of companies that own these plants do not fall within the scope of the definition of ''small entities'' set forth in the Regulatory Flexibility Act or the size standards established by the NRC (10 CFR 2.810).

    The NRC is seeking public comment on the potential impact of the proposed rule on small entities. The NRC particularly desires comment from licensees who qualify as small businesses, specifically as to how the proposed regulation will affect them and how the regulation may be tiered or otherwise modified to impose less stringent requirements on small entities while still adequately protecting the public health and safety and common defense and security. Comments on how the regulation could be modified to take into account the differing needs of small entities should specifically discuss:

    (a) The size of the business and how the proposed regulation would result in a significant economic burden upon it as compared to a larger organization in the same business community;

    (b) How the proposed regulation could be further modified to take into account the business' differing needs or capabilities;

    (c) The benefits that would accrue, or the detriments that would be avoided, if the proposed regulation was modified as suggested by the commenter;

    (d) How the proposed regulation, as modified, would more closely equalize the impact of the NRC's regulations as opposed to providing special advantages to any individuals or groups; and

    (e) How the proposed regulation, as modified, would still adequately protect the public health and safety and common defense and security.

    XV. Backfitting and Issue Finality

    The NRC has determined that the NRC's backfitting and issue finality regulations in 10 CFR 50.109, 70.76, 72.62, 76.76, and in 10 CFR part 52, do not apply to this proposed rule because this amendment would not involve any provisions that are subject to these backfitting and issue finality provisions. The proposed rule addresses MC&A programs, which consist of administrative procedures and operations to track and control SNM and related information to deter and detect any loss, theft, diversion, or unauthorized production of nuclear material. The NRC regards MC&A requirements as constituting information collection and reporting requirements. The NRC has long taken the position that information collection and reporting requirements are not subject to the NRC's backfitting and issue finality regulations, as reflected in past MC&A rulemakings published in the Federal Register (e.g., 56 FR 55991; October 31, 1991, 67 FR 78130; December 23, 2002, and 73 FR 32453; June 9, 2008). The remainder of this section discusses the NRC's bases for determining that MC&A activities are information collection and reporting requirements.

    There are several bases for the NRC's determination that MC&A activities required by 10 CFR part 74 are information collection and reporting requirements. First, several of the existing general provisions in 10 CFR part 74, subpart A, indicate that 10 CFR part 74 includes information collection and reporting requirements. For example, 10 CFR 74.1, Purpose, states

    Page 67241

    that the requirements in 10 CFR part 74 address ``the control and accounting of special nuclear material at fixed sites and for documenting the transfer of special nuclear material,'' and include general ``reporting requirements'' (emphases added). This focus on information collection and reporting requirements is further emphasized by the current language of paragraph (a) of 10 CFR 74.2, Scope, which states, ``The general reporting and recordkeeping requirements of subpart B . . . apply to each person licensed under this chapter . . . (emphasis added).'' Similarly, Sec. 74.2(c) states that the regulations in 10 CFR part 74 ``establish procedures and criteria for material control and accounting for the issuance of a certificate of compliance or the approval of a compliance plan'' (emphasis added).

    The proposed revisions to 10 CFR part 74 subpart A do not change the purpose and scope of 10 CFR part 74. The proposed addition to 10 CFR 74.2(a) states that the general reporting and recordkeeping requirements of subpart B of this part also apply to licensees who possess spent nuclear fuel at independent spent fuel storage installations emphasis added. Paragraph (b) of proposed Sec. 74.3 states, ``In addition, specific control and accounting requirements are included in subparts C, D and E for certain licensees. . .'' (emphasis added).

    Given the language in the preceding paragraphs referencing the existing and proposed provisions of 10 CFR part 74, the NRC believes that the primary issue--from the standpoint of backfitting and issue finality--is whether MC&A requirements may reasonably be deemed ``information collection and reporting'' requirements. In the NRC's view, the answer is in the affirmative. Required MC&A actions represent a systematic approach for ensuring that information about SNM at a facility is accurate, which in turn, helps achieve the objective of ensuring that items containing SNM are not lost, stolen, diverted, or misused through human error, or because of deliberate acts of malfeasance. Item is a defined term in 10 CFR part 74, and means ``any discrete quantity or container of SNM or source material, not undergoing processing, having an unique identity and also having an assigned element and isotope quantity.'' The systematic approach for managing items under 10 CFR part 74 has two aspects: accounting for items of material; and maintaining control over such items.

    The concept of material accounting is reflected in the proposed definition of accounting that would be added to 10 CFR 74.4 to read as follows: Accounting means a system that documents the quantities of SNM held on current inventory by the licensee, and includes tracking of receipts, shipments, and measured discards, and transfers of SNM. Material accounting constitutes the principles, processes and procedures for collecting and maintaining accurate information and records on the nature and quantities of SNM within the licensee's control. By accurate information and records, the NRC means that the information has been collected and maintained in a manner that minimizes the possibility of human error or deliberate acts of malfeasance affecting the accuracy and quality of the information.

    The concept of material control is reflected in the proposed definitions that would be added to 10 CFR 74.4 and that read as follows. Item control area means a designated administrative area within the controlled access area, in which SNM is maintained in such a way that, at any time, a count of the items and the related material quantities can be obtained using the accounting system. Control of items moving into, out of, and within an ICA is by the identity of an item and its assigned material quantity. Item control system means a system tracking the creation, identity, element and isotopic content, location, and disposition of all items, which enables the licensee to maintain current knowledge of each item.

    Material control constitutes the administrative processes and procedures that a holder of SNM employs to control the location and accounting of items containing SNM, by applying appropriate material accounting principles, processes and procedures. These processes and procedures for controlling the quantities, location, storage, transportation and use of items containing SNM support the accuracy of the material accounting information each time it is collected, and ensure that the information remains accurate throughout the period of time that the items are in the possession of the licensee. This concept of control is reflected in the proposed definition that would be added to 10 CFR 74.4: Material control and accounting means a program to control and account for certain types of nuclear material used at a licensed facility, including SNM and source material, and which controls and accounts for unauthorized use of equipment capable of producing enriched uranium. The purpose of an MC&A program is to deter and detect any loss, theft, diversion, misuse, or unauthorized production of nuclear material.

    Material accounting and material control, properly integrated, ensure that accurate information (i.e., information that is not inaccurate due to human error or deliberate acts of malfeasance) is developed and maintained on items of SNM in the licensee's possession. By doing so, the NRC's regulatory objective (of ensuring that SNM is not lost, stolen, diverted, or misused through human error or because of deliberate acts of malfeasance) is achieved.

    The performance requirements for the MC&A program, set forth in proposed 10 CFR 74.3, General Performance Requirements, demonstrate that such a program represents a system of information collection and reporting requirements directed at achieving the NRC's regulatory objective of ensuring that SNM is not lost, stolen, diverted, or misused. Proposed 10 CFR 74.3 would require licensees to implement an MC&A program to achieve five general performance objectives. The nature of the five objectives (shown in Table 3) includes maintaining accurate, current, and reliable information to confirm quantities and locations of SNM. The information would enable a licensee to detect, respond and resolve any anomaly concerning SNM being held by the licensee and would enable the licensee to make a rapid determination of the actual situation. A licensee would be able to provide reliable information to aid in the investigation and recovery of SNM. A licensee would be expected to control access to MC&A information and prevent unauthorized use of the information by adversaries.

    The NRC notes that nothing in the current provisions of part 74, or in the proposed amendments to part 74, precludes affected licensees from possessing or using SNM. Such substantive health and safety or common defense and security requirements are set forth in other parts of 10 CFR parts 20, 70, 71, 72, 73, 75, 76, 95, and 110. A review of the substantive provisions of the proposed rule (i.e., those proposed changes to the regulations other than conforming changes, plain language revisions, and other changes of an administrative or organizational nature) confirms that the overall character of the rulemaking is one of information collection and reporting.

    Table 3 summarizes the key substantive provisions of the proposed rule, together with a short explanation why the provision includes an information collection and reporting requirement.

    Page 67242

    Table 3--Characterization of Proposed Substantive Amendments to 10 CFR Part 74 as Information Collection and

    Reporting Requirements

    ----------------------------------------------------------------------------------------------------------------

    Explanation of why the proposed

    Proposed rule citation Description of proposed requirement requirement would be information

    collection and reporting

    ----------------------------------------------------------------------------------------------------------------

    74.3 General performance objectives This section would require a licensee The proposed general performance

    authorized by the NRC to possess SNM objectives in Sec. 74.3 are

    in a quantity greater than 350 grams directed at maintaining knowledge

    to implement and maintain an MC&A of SNM which is done through

    program that achieves the five collection and recording of

    general performance objectives, as information. Loss of material is

    follows: detected through activities such as

    (a) Maintain accurate, current, and physical inventory that provide

    reliable information on, and confirm information to verify the accuracy

    the quantities and locations of SNM of the MC&A records at a site. MC&A

    in its possession;. information is essential to

    (b) Detect, respond to, and resolve detecting and resolving any actual

    any anomaly indicating a possible or potential loss, theft,

    loss, theft, diversion, or misuse of diversion, or misuse. Finally,

    SNM;. restricting access to MC&A records

    (c) Permit rapid determination of reduces the likelihood that these

    whether an actual loss, theft, records could be tampered with in a

    diversion, or misuse of SNM has manner that would invalidate the

    occurred;. information they contain (i.e.,

    (d) Provide information to aid in the concealing the loss, theft or

    investigation and recovery of diversion of SNM).

    missing SNM in the event of an

    actual loss, theft, diversion, or

    misuse; and.

    (e) Control access to MC&A

    information that might assist

    adversaries to carry out acts of

    theft, diversion, misuse, or

    radiological sabotage involving SNM.

    74.19 Recordkeeping, procedures, Paragraph (d) would require The reactor and ISFSI licensees

    item controls, and physical production or utilization facilities would be required to periodically

    inventories. licensed under 10 CFR part 50 or 52 collect and verify the MC&A

    of this chapter and independent information recorded on site.

    spent fuel storage installations

    licensed under 10 CFR part 72 of

    this chapter to establish, document,

    implement, and maintain an item

    control system as defined in Sec.

    74.4.

    74.31 Nuclear material control and To achieve the general performance Removing some of the currently

    accounting for special nuclear objectives, a licensee's MC&A plan allowed exemptions for item control

    material of low strategic would include the capabilities for Category III licensees would

    significance. described in paragraph (c). require these licensees to collect

    In paragraph (c)(6) a licensee would and maintain additional MC&A

    be required to establish, document, information on these types of items

    implement, and maintain an item and verify the information

    control system as defined in Sec. periodically.

    74.4 to ensure that items are stored

    and handled or subsequently measured

    in a manner such that unauthorized

    removals of individual items or any

    quantity of SNM from items would be

    detected. Items in solution with a

    concentration of less than 5 grams

    of uranium-235 per liter and items

    of waste destined for burial or

    incineration would continue to be

    exempted from the item control.

    In paragraph (c)(9) a licensee would Tamper-safing as defined in Sec.

    be required to maintain and follow 74.4, increases the integrity of

    procedures for tamper-safing (as MC&A information collected and

    defined in Sec. 74.4) of maintained by the licensee. This

    containers or vaults (as defined in reduces the likelihood that these

    Sec. 74.4) containing SNM, which records could be tampered with in a

    include control of access to, and manner that would invalidate the

    distribution of, unused seals and information they contain (i.e.,

    records. concealing the loss, theft or

    diversion of SNM).

    In paragraph (c)(10) a licensee would The use of MBAs, ICAs, and

    be required to designate material designated custodians provides a

    balance areas and item control areas means of tracking SNM at a more

    and assign custodial responsibility localized level than the entire

    for each of these areas in a manner site. These areas and their

    that ensures that such custodians help to collect MC&A

    responsibility can be effectively information on the movement of SNM

    executed for all SNM possessed under through the facility.

    the license.

    Page 67243

    74.33 Nuclear material control and To achieve the general performance Removing some of the currently

    accounting for uranium enrichment objectives, a licensee's MC&A plan allowed exemptions for item control

    facilities authorized to produce would include the capabilities for Category III licensees would

    special nuclear material of low described in paragraph (c). require these licensees to maintain

    strategic significance. In paragraph (c)(6) a licensee would additional MC&A information on

    be required to establish, document, these types of items and verify the

    implement, and maintain an item information periodically.

    control system as defined in Sec.

    74.4 to ensure that items are stored

    and handled or subsequently measured

    in a manner such that unauthorized

    removal of any quantity of

    Udash235, as individual items or

    as uranium contained in items, will

    be detected. Items in solution with

    a concentration of less than 5 grams

    of uraniumdash235 per liter and

    items of waste destined for burial

    or incineration would be exempted

    from the item control.

    In paragraph (c)(9) a licensee would Tamper-safing, as defined in Sec.

    be required to maintain and follow 74.4, increases the integrity of

    procedures for tamper-safing (as MC& A information collected and

    defined in Sec. 74.4) of maintained by the licensee. This

    containers or vaults (as defined in reduces the likelihood that these

    Sec. 74.4) containing SNM, which records could be tampered with in a

    include control of access to, and manner that would invalidate the

    distribution of, unused seals and information they contain (i.e.,

    records. concealing the loss, theft or

    diversion of SNM).

    In paragraph (c)(10) a licensee would The use of MBAs, ICAs, and

    be required to designate material designated custodians provides a

    balance areas and item control areas means of tracking SNM at a more

    and assign custodial responsibility localized level than the entire

    for each of these areas in a manner site. Collecting information on SNM

    that ensures that such movements within specific areas of

    responsibility can be effectively the plant provides increased

    executed for all SNM possessed under knowledge of the quantities and

    the license. movement of SNM through the

    facility. By increasing the number

    of data collection areas, and the

    need to reconcile inventory

    statements for different areas,

    this reduces the likelihood that

    these records could be tampered

    with in a manner that would

    invalidate the information they

    contain (i.e., concealing the loss,

    theft or diversion of SNM).

    74.43 Internal controls, inventory, Paragraph (b)(5) would require a Removing some of the currently

    and records. licensee to establish, document, allowed exemptions for item control

    implement, and maintain an item for Category II licensees would

    control system as defined in Sec. require these licensees to maintain

    74.4 to ensure that items are stored additional MC&A information on

    and handled or subsequently measured these types of items and verify the

    in a manner such that unauthorized information periodically.

    removals of individual items or any

    quantity of material (as defined in

    Sec. 74.4) from items will be

    detected.

    Paragraph (b)(6) would exempt from

    the requirements of paragraph (b)(5)

    an item in solution with a

    concentration of less than 5 grams

    of Udash235 per liter, and items

    of waste destined for burial or

    incineration.

    In paragraph (c)(3) a licensee would Tamper-safing, as defined in Sec.

    be required to maintain and follow 74.4, increases the integrity of

    procedures for tamper-safing (as MC& A information collected and

    defined in Sec. 74.4) of maintained by the licensee. This

    containers or vaults (as defined in reduces the likelihood that these

    Sec. 74.4) containing SNM, which records could be tampered with in a

    include control of access to, and manner that would invalidate the

    distribution of, unused seals and information they contain (i.e.,

    records. concealing the loss, theft or

    diversion of SNM).

    In paragraph (c)(9) a licensee would The use of MBAs, ICAs, and

    be required to designate material designated custodians provides a

    balance areas and item control areas means of tracking SNM at a more

    and assign custodial responsibility localized level than the entire

    for each of these areas in a manner site. Collecting information on SNM

    that ensures that such movements within specific areas of

    responsibility can be effectively the plant provides increased

    executed for all SNM possessed under knowledge of the quantities and

    the license. movement of SNM through the

    facility. By increasing the number

    of data collection areas, and the

    need to reconcile inventory

    statements for different areas,

    this reduces the likelihood that

    these records could be tampered

    with in a manner that would

    invalidate the information they

    contain (i.e., concealing the loss,

    theft or diversion of SNM).

    Page 67244

    74.59 Quality assurance and Paragraph (f)(2)(i) would require a Tamper-safing, as defined in Sec.

    accounting requirements. licensee to develop procedures for 74.4, increases the integrity of

    tamper-safing of containers or MC& A information collected and

    vaults containing SSNM not in maintained by the licensee. This

    process that include adequate reduces the likelihood that these

    controls to assure the validity of records could be tampered with in a

    assigned SSNM values and which manner that would invalidate the

    include control of access to, and information they contain (i.e.,

    distribution of, unused seals and concealing the loss, theft or

    records. diversion of SNM).

    Paragraph (h)(5) would require a The use of MBAs, ICAs, and

    licensee to designate material designated custodians provides a

    balance areas and item control areas means of tracking SNM at a more

    and assign custodial responsibility localized level than the entire

    for each of these areas in a manner site. Collecting information on SNM

    that ensures that such movements within specific areas of

    responsibility can be effectively the plant provides increased

    executed for all SSNM possessed knowledge of the quantities and

    under the license. movement of SNM through the

    facility. By increasing the number

    of data collection areas, and the

    need to reconcile inventory

    statements for different areas,

    this reduces the likelihood that

    these records could be tampered

    with in a manner that would

    invalidate the information they

    contain (i.e., concealing the loss,

    theft or diversion of SNM).

    ----------------------------------------------------------------------------------------------------------------

    In as much as the MC&A provisions constitute requirements to collect and report information, they are not subject to backfitting and issue finality requirements. Accordingly, the NRC did not prepare a backfit analysis for the proposed rulemaking. This conclusion is consistent with the NRC's position on the applicability of backfitting to past MC&A rulemakings published in the Federal Register (e.g., 56 FR 55991; October 31, 1991, 67 FR 78130; December 23, 2002, and 73 FR 32453; June 9, 2008).

    List of Subjects

    10 CFR Part 40

    Criminal penalties, Government contracts, Hazardous materials transportation, Nuclear materials, Reporting and recordkeeping requirements, Source material, Uranium.

    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 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 74

    Accounting, Criminal penalties, Hazardous materials transportation, Material control and accounting, Nuclear materials, Packaging and containers, Radiation protection, Reporting and recordkeeping requirements, Scientific equipment, Special nuclear material.

    10 CFR Part 150

    Criminal penalties, Hazardous materials transportation, Intergovernmental relations, Nuclear materials, Reporting and recordkeeping requirements, Security measures, Source material, SNM.

    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 40, 70, 72, 74, and 150.

    0

    1. The authority citation for part 40 continues to read as follows:

    PART 40--DOMESTIC LICENSING OF SOURCE MATERIAL

    Authority: Atomic Energy Act secs. 11(e)(2), 62, 63, 64, 65, 81, 161, 181, 182, 183, 186, 193, 223, 234, 274, 275 (42 U.S.C. 2014(e)(2), 2092, 2093, 2094, 2095, 2111, 2113, 2114, 2201, 2231, 2232, 2233, 2236, 2243, 2273, 2282, 2021, 2022); Energy Reorganization Act secs. 201, 202, 206 (42 U.S.C. 5841, 5842, 5846); Government Paperwork Elimination Act sec. 1704 (44 U.S.C. 3504 note); Energy Policy Act of 2005, Pub. L. No. 109-59, 119 Stat. 594 (2005).

    Section 40.7 also issued under Energy Reorganization Act sec. 211, Pub. L. 95-601, sec. 10, as amended by Pub. L. 102-486, sec. 2902 (42 U.S.C. 5851). Section 40.31(g) also issued under Atomic Energy Act sec. 122 (42 U.S.C. 2152). Section 40.46 also issued under Atomic Energy Act sec. 184 (42 U.S.C. 2234). Section 40.71 also issued under Atomic Energy Act sec. 187 (42 U.S.C. 2237).

    0

    2. In Sec. 40.64, revise paragraphs (b)(1) and (2) to read as follows:

    Sec. 40.64 Reports.

    * * * * *

    (b) * * *

    (1) Possesses, or had possessed in the previous reporting period, at any one time and location, one kilogram or more of uranium or thorium source material with foreign obligations as defined in this part, shall document holdings as of September 30 of each year and submit to the Commission within 30 days, a statement of its source material inventory with foreign obligations as defined in this part. Alternatively, this information may be submitted with the licensee's material status reports on SNM filed under part 74 of this chapter, as a statement of its source material inventory with foreign obligations as defined in this part. This statement must be submitted to the address specified in the reporting instructions in NUREG/BR-0007, and include the Reporting Identification Symbol (RIS) assigned by the Commission to the licensee.

    (2) Possesses, or had possessed in the previous reporting period, one kilogram or more of uranium or thorium source material pursuant to the operation of

    Page 67245

    enrichment services, downblending uranium that has an initial enrichment of the U-235 isotope of 10 percent or more, or in the fabrication of mixed-oxide fuels shall complete and submit, in computer-readable format, Material Balance and Physical Inventory Listing Reports concerning all source material that the licensee has received, produced, possessed, transferred, consumed, disposed of, or lost. Reports must be submitted for each RIS account including all holding accounts. Each licensee shall prepare and submit these reports as specified in the instructions in NUREG/BR-0007 and NMMSS Report D-

    24, ``Personal Computer Data Input for NRC Licensees.'' These reports must document holdings as of September 30 of each year and must be submitted to the Commission within 30 days. Alternatively, these reports may be submitted with the licensee's material status reports on special nuclear material filed under part 74 of this chapter. Copies of the reporting instructions may be obtained either by writing to the U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety and Safeguards, Washington, DC 20555-0001, or by email to RidsNmssFcss.Resource@nrc.gov. Each licensee required to report material balance, inventory, and/or foreign obligation information, as detailed in this part, shall resolve any discrepancies identified during the report review and reconciliation process within 30 calendar days of notification of a discrepancy identified by the NRC.

    * * * * *

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    3. The authority citation for part 70 continues to read as follows:

    PART 70--DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL

    Authority: Atomic Energy Act secs. 51, 53, 161, 182, 183, 193, 223, 234 (42 U.S.C. 2071, 2073, 2201, 2232, 2233, 2243, 2273, 2282, 2297f); secs. 201, 202, 204, 206, 211 (42 U.S.C. 5841, 5842, 5845, 5846, 5851); Government Paperwork Elimination Act sec. 1704 (44 U.S.C. 3504 note); Energy Policy Act of 2005, Pub. L. No. 109-58, 119 Stat. 194 (2005).

    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 70.21(g) also issued under Atomic Energy Act sec. 122 (42 U.S.C. 2152). Section 70.31 also issued under Atomic Energy Act sec. 57(d) (42 U.S.C. 2077(d)). Sections 70.36 and 70.44 also issued under Atomic Energy Act sec. 184 (42 U.S.C. 2234). Section 70.81 also issued under Atomic Energy Act secs. 186, 187 (42 U.S.C. 2236, 2237). Section 70.82 also issued under Atomic Energy Act sec. 108 (42 U.S.C. 2138).

    0

    4. In Sec. 70.32, revise paragraphs (c)(1)(i), (ii), and (iii) to read as follows:

    Sec. 70.32 Conditions of licenses.

    * * * * *

    (c)(1) * * *

    (i) The program for control and accounting of uranium source material at a uranium enrichment facility and SNM at all applicable facilities as implemented pursuant to Sec. 70.22(b), or Sec. Sec. 74.31(b), 74.33(b), 74.41(b), or 74.51(b) of this chapter, as appropriate;

    (ii) The measurement control program for uranium source material at a uranium enrichment facility and for SNM at all applicable facilities as implemented pursuant to Sec. Sec. 74.31(b), 74.33(b), 74.45(c), or 74.59(e) of this chapter, as appropriate; and

    (iii) Other material control procedures as the Commission determines to be essential for the safeguarding of uranium source material at a uranium enrichment facility or of SNM and providing that the licensee shall make no change that would decrease the effectiveness of the material control and accounting program implemented pursuant to Sec. 70.22(b), or Sec. Sec. 74.31(b), 74.33(b), 74.41(b), or 74.51(b) of this chapter, and the measurement control program implemented pursuant to Sec. Sec. 74.31(b), 74.33(b), 74.41(b), or 74.59(e) of this chapter without the prior approval of the Commission. A licensee desiring to make changes that would decrease the effectiveness of its material control and accounting program or its measurement control program shall submit an application for amendment to its license pursuant to Sec. 70.34.

    * * * * *

    0

    5. The authority citation for part 72 continues to read as follows:

    PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-

    RELATED GREATER THAN CLASS C WASTE

    Authority: Atomic Energy Act secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C. 2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233, 2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy Reorganization Act sec. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); National Environmental Policy Act sec. 102 (42 U.S.C. 4332); Nuclear Waste Policy Act secs. 131, 132, 133, 135, 137, 141 148 (42 U.S.C. 10151, 10152, 10153, 10155, 10157, 10161, 10168); sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504 note); Energy Policy Act of 2005, Pub. L. No. 109-

    58, 119 Stat. 549 (2005).

    Section 72.44(g) also issued under secs. Nuclear Waste Policy Act 142(b) and 148(c), (d) (42 U.S.C. 10162(b), 10168(c), (d)). Section 72.46 also issued under Atomic Energy Act sec. 189 (42 U.S.C. 2239); Nuclear Waste Policy Act sec. 134 (42 U.S.C. 10154). Section 72.96(d) also issued under Nuclear Waste Policy Act sec. 145(g) (42 U.S.C. 10165(g)). Subpart J also issued under Nuclear Waste Policy Act secs. 117(a), 141(h) (42 U.S.C. 10137(a), 10161(h)). Subpart K is also issued under sec. 218(a) (42 U.S.C. 10198).

    0

    6. In Sec. 72.9, revise paragraph (b) to read as follows:

    Sec. 72.9 Information collection requirements: OMB approval.

    * * * * *

    (b) The approved information collection requirements contained in this part appear in Sec. Sec. 72.7, 72.11, 72.16, 72.22 through 72.34, 72.42, 72.44, 72.48 through 72.56, 72.62, 72.70 through 72.75, 72.77, 72.79, 72.80, 72.90, 72.92, 72.94, 72.98, 72.100, 72.102, 72.103, 72.104, 72.108, 72.120, 72.126, 72.140 through 72.176, 72.180 through 72.186, 72.192, 72.206, 72.212, 72.218, 72.230,72.232, 72.234, 72.236, 72.240, 72.242, 72.244, 72.248.

    * * * * *

    0

    7. Revise Sec. 72.72 to read as follows:

    Sec. 72.72 Material control and accounting requirements for source material and special nuclear material.

    (a) Each licensee shall follow the requirements of Sec. 40.61 and Sec. 40.64 of this chapter for source material.

    (b) Each licensee shall follow the requirements of 10 CFR part 74, subparts A and B, for special nuclear material.

    0

    8. Revise Sec. 72.74 to read as follows:

    Sec. 72.74 Reports of accidental criticality.

    (a) Each licensee shall notify the NRC Headquarters Operations Center within one hour of discovery of accidental criticality.

    (b) Each licensee shall make the notifications required by paragraph (a) of this section to the NRC Headquarters Operations Center via any available telephone system to ensure that a report is received within one hour.

    (c) Reports required under Sec. 73.71 of this chapter need not be duplicated under the requirements of this section.

    0

    9. Remove and reserve Sec. Sec. 72.76 and 72.78.

    Sec. 72.76 Removed and Reserved

    Sec. 72.78 Removed and Reserved

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    10. The authority citation for part 74 continues to read as follows:

    Page 67246

    PART 74--MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL

    Authority: Atomic Energy Act secs. 53, 57, 161, 182, 183, 223, 234, 1701 (42 U.S.C. 2073, 2077, 2201, 2232, 2233, 2273, 2282, 2297f); Energy Reorganization Act secs. 201, 202, 206 (42 U.S.C. 5841, 5842, 5846); Government Paperwork Elimination Act sec. 1704 (44 U.S.C. 3504 note).

    0

    11. In Sec. 74.2, revise the last sentence in paragraph (a) to read as follows:

    Sec. 74.2 Scope.

    (a) * * * The general reporting and recordkeeping requirements of subpart B of this part also apply to licensees who possess spent nuclear fuel at independent spent fuel storage installations.

    * * * * *

    0

    12. Add Sec. 74.3 to read as follows:

    Sec. 74.3 General performance objectives.

    In addition to any other requirements in this part, each licensee who is authorized to possess or use SNM in a quantity greater than 350 grams of contained uranium-235, uranium-233, or plutonium, or any combination thereof, at a fixed site, shall implement and maintain a material control and accounting program that enables the licensee to achieve the following general performance objectives in a timely manner:

    (a) Maintain accurate, current, and reliable information on, and confirm the quantities and locations of SNM in its possession;

    (b) Detect, respond to, and resolve any anomaly indicating a possible loss, theft, diversion, or misuse of SNM;

    (c) Permit rapid determination of whether an actual loss, theft, diversion, or misuse of SNM has occurred;

    (d) Provide information to aid in the investigation and recovery of missing SNM in the event of an actual loss, theft, diversion, or misuse; and

    (e) Control access to MC&A information that might assist adversaries to carry out acts of theft, diversion, misuse, or radiological sabotage involving SNM.

    0

    13. In Sec. 74.4:

    0

    a. Remove the definition for Effective kilograms of special nuclear material;

    0

    b. Add the definitions for Accounting, Custodian, Item control system, Item control area, Material balance area, and Material control and accounting in alphabetical order; and

    0

    c. Revise the definitions for Formula quantity, Special nuclear material of low strategic significance, and Special nuclear material of moderate strategic significance.

    The additions and revisions read as follows:

    Sec. 74.4 Definitions.

    * * * * *

    Accounting means a system that documents the quantities of special nuclear material (SNM) held on current inventory by the licensee, and includes tracking of receipts, shipments, and measured discards, and transfers of SNM.

    * * * * *

    Custodian means an individual authorized and qualified by the licensee who is responsible for controlling the movement of all SNM into, out of, and within a material balance area.

    * * * * *

    Formula quantity means strategic special nuclear material (SSNM) in any combination in a quantity of 5,000 grams or more computed by the formula, grams = (grams contained U-235) + 2.5 (grams U-233 + grams plutonium). This class of material is also referred to as a Category I quantity of material as shown in appendix A to this part.

    * * * * *

    Item control area (ICA) means a designated administrative area within the controlled access area, in which SNM is maintained in such a way that, at any time, a count of the items and the related material quantities can be obtained using the accounting system. Control of items moving into, out of, and within an ICA is by the identity of an item and its assigned material quantity.

    Item control system means a system tracking the creation, identity, element and isotopic content, location, and disposition of all items, which enables the licensee to maintain current knowledge of each item.

    * * * * *

    Material balance area (MBA) means a designated contiguous area in which the control of SNM is such that the quantity of material being moved into, out of, and within the MBA is an assigned value based on measurements of both the element content and the isotopic content.

    Material control and accounting (MC&A) means a program to control and account for certain types of nuclear material used at a licensed facility, including SNM and source material, and which controls and accounts for unauthorized use of equipment capable of producing enriched uranium. The purpose of an MC&A program is to deter and detect any loss, theft, diversion, misuse, or unauthorized production of nuclear material.

    * * * * *

    Special nuclear material of low strategic significance means:

    (1)(i) Less than an amount of SNM of moderate strategic significance, but more than 15 grams of uranium-235 (contained in uranium enriched to 20 percent or more in the U-235 isotope) or 15 grams of uranium-233 or 15 grams of plutonium or the combination of 15 grams when computed by the equation, grams = grams contained U-235 + grams plutonium + grams U-233; or

    (ii) Less than 10,000 grams but more than 1,000 grams of uranium-

    235 (contained in uranium enriched to 10 percent or more, but less than 20 percent in the U-235 isotope); or

    (iii) 10,000 grams or more of uranium-235 contained in uranium enriched above natural, but less than 10 percent in the U-235 isotope.

    (2) This class of material is also referred to as a Category III quantity of material as shown in appendix A to this part.

    Special nuclear material of moderate strategic significance means:

    (1)(i) Less than a formula quantity of SSNM but more than 1,000 grams of uranium-235 (contained in uranium enriched to 20 percent or more in the U-235 isotope) or more than 500 grams of uranium-233 or plutonium or in a combined quantity of more than 1,000 grams when computed by the equation, grams = (grams contained U-235) + 2 (grams U-

    233 + grams plutonium); or

    (ii) 10,000 grams or more of uranium-235 (contained in uranium enriched to 10 percent or more but less than 20 percent in the U-235 isotope).

    (2) This class of material is also referred to as a Category II quantity of material as shown in appendix A to this part.

    * * * * *

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    14. In Sec. 74.11, revise paragraph (b) to read as follows:

    Sec. 74.11 Reports of loss or theft or attempted theft or unauthorized production of special nuclear material.

    * * * * *

    (b) Each licensee shall make the notifications required by paragraph (a) of this section to the NRC Headquarters Operations Center via any available telephone system to ensure that a report is received within 1 hour.

    * * * * *

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    15. Revise Sec. 74.13 to read as follows:

    Sec. 74.13 Material status reports.

    (a) All licensees who possess or who had possessed in the previous reporting period one gram or more of irradiated or

    Page 67247

    non-irradiated SNM are required to submit both a Material Balance Report and a Physical Inventory Listing Report of these materials to the NMMSS in accordance with the instructions in paragraph (b) of this section and according to the following schedule:

    (1) Commercial power reactor licensees, authorized under part 50 or part 52 of this chapter shall submit both reports within 60 calendar days of the beginning of the physical inventory covered by the reports;

    (2) Research and test reactors, authorized under part 50 of this chapter shall submit both reports within 60 calendar days of the beginning of the physical inventory covered by the reports;

    (3) Independent spent fuel storage licensees, authorized under part 72 of this chapter shall submit both reports within 60 calendar days of the beginning of the physical inventory covered by the reports.

    (4) Licensees subject to Sec. 74.31 shall submit both reports within 60 calendar days of the beginning of the physical inventory covered by the reports;

    (5) Licensees operating uranium enrichment facilities shall submit both reports within 60 calendar days of the beginning of the physical inventory providing a total plant material balance as described in Sec. 74.33(c)(4)(i);

    (6) Licensees subject to subpart D of this part shall submit both reports within 60 calendar days of the beginning of the physical inventory covered by the reports;

    (7) Licensees subject to subpart E of this part shall submit both reports within 30 calendar days of the beginning of the physical inventory covered by the reports; and

    (8) All other licensees who possess, or had possessed in the previous reporting period, one gram or more of irradiated or non-

    irradiated SNM shall submit both reports between January 1 and March 31 of each year.

    (b) Each licensee shall prepare and submit the reports described in paragraph (a) of this section as follows:

    (1) Reports must be submitted for each Reporting Identification Symbol (RIS) account, including all holding accounts, concerning SNM that the licensee has received, produced, possessed, transferred, consumed, disposed, or lost.

    (2) Each licensee shall prepare and submit the reports described in this section as specified in the instructions in both NUREG/BR-0007 and NMMSS Report D-24 ``Personal Computer Data Input for NRC Licensees.''

    (i) This prescribed computer-readable report replaces the DOE/NRC Form 742, Material Balance Report, and DOE/NRC Form 742C, Physical Inventory Listing Report, which have been previously submitted in paper form.

    (ii) Copies of these instructions may be obtained from the U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety and Safeguards, Washington, DC 20555-0001 or by email to RidsNmssFcss.Resource@nrc.gov.

    (c) The Commission may permit a licensee to submit the reports at other times for good cause. Such requests must be submitted in writing to Chief, Material Control and Accounting Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555. The licensee must continue to report as required until such request is granted.

    (d) Any licensee who is required to submit routine Material Status Reports under Sec. 75.35 of this chapter (pertaining to implementation of the U.S./IAEA Safeguards Agreement) shall prepare and submit these reports only as provided in that section (instead of as provided in paragraphs (a) through (b) of this section).

    (e) Each licensee subject to the requirements of this section shall resolve any discrepancies identified during the report review and reconciliation process within 30 calendar days of notification of a discrepancy identified by the NRC.

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    16. In Sec. 74.15, revise paragraph (b)(2) to read as follows:

    Sec. 74.15 Nuclear material transaction reports.

    * * * * *

    (b) * * *

    (2) Perform independent tests to assure the accurate identification and measurement of the material received, including its weight and enrichment; except that a licensee authorized under parts 50 or 52 of this chapter receiving unirradiated fuel rods or unirradiated fuel assemblies or a licensee authorized under part 70 of this chapter receiving SNM contained in a sealed source that will not be opened need not perform such tests; and

    * * * * *

    0

    17. In Sec. 74.19, revise the section heading, paragraph (b), redesignate paragraph (d) as paragraph (e), and add a new paragraph (d) to read as follows:

    Sec. 74.19 Recordkeeping, procedures, item controls, and physical inventories.

    * * * * *

    (b) Each licensee authorized to possess special nuclear material, at any one time and site location, in a quantity greater than 350 grams of contained uranium-235, uranium-233, or plutonium, or any combination thereof, shall establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the SNM in its possession under the license. The licensee shall retain these procedures until the Commission terminates the license that authorizes possession of the special nuclear material and retain any superseded portion of the procedures for 3 years after the portion is superseded.

    * * * * *

    (d) Production or utilization facilities licensed under part 50 or 52 of this chapter and independent spent fuel storage installations licensed under part 72 of this chapter shall establish, document, implement, and maintain an item control system as defined in Sec. 74.4.

    * * * * *

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    18. In Sec. 74.31, revise paragraphs (a), (b), and (c) to read as follows:

    Sec. 74.31 Nuclear material control and accounting for special nuclear material of low strategic significance.

    (a) General performance objectives. (1) Each licensee who is authorized to possess and use a quantity greater than 350 grams of contained uranium-235 or SNM of low strategic significance (as defined in Sec. 74.4 and shown in appendix A to this part) at any site or contiguous sites subject to control by the licensee is subject to the performance objective requirements stated in Sec. 74.3.

    (2) Production or utilization facilities licensed under part 50 or 52 of this chapter, independent spent fuel storage installations licensed under part 72 of this chapter, and operations involving waste disposal are not subject to the requirements of subpart C of this part.

    (b) Implementation. Each applicant for a license, and each licensee that, upon application for modification of its license, would become newly subject to paragraph (a) of this section shall submit for approval an MC&A plan describing how the performance objectives of Sec. 74.3 and the requirements of paragraph (c) of this section will be met. The MC&A plan shall be implemented when a license is issued or modified to authorize the activities being addressed in paragraph (a) of this section, or by the date specified in a license condition.

    (c) Program capabilities. To achieve the Sec. 74.3 performance objectives, the MC&A plan must include the capabilities described in paragraphs

    Page 67248

    (c)(1) through (10) of this section, and require the licensee to:

    (1) Establish, document, and maintain a management structure that assures clear overall responsibility for material control and accounting functions, independence from production responsibilities, separation of key responsibilities, and adequate review and use of critical material control and accounting procedures;

    (2) Establish and maintain a measurement system, which assures that all quantities in the material accounting records are based on measured values;

    (3) Follow a measurement control program, which assures that measurement bias is estimated and significant biases are eliminated from inventory difference values of record;

    (4) In each inventory period, control total material control and accounting measurement uncertainty so that twice its standard error of the inventory difference (SEID) is less than the greater of 9,000 grams of U-235 or 0.25 percent of the active inventory, and assure that any measurement performed under contract is controlled so that the licensee can satisfy this requirement;

    (5) Unless otherwise required to satisfy part 75 of this chapter, perform a physical inventory at least every 12 months and, within 60 calendar days after the start of the inventory, reconcile and adjust the book inventory to the results of the physical inventory, and resolve, or report an inability to resolve, any inventory difference that is rejected by a statistical test that has a 90-percent power of detecting a discrepancy of a quantity of uranium-235 established by the NRC on a site-specific basis;

    (6) Establish, document, implement, and maintain an item control system as defined in Sec. 74.4. Store and handle or subsequently measure items in a manner such that unauthorized removals of individual items or any quantity of SNM from items will be detected. Exempted from this requirement are items in solution with a concentration of less than 5 grams of uranium-235 per liter and items of waste destined for burial or incineration;

    (7) Conduct and document shipper-receiver difference comparisons for all SNM receipts on a total shipment basis, and on an individual batch basis when required by part 75 of this chapter, and ensure that any shipper-receiver difference that is statistically significant and exceeds twice the estimated standard deviation of the difference estimator and 500 grams of uranium-235 is investigated and resolved;

    (8) Independently assess the effectiveness of the MC&A program at least every 24 months, and document management's action on prior assessment recommendations.

    (9) Maintain and follow procedures for tamper-safing (as defined in Sec. 74.4) of containers or vaults (as defined in Sec. 74.4) containing SNM, which include control of access to, and distribution of, unused seals and records;

    (10) Designate material balance areas and item control areas and assign custodial responsibility for each of these areas in a manner that ensures that such responsibility can be effectively executed for all SNM possessed under license.

    * * * * *

    0

    19. Revise Sec. 74.33 to read as follows:

    Sec. 74.33 Nuclear material control and accounting for uranium enrichment facilities authorized to produce special nuclear material of low strategic significance.

    (a) General performance objectives. Each licensee who is authorized to possess equipment capable of enriching uranium or operate an enrichment facility, and produce, possess, or use a quantity greater than 350 grams of contained uranium-235 or SNM of low strategic significance (as defined in Sec. 74.4 and shown in appendix A to this part) at any site or contiguous sites, subject to control by the licensee, is subject to the performance objective requirements stated in Sec. 74.3 and to the following performance objectives:

    (1) Maintain accurate, current, and reliable information on, and confirm the quantities and locations of source material (SM) in its possession;

    (2) Detect, respond to, and resolve any anomaly indicating a possible loss, theft, diversion, or misuse of SM;

    (3) Permit rapid determination of whether an actual loss, theft, diversion, or misuse of SM has occurred;

    (4) Provide information to aid in the investigation and recovery of missing SM in the event of an actual loss, theft, diversion, or misuse; and

    (5) Provide information to aid in the investigation of any unauthorized production of uranium, including unauthorized production of uranium enriched to 10 percent or more in the isotope U-235. (For centrifuge enrichment facilities this requirement does not apply to each cascade during its start-up process, not to exceed the first 24 hours.)

    (b) Implementation. Each applicant for a license who would, upon issuance of a license under any part of this chapter, be subject to the requirements of paragraph (a) of this section shall:

    (1) Submit for approval an MC&A plan describing how the performance objectives of Sec. Sec. 74.3 and 74.33(a), the program capabilities of Sec. 74.33(c), and the recordkeeping requirements of Sec. 74.33(d) will be met; and

    (2) Implement the NRC-approved MC&A plan submitted under paragraph (b)(1) of this section prior to:

    (i) The cumulative receipt of 5,000 grams of U-235 contained in any combination of natural, depleted, or enriched uranium; or

    (ii) The NRC's issuance of a license to test or operate the enrichment facility, whichever occurs first.

    (c) Program capabilities. To achieve the general performance objectives stated and referenced in paragraph (a) of this section, the MC&A plan must include the capabilities described in paragraphs (c)(1) through (10) of this section. The licensee shall establish, document, implement and maintain:

    (1) A management structure that ensures:

    (i) Clear overall responsibility for MC&A functions;

    (ii) Independence of MC&A management from production responsibilities;

    (iii) Separation of key MC&A responsibilities from each other; and

    (iv) Use of approved written MC&A procedures and periodic review of those procedures;

    (2) A measurement program that ensures that all quantities of SM and SNM in the accounting records are based on measured values;

    (3) A measurement control program that ensures that:

    (i) Measurement bias is estimated and minimized through the measurement control program, and any significant biases are eliminated from inventory difference values of record;

    (ii) All MC&A measurement systems are controlled so that twice the standard error of the inventory difference (SEID), based on all measurement error contributions, is less than the greater of 5,000 grams of U-235 or 0.25 percent of the U-235 of the active inventory for each total plant material balance; and

    (iii) Any measurements performed under contract are controlled so that the licensee can satisfy the requirements of paragraphs (c)(3)(i) and (ii) of this section;

    (4) A physical inventory program that provides for:

    (i) Performing, unless otherwise required to satisfy part 75 of this chapter, a dynamic (nonshutdown) physical inventory of in-process (e.g., in the enrichment equipment) uranium and U-235 at least every 65 calendar days, and performing a static physical

    Page 67249

    inventory of all other uranium and total U-235 contained in natural, depleted, and enriched uranium located outside of the enrichment processing equipment at least every 370 calendar days, with static physical inventories being conducted in conjunction with a dynamic physical inventory of in-process uranium and U-235 so as to provide a total plant material balance at least every 370 calendar days; and

    (ii) Reconciling and adjusting the book inventory to the results of the static physical inventory and resolving, or reporting an inability to resolve, any inventory difference that is rejected by a statistical test that has a 90-percent power of detecting a discrepancy of a quantity of U-235, established by the NRC on a site-specific basis, within 60 calendar days after the start of each static physical inventory;

    (5) A detection program, independent of production, which provides high assurance of detecting and resolving:

    (i) Production of uranium enriched to 10 percent or more in the U-

    235 isotope, to the extent that SNM of moderate strategic significance (as defined in Sec. 74.4) could be produced within any 370 calendar day period;

    (ii) Production of uranium enriched to 20 percent or more in the U-

    235 isotope; and

    (iii) Unauthorized production of uranium of low strategic significance (as defined in Sec. 74.4);

    (6) An item control system (as defined in Sec. 74.4). The system must ensure that items are stored and handled or subsequently measured in a manner such that unauthorized removal of any quantity of U-235, as individual items or as uranium contained in items, will be detected. Exempted from this requirement are items in solution with a concentration of less than 5 grams of uranium-235 per liter and items of waste destined for burial or incineration;

    (7) A system for conducting and documenting shipper-receiver difference comparisons for all source material and SNM receipts on a total shipment basis, and on an individual batch basis when required by part 75 of this chapter, to ensure that any shipper-receiver difference that is statistically significant and exceeds twice the estimated standard deviation of the difference estimator and 500 grams of uranium-235 is investigated and resolved;

    (8) An assessment program that:

    (i) Independently assesses the effectiveness of the MC&A program at least every 24 months;

    (ii) Documents the results of the above assessment;

    (iii) Documents management's findings on whether the MC&A program is currently effective; and

    (iv) Documents any actions taken on recommendations from prior assessments;

    (9) Procedures for tamper-safing (as defined in Sec. 74.4) of containers or vaults (as defined in Sec. 74.4) containing SNM, which include control of access to, and distribution of, unused seals and records;

    (10) Material balance areas and item control areas, and shall assign custodial responsibility for each of these areas in a manner that ensures that such responsibility can be effectively executed for all SM and SNM possessed under license.

    (d) Recordkeeping.

    (1) Each licensee shall establish records that will demonstrate that the performance objectives stated and referenced in paragraph (a) of this section and the program capabilities of paragraph (c) of this section have been met and maintain these records in an auditable form, available for inspection, for at least 3 years, unless a longer retention time is required by part 75 of this chapter.

    (2) Records that must be maintained pursuant to this part may be the original or a reproduced copy or a microform if such reproduced copy or microform is duly authenticated by authorized personnel and the microform is capable of producing a clear and legible copy after storage for the period specified by Commission regulations. The record may also be stored in electronic media with the capability for producing, on demand, legible, accurate, and complete records during the required retention period. Records such as letters, drawings, and specifications must include all pertinent information such as stamps, initials, and signatures.

    (3) The licensee shall maintain adequate safeguards against tampering with and loss of records.

    0

    20. In Sec. 74.41, revise paragraphs (a), (b), and (c) to read as follows:

    Sec. 74.41 Nuclear material control and accounting for special nuclear material of moderate strategic significance.

    (a) General performance objectives. (1) Each licensee who is authorized to possess and use SNM of moderate strategic significance (as defined in Sec. 74.4 and shown in appendix A of this part) or 1 kilogram or more but less than 5 kilograms of SSNM (as defined in Sec. 74.4 and shown in appendix A to this part) in irradiated fuel reprocessing operations at any site or contiguous sites subject to control by the licensee, is subject to the performance objective requirements stated in Sec. 74.3.

    (2) Production or utilization facilities licensed under part 50 or 52 of this chapter; licensees using reactor irradiated fuels involved in research, development, and evaluation programs in facilities other than irradiated fuel reprocessing plants; and operations involving waste disposal, are not subject to the requirements of subpart D of this part.

    (b) Implementation. Each applicant for a license, and each licensee that, upon application for modification of its license, would become newly subject to paragraph (a) of this section shall submit for approval an MC&A plan describing how the performance objectives of Sec. 74.3 and the requirements of paragraph (c) of this section will be met. The MC&A plan shall be implemented when a license is issued or modified to authorize the activities being addressed in paragraph (a) of this section, or by the date specified in a license condition.

    (c) Program capabilities. To achieve the Sec. 74.3 performance objectives, the MC&A plan must include the capabilities described in Sec. Sec. 74.43 and 74.45, and must incorporate checks and balances that are sufficient to detect falsification of data and reports that could conceal diversion of SNM by:

    (1) A single individual, including an employee in any position; or

    (2) Collusion between two individuals, one or both of whom have authorized access to SNM.

    0

    21. In Sec. 74.43, revise paragraphs (b)(3), (b)(5), (b)(6), (b)(7), and (c)(3); add new paragraph (c)(9); and revise paragraph (d)(5) to read as follows:

    Sec. 74.43 Internal controls, inventory, and records.

    * * * * *

    (b) * * *

    (3) The licensee shall provide for the adequate review, approval, and use of written MC&A procedures that are identified in the approved MC&A plan as being critical to the effectiveness of the described system.

    * * * * *

    (5) The licensee shall establish, document, implement, and maintain an item control system as defined in Sec. 74.4. The system must ensure that items are stored and handled or subsequently measured in a manner such that unauthorized removals of individual items or any quantity of material (as defined in Sec. 74.4) from items will be detected.

    (6) Exempted from the requirements of paragraph (b)(5) of this section are items in solution with a concentration

    Page 67250

    of less than 5 grams of U-235 per liter, and items of waste destined for burial or incineration.

    (7) Conduct and document shipper-receiver difference comparisons for all SNM receipts,

    * * * * *

    (c) * * *

    (3) Maintain and follow procedures for tamper-safing (as defined in Sec. 74.4) of containers or vaults (as defined in Sec. 74.4) containing SNM which include control of access to, and distribution of, unused seals and records;

    * * * * *

    (9) Designate material balance areas and item control areas, and assign custodial responsibility for each of these areas in a manner that ensures that such responsibility can be effectively executed for all SNM possessed under license.

    * * * * *

    (d) * * *

    (5) Establish records that will demonstrate that the performance objectives of Sec. 74.3 and Sec. 74.41(a)(1), the system capabilities of paragraphs (b) and (c) of this section, and Sec. 74.45(b) and (c) have been met, and maintain these records in an auditable form, available for inspection, for at least 3 years, unless a longer retention time is specified by Sec. 74.19(b), part 75 of this chapter, or by a specific license condition.

    0

    22. In Sec. 74.45, revise paragraph (c)(4) to read as follows:

    Sec. 74.45 Measurements and measurement control.

    * * * * *

    (c) * * *

    (4) Establish and maintain a measurement control system so that for each inventory period the standard error of the inventory difference (SEID) is less than 0.125 percent of the active inventory, and assure that any MC&A measurements performed under contract are controlled so that the licensee can satisfy this requirement.

    * * * * *

    0

    23. Revise Sec. 74.51 to read as follows:

    Sec. 74.51 Nuclear material control and accounting for strategic special nuclear material.

    (a) General performance objectives. (1) Each licensee who is authorized to possess and use five or more formula kilograms of strategic special nuclear material (SSNM), as defined in Sec. 74.4 and shown in appendix A to this part, at any site or contiguous sites subject to control by the licensee is subject to the performance objective requirements stated in Sec. 74.3, and to the following performance objectives:

    (i) Ongoing confirmation of the presence of SSNM in assigned locations;

    (ii) Timely detection of the possible abrupt loss of five or more formula kilograms of SSNM from an individual unit process; and

    (iii) Rapid determination of whether an actual loss of five or more formula kilograms of SSNM occurred.

    (2) Production or utilization facilities licensed under part 50 or 52 of this chapter, independent spent fuel storage installations licensed under part 72 of this chapter; and any licensee operations involving waste disposal, are not subject to the requirements of subpart E of this part.

    (b) Implementation. Each applicant for a license, and each licensee that, upon application for modification of its license, would become newly subject to paragraph (a) of this section shall submit for approval an MC&A plan describing how the performance objectives of Sec. 74.3 and paragraph (a) of this section will be achieved, and how the requirements of paragraph (c) of this section will be met. The MC&A plan shall be implemented when a license is issued or modified to authorize the activities being addressed in paragraph (a) of this section, or by the date specified in a license condition.

    (c) Program capabilities. To achieve the general performance objectives specified in Sec. 74.3 and paragraph (a) of this section, the MC&A plan must provide the capabilities described in Sec. Sec. 74.53, 74.55, 74.57 and 74.59 and must incorporate checks and balances that are sufficient to detect falsification of data and reports that could conceal diversion of SNM or SSNM by:

    (1) A single individual, including an employee in any position; or

    (2) Collusion between two individuals, one or both of whom have authorized access to SNM or SSNM.

    (d) Inventories. Notwithstanding Sec. 74.59(f)(1), licensees shall perform at least 3 physical inventories at intervals not to exceed 65 calendar days after implementation of the NRC-approved MC&A plan and shall continue to perform such inventories at intervals not to exceed 65 calendar days until performance acceptable to the NRC has been demonstrated and the Commission has issued formal approval to perform physical inventories at intervals not to exceed 185 calendar days. Licensees who have prior experience with process monitoring and/or can demonstrate acceptable performance against all MC&A plan commitments may request authorization to perform inventories at intervals not to exceed 185 calendar days at an earlier date.

    0

    24. In Sec. 74.53, revise the introductory text of paragraph (a), and paragraphs (a)(3), (a)(4), and (c)(1) to read as follows:

    Sec. 74.53 Process monitoring.

    (a) Licensees subject to Sec. 74.51 shall monitor internal transfers, storage, and processing of SSNM. The process monitoring must achieve the detection capabilities described in paragraph (b) of this section for all SSNM except:

    * * * * *

    (3) SSNM with an estimated measurement standard deviation greater than 5 percent that is either input or output material associated with a unit that processes less than five formula kilograms over a period of 95 calendar days; and

    (4) SSNM involved in research and development operations that process less than five formula kilograms during a period of seven calendar days.

    * * * * *

    (c) * * *

    (1) Perform material balance tests on a lot or a batch basis, as appropriate, or at intervals not to exceed 30 calendar days, whichever is sooner, and investigate any difference greater than 200 grams of plutonium or U-233 or 300 grams of U-235 that exceeds three times the estimated standard error of the inventory difference;

    * * * * *

    0

    25. In Sec. 74.57, revise the introductory text of paragraph (c) to read as follows:

    Sec. 74.57 Alarm resolution.

    * * * * *

    (c) Each licensee shall notify the NRC Headquarters Operations Center by telephone of any MC&A alarm that remains unresolved beyond the time period specified for its resolution in the licensee's MC&A plan. Notification must occur within 24 hours except when a holiday or weekend intervenes in which case the notification must occur on the next scheduled workday. The licensee may consider an alarm to be resolved if:

    * * * * *

    0

    26. In Sec. 74.59, revise paragraph (e)(7), the introductory text of paragraph (f)(1), and paragraphs (f)(2)(i), (h)(2)(ii), and (h)(5) to read as follows:

    Sec. 74.59 Quality assurance and accounting requirements.

    * * * * *

    (e) * * *

    (7) Investigate and take corrective action, as appropriate, to identify and reduce associated measurement biases when, for like material types (i.e., measured by the same measurement system), the net cumulative shipper/

    Page 67251

    receiver differences accumulated over a period not to exceed 185 calendar days results in a value greater than one formula kilogram or 0.1 percent of the total amount received.

    * * * * *

    (f) * * *

    (1) Except as required by part 75 of this chapter, perform a physical inventory at least every 185 calendar days and within 45 calendar days after the start of the ending inventory:

    * * * * *

    (2) * * *

    (i) Development of procedures for tamper-safing of containers or vaults containing SSNM not in process that include adequate controls to assure the validity of assigned SSNM values and that include control of access to, and distribution of, unused seals and records;

    * * * * *

    (h) * * *

    (2) * * *

    (ii) Any scrap measured with a standard deviation greater than 5 percent of the measured amount is recovered so that the results are segregated by inventory period and recovered within 185 calendar days of the end of the inventory period in which the scrap was generated except where it can be demonstrated that the scrap measurement uncertainty will not cause noncompliance with Sec. 74.59(e)(5).

    * * * * *

    (5) Designate material balance areas and item control areas and assign custodial responsibility for each of these areas in a manner that ensures that such responsibility can be effectively executed for all SSNM possessed under license.

    0

    27. Add appendix A to part 74 to read as follows:

    Appendix A to Part 74--Categories of Special Nuclear Material

    Notes:

    1. Sealed sources as defined in Sec. 74.4 are excluded from the quantities in the table.

    2. Irradiated fuel, which by virtue of its original fissile material content is included as Category I or II before irradiation, is reduced one category level, during the period of time that the radiation level from the fuel exceeds 1 Sv per hour (100 rads per hour) at 1 meter, unshielded.

    ----------------------------------------------------------------------------------------------------------------

    Isotopic Category I (Subpart Category II Category III

    Material composition E) (Subpart D) (Subpart C)

    ----------------------------------------------------------------------------------------------------------------

    Plutonium................ All plutonium 2,000 grams or more. Less than 2,000 500 grams or less,

    (element). grams, but more but more than 15

    than 500 grams. grams.

    Uranium-233.............. All U-233 2,000 grams or more. Less than 2,000 500 grams or less,

    enrichments. grams, but more but more than 15

    than 500 grams. grams.

    Uranium-235.............. Uranium enriched to 5,000 grams or more. Less than 5,000 1,000 grams or

    20% or more in grams, but more less, but more

    isotope U-235. than 1,000 grams. than 15 grams.

    Uranium enriched to .................... 10,000 grams or more Less than 10,000

    10%, but less than grams, but more

    20%, in isotope U- than 1,000 grams.

    235.

    Uranium enriched .................... .................... 10,000 grams or

    above 0.711%, but more.

    less than 10%, in

    isotope U-235.

    ----------------------------------------------------------------------------------------------------------------

    The formulae to calculate a quantity of SSNM as defined in Sec. 74.4 are as follows:

    Category I, 5000 grams or more of SSNM

    cir grams = grams contained U-235 + 2.5 (grams U-233 + grams Pu)

    Category II, less than 5000 grams but more than 1000 grams of SSNM

    cir grams = grams contained U-235 + 2 (grams U-233 + grams Pu)

    Category III, 1000 grams or less but more than 15 grams of SSNM

    cir grams = grams contained U-235 + grams U-233 + grams Pu.

    0

    28. The authority citation for part 150 continues to read as follows:

    PART 150--EXEMPTIONS AND CONTINUED REGULATORY AUTHORITY IN AGREEMENT STATES AND IN OFFSHORE WATERS UNDER SECTION 274

    Authority: Atomic Energy Act secs. 161, 181, 223, 234 (42 U.S.C. 2201, 2021, 2231, 2273, 2282); Energy Reorganization Act sec. 201 (42 U.S.C. 5841); Government Paperwork Elimination Act sec. 1704 (44 U.S.C. 3504 note); Energy Policy Act of 2005, Public Law 109-58, 119 Stat. 594 (2005).

    Sections 150.3, 150.15, 150.15a, 150.31, 150.32 also issued under Atomic Energy Act secs. 11e(2), 81, 83, 84 (42 U.S.C. 2014e(2), 2111, 2113, 2114). Section 150.14 also issued under Atomic Energy Act sec. 53 (42 U.S.C. 2073).

    Section 150.15 also issued under Nuclear Waste Policy Act secs. 135 (42 U.S.C. 10155, 10161). Section 150.17a also issued under Atomic Energy Act sec. 122 (42 U.S.C. 2152). Section 150.30 also issued under Atomic Energy Act sec. 234 (42 U.S.C. 2282).

    0

    29. In Sec. 150.17 revise paragraphs (a) and (b) to read as follows:

    Sec. 150.17 Submission to commission of nuclear material status reports.

    (a) Except as specified in paragraph (d) of this section and Sec. 150.17a, all licensees who possess or who had possessed in the previous reporting period, under an Agreement State license, one gram or more of irradiated or non-irradiated special nuclear material are required to submit both a Material Balance Report and a Physical Inventory Listing Report of these materials to the NMMSS in accordance with the instructions in paragraph (a)(1) of this section. Both reports shall be submitted between January 1 and March 31 of each year.

    (1) Each licensee shall prepare and submit the reports described in this section as follows:

    (i) Reports must be submitted for each Reporting Identification Symbol (RIS) account, including all special nuclear material that the licensee has received, produced, possessed, transferred, consumed, disposed, or lost.

    (ii) Each licensee shall prepare and submit the reports described in this section as specified in the instructions in both NUREG/BR-0007 and NMMSS Report D-24, ``Personal Computer Data Input for NRC Licensees.''

    (iii) This prescribed computer-readable report replaces the DOE/NRC Form 742, Material Balance Report, and DOE/NRC Form 742C, Physical Inventory Listing Report, which have been previously submitted in paper form.

    (iv) Copies of these instructions may be obtained from the U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety and Safeguards, Washington, DC 20555-0001 or by email to RidsNmssFcss.Resource@nrc.gov.

    (2) The Commission may permit a licensee to submit the reports at other times for good cause. Such requests must be submitted in writing to Chief, Material Control and Accounting Branch, Division of Fuel Cycle Safety

    Page 67252

    and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555. The licensee must continue to report as required until such request is granted.

    (3) Any licensee who is required to submit routine Material Status Reports under Sec. 75.35 of this chapter (pertaining to implementation of the U.S./IAEA Safeguards Agreement) shall prepare and submit these reports only as provided in that section (instead of as provided in paragraphs (a) through (b) of this section).

    (4) Each licensee subject to the requirements of this section shall resolve any discrepancies identified during the report review and reconciliation process within 30 calendar days of notification of a discrepancy identified by the NRC.

    (b) Except as specified in paragraph (d) of this section and Sec. 150.17a, each person possessing, or who had possessed in the previous reporting period, at any one time and location, under an Agreement State license:

    (1) One kilogram or more of uranium or thorium source material with foreign obligations, shall document holdings as of September 30 of each year and submit the material status reports to the Commission within 30 days. Alternatively, these reports may be submitted with the licensee's material status reports on special nuclear material filed under part 74 of this chapter. This statement must be submitted to the address specified in the reporting instructions in NUREG/BR-0007, and include the RIS assigned by the Commission.

    (2) One kilogram or more of uranium or thorium source material in the operation of enrichment services, down blending uranium that has an initial enrichment of the U-235 isotope of 10 percent or more, or in the fabrication of mixed-oxide fuels shall complete and submit, in computer-readable format, Material Balance and Physical Inventory Listing Reports concerning source material that the licensee has received, produced, possessed, transferred, consumed, disposed, or lost. Reports must be submitted for each RIS account including all holding accounts. Each licensee shall prepare and submit these reports as specified in the instructions in NUREG/BR-0007 and NMMSS Report D-

    24, ``Personal Computer Data Input for NRC Licensees.'' These reports must document holdings as of September 30 of each year and be submitted to the Commission within 30 days. Alternatively, these reports may be submitted with the licensee's material status reports on special nuclear material filed under part 74 of this chapter. Copies of the reporting instructions may be obtained by writing to the U.S. Nuclear Regulatory Commission, Division of Fuel Cycle Safety and Safeguards, Washington, DC 20555-0001, or by email to RidsNmssFcss.Resource@nrc.gov. Each licensee required to report material balance, and inventory information, as described in this part, shall resolve any discrepancies identified during the report review and reconciliation process within 30 calendar days of the notification of a discrepancy identified by the NRC.

    * * * * *

    Dated at Rockville, Maryland, this October 23, 2013.

    For the Nuclear Regulatory Commission.

    Annette Vietti-Cook,

    Secretary of the Commission.

    FR Doc. 2013-25617 Filed 11-7-13; 8:45 am

    BILLING CODE 7590-01-P