| Page Range | 38982-38997 | |
| FR Document | 2018-16863 |
[Federal Register Volume 83, Number 153 (Wednesday, August 8, 2018)] [Proposed Rules] [Pages 38982-38997] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2018-16863] ======================================================================== Proposed Rules Federal Register ________________________________________________________________________ This section of the FEDERAL REGISTER contains notices to the public of the proposed issuance of rules and regulations. The purpose of these notices is to give interested persons an opportunity to participate in the rule making prior to the adoption of the final rules. ======================================================================== Federal Register / Vol. 83, No. 153 / Wednesday, August 8, 2018 / Proposed Rules [[Page 38982]] DEPARTMENT OF ENERGY 10 CFR Part 830 RIN 1992-AA57 Nuclear Safety Management AGENCY: Office of Environment, Health, Safety and Security, U.S. Department of Energy. ACTION: Notice of proposed rulemaking and notice of public meetings. ----------------------------------------------------------------------- SUMMARY: The Department of Energy (DOE or the Department) publishes a proposed rule to amend regulations concerning nuclear safety management. These regulations govern the conduct of DOE contractors, DOE personnel, and other persons conducting activities (including providing items and services) that affect, or may affect, the safety of DOE nuclear facilities. The proposed revisions reflect the experience gained in the implementation of the regulations over the past seventeen years, with specific improvements to the process for facility hazard categorization, the unreviewed safety question process, and the review and approval of safety documentation. The proposed revisions are intended to enhance operational efficiency while maintaining robust safety performance. DATES: Public comment on this proposed rule will be accepted until October 9, 2018. For dates and more information on the public meetings for this proposed rulemaking, see SUPPLEMENTARY INFORMATION. ADDRESSES: You may submit comments, identified by RIN 1992-AA57, by any of the following methods: 1. Federal eRulemaking Portal: http://www.regulations.gov. Follow the instructions for submitting comments. 2. Email: [email protected]. Include RIN 1992-AA57 in the subject line of the email. Please include the full body of your comments in the text of the message or as an attachment. 3. Mail: U.S. Department of Energy, Office of Nuclear Safety, AU- 30, 1000 Independence Avenue SW, Washington, DC 20585. Due to potential delays in DOE's receipt and processing of mail sent through the U.S. Postal Service, we encourage respondents to submit comments electronically to ensure timely receipt. FOR FURTHER INFORMATION CONTACT: Mr. Garrett Smith, U.S. Department of Energy, Office of Nuclear Safety, AU-30, 1000 Independence Avenue SW, Washington, DC 20585; (301) 903-2996 or [email protected]. SUPPLEMENTARY INFORMATION: Public meetings for this proposed rulemaking will be held in: 1. Richland, WA at the HAMMER Federal Training Facility, Building 6091, Room 10, 2890 Horn Rapids Road, Richland, WA, on August 16th, 2018. 2. Albuquerque, NM at the Albuquerque Marriott, Sandia Room, 2101 Louisiana Blvd. NE, Albuquerque, NM, on September 6th, 2018. 3. Oak Ridge, TN at the Oak Ridge Associated Universities, Pollard Technology Conference Center Auditorium, 210 Badger Avenue, Oak Ridge, TN, on September 25th, 2018. 4. Aiken, SC at the University of South Carolina--Aiken, Business and Education Building, Room 124, 471 University Parkway, Aiken, SC, on September 27th, 2018. All public meetings will be held from 1 p.m. to 4:30 p.m. and from 6 p.m. to 8:30 p.m. local time. Interested persons who wish to speak at the public meeting should telephone the Office of Nuclear Safety, (301) 903-2996, by 4:30 p.m. Eastern Time on August 13th, 2018 for Richland, WA, on August 31st, 2018 for Albuquerque, NM, on September 18th, 2018 for Oak Ridge, TN, and on September 20th, 2018 for Aiken, SC. Each presentation is limited to 20 minutes. I. Introduction and Background A. Introduction B. Procedural History of the Rule II. Discussion of Proposed Rule A. Discussion of Key Proposed Changes B. Proposed Changes in Order of Appearance III. Public Comment Procedures A. Written Comments B. Public Meetings IV. Regulatory Review A. Review Under Executive Order 12866 B. Review Under Executive Orders 13771 and 13777 C. Regulatory Flexibility Act D. Paperwork Reduction Act E. National Environmental Policy Act F. Unfunded Mandates Reform Act of 1995 G. Treasury and General Government Appropriations Act, 1999 H. Executive Order 13132 I. Executive Order 12988 J. Treasury and General Government Appropriations Act, 2001 K. Executive Order 13211 V. Approval of the Office of the Secretary I. Introduction and Background A. Introduction Pursuant to the Atomic Energy Act of 1954, as amended (the AEA), the Department of Energy (DOE or the Department) owns and leases nuclear and non-nuclear facilities at various locations in the United States. These facilities are operated either by DOE or by contractors with DOE oversight. Activities at these facilities include, but are not limited to: Research, testing, production, disassembly, or transporting nuclear materials. DOE regulations governing nuclear safety at these facilities are set forth in the Nuclear Safety Management rule (10 CFR part 830). The regulations were issued in response to external assessments from the National Academy of Sciences (NAS), the enactment of the Price-Anderson Amendments Act of 1988 (PAAA), and DOE efforts to improve safety at DOE nuclear facilities. Aspects of 10 CFR part 830 were finalized and issued from 1994 to 2001, covering core safety requirements for quality assurance and facility safety basis. Over the past 17 years, DOE has gained considerable experience in the implementation of 10 CFR part 830, and is proposing to modify the requirements to incorporate that experience and help ensure more effective safety performance. B. Procedural History of the Rule On December 9, 1991, DOE published Procedural Rules for DOE Nuclear Activities (56 FR 64290) and a Notice of Proposed Rulemaking and Public Hearing (1991 Notice, 56 FR 64316) to add Parts 820 and 830 to Title 10 of the Code of Federal Regulation (CFR).\1\ Title [[Page 38983]] 10 CFR part 830 was proposed to establish safety management requirements for DOE nuclear facilities. DOE issued, as final, the sections of 10 CFR part 830 related to the initial provisions (Sec. Sec. 830.1-830.7) and Subpart A--General Provisions, (Sec. Sec. 830.100-830.120) on April 5, 1994 (1994 Notice, 59 FR 15843). --------------------------------------------------------------------------- \1\ The Department proposed 10 CFR part 820 (Part 820), Procedural Rules for DOE Nuclear Activities, to establish the procedural requirements for enforcement activities in accordance with PAAA. On August 17, 1993, the Department issued the Procedural Regulations for DOE Nuclear Activities in final form as 10 CFR part 820 (58 FR 43680). Part 820 establishes the procedures for DOE enforcement actions and for issuing civil and criminal penalties for contractor, subcontractor, and supplier violations of DOE nuclear safety requirements. --------------------------------------------------------------------------- The Department issued a Notice of Limited Reopening of the Comment Periods for the remaining topics to be addressed in 10 CFR part 830 on August 31, 1995, and for a second, unrelated, rule (Reopening Notice, 60 FR 45381). On October 10, 2000, the Department published an Interim Final Rule and Opportunity for Public Comment (65 FR 60291) which amended the nuclear safety regulations to (1) establish and maintain safety bases for Hazard Category 1, 2, and 3 DOE nuclear facilities and perform work in accordance with safety bases, and (2) clarify that the quality assurance work process requirements apply to standards and controls adopted to meet regulatory or contract requirements that may affect nuclear safety (Interim Final Rule). The Interim Final Rule was also issued to provide further opportunity for public comment on the rule. Following the public comment period, the Department issued a Final Rule on January 10, 2001 (66 FR 1810). II. Discussion of Proposed Rule A. Discussion of Key Proposed Changes 1. DOE Standard 1027--Section 830.202 of the regulations requires that DOE nuclear facilities be categorized consistent with DOE-STD- 1027-92 (``Hazard Categorization and Accident Analysis Techniques for compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports,'' Change Notice 1, September 1997). The Department continues to believe that the methodology in DOE-STD-1027-92 Ch 1 is sufficient and supports the categorization of DOE nuclear facilities. In 2001, when Subpart B of 10 CFR part 830 was issued, not every Hazard Category 1, 2, and 3 DOE nuclear facility was categorized using a standardized methodology, and therefore consistent application of the cited reference, without change, was appropriate. DOE now proposes, after two decades of experience in facility categorization using DOE-STD-1027-92, Ch 1, to amend Sec. 830.202(b)(3) by adding ``or successor document''. This change would allow the Department to revise the standard to include up-to-date research, data, and DOE experience with implementation. This would be consistent with DOE's practice to periodically evaluate and revise DOE Technical Standards and would follow the development, review, and approval process described in DOE Order 252.1A, Technical Standards Program. The Technical Standards Program process requires concurrence from all affected Departmental elements prior to issuance of any standard. DOE also proposes to amend Section C, Scope, of Appendix A to remove the reference to the specific version of DOE-STD-1027, for consistency with the revision in Sec. 830.202. DOE would also remove Table 1 of Appendix A and replace that table with a definition for Hazard Category 1, 2, and 3 DOE nuclear facilities in Sec. 830.3 that references DOE-STD-1027-92 or successor document. The removal of Table 1 would allow successor revisions to more clearly link the determination of Hazard Category 1, 2, 3, and below hazard category 3 to the methodology in the Standard. The concept that Hazard Category 1 will have higher potential consequences and Hazard Category 3 will have lower potential consequences will be maintained throughout all successor documents of DOE-STD-1027. 2. Unreviewed Safety Question (USQ) Process--A situation or potential situation outside the bounds of the current safety analysis for a Hazard Category 1, 2, or 3 nuclear facility (as documented in its approved safety analysis) constitutes an Unreviewed Safety Question under the current regulations. Section 830.203 allows contractors to make changes to the facility, to change site or facility procedures, and to conduct tests and/or experiments without prior DOE approval when these activities do not involve an Unreviewed Safety Question and do not require any change to Technical Safety Requirements. The proposed change to Appendix A to Subpart B of 10 CFR part 830-- General Statement of Safety Basis Policy, H, Unreviewed Safety Questions, would add the sentence, ``The contractor is allowed to make editorial and format changes to its USQ procedure while maintaining DOE approval.'' This proposal would focus the requirement to obtain DOE's approval on changes with the potential to impact on the safety basis of the facility. DOE also proposes to modify Sec. 830.3, Definitions, by changing the definition for Unreviewed Safety Question (USQ). The current definition includes four situations that define a USQ: (1) The probability of the occurrence or the consequences of an accident or the malfunction of equipment important to safety previously evaluated in the documented safety analysis (DSA) could be increased; (2) The possibility of an accident or malfunction of a different type than any evaluated previously in the documented safety analysis could be created; or (3) A margin of safety could be reduced; or (4) The documented safety analysis may not be bounding or may be otherwise inadequate. As explained in the following paragraphs, the proposed definition would remove the third situation: ``A margin of safety could be reduced''. The current set of four situations that define an USQ in 10 CFR 830.3 reflected standard nuclear industry practice and was an adaptation of 10 CFR 50.59, changes, tests and experiments, used by the United States Nuclear Regulatory Commission (NRC). The NRC, in 1968, added to Sec. 50.59 the concept of ``margin of safety as defined in the basis for any technical specification is reduced.'' In issuing 10 CFR part 830, DOE modified this question to simply read ``A margin of safety could be reduced''. In addition to adapting the NRC process, DOE included the situation of ``(4) The documented safety analysis may not be bounding or may otherwise be inadequate.'' The NRC, after 30 years of experience implementing Sec. 50.59, issued an October 21, 1998, Notice of Proposed Rulemaking to change the criteria associated with margin of safety, explaining that ``the phrases `margin of safety' and `as defined in the basis for any technical specification' in the third criterion have been the subject of differing interpretations because the rule does not define what constitutes a margin of safety or a basis for any technical specification in the context of Sec. Sec. 50.59 and 72.48. In addition, some have questioned the need for the third criterion on `margin of safety.' '' The third criterion refers to the existence of two prior questions associated with creation, consequences, and likelihood of accidents and equipment malfunction. The revision to 10 CFR part 50 removing the term ``margin of safety'' from 10 CFR 50.59 was issued as a final rule on October 4, 1999. DOE's experience with the margin of safety criteria is similar to that expressed by the NRC in its rulemaking, specifically, that the other existing criteria provide sufficient guidance to identify facility and safety basis changes that warrant DOE approval. Feedback from periodic surveys considering a broad-range of USQ determinations indicated that the ``margin of safety'' [[Page 38984]] criterion has not provided benefit independent of the criteria DOE is retaining in the definition of the USQ process. In addition, stakeholder feedback noted that the ``margin of safety'' criterion was subjectively interpreted and often diverted safety resources without a corresponding safety benefit. Therefore, the proposed removal of the criterion related to ``margin of safety'' would enhance DOE and contractor operational effectiveness, without reducing the level of safety provided by the current practice. The current practice allows contractors to conduct certain specified activities without prior DOE approval, when these activities do not cause an Unreviewed Safety Question (and when they do not require Technical Safety Requirements changes).\2\ --------------------------------------------------------------------------- \2\ DOE's implementation guidance associated with these criteria is DOE G 424.1-1B Chg 2, Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements. Based on the four criteria defining a situation involving a USQ in 10 CFR part 830, DOE G 424.1-1B Chg 2 contains seven questions. The last question related to the concept of the margin of safety. If DOE adopts this proposal in a final rule, DOE would also conduct a process to consider removal of the question from the DOE Guide. --------------------------------------------------------------------------- 3. DOE Approval of Annual DSA Updates--As stated above, DOE currently requires the contractor, in Sec. 830.203, Unreviewed Safety Question process, to obtain DOE approval prior to taking any action determined to involve a USQ. Additionally, in Sec. 830.202 Safety basis, DOE requires the contractor to annually submit to DOE either the updated DSA for approval or a letter stating that there have been no changes in the DSA since the prior submission. This effectively requires the contractor to submit changes to the DSA for DOE approval twice. Currently, DOE provides implementation guidance for this approval process in DOE-STD-1104-2016, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents, Section 7.1.2, Review of Safety Basis Changes and DSA Annual Updates. The guidance states that ``Review and approval of revisions and annual updates are a matter of endorsing the incorporation of changes in the safety basis since the last approval rather than performing a new assessment of the previously approved safety basis documents.'' While the guidance is clear in the intent to drive focus of DOE's approval to the change identified in the USQ process, the regulations' additional requirement for a second approval has led to considerable implementation challenges, and unnecessary review iterations without providing additional safety benefit. Therefore, DOE is proposing to change the requirement in Sec. 830.202, Safety basis, to require the current DSA be provided to DOE annually, but not to require DOE approval at that time. Additional guidance would also be included in Appendix A to Subpart B of 10 CFR part 830--General Statement of Safety Basis Policy, F, Documented Safety Analysis, to make clear that DOE's review and approval of the safety analysis is intended to be focused on changes submitted through the USQ process, but may require DOE approval if DOE has reason to believe a portion of the safety basis has substantially changed. DOE would continue to have the authority to review the safety basis at any time. DOE would maintain the ability to direct the contractor to incorporate in the safety basis any changes, conditions, or hazard controls. 4. Definition and Application of New Facilities, Major Modification, Preliminary Documented Safety Analysis, and Existing Facilities--The current definitions of a New DOE nuclear facility, Major Modification, Preliminary documented safety analysis, and Existing DOE nuclear facility (and applications of those definitions within the rule) reference specific dates related to the issuance of the rule and the need to bring DOE nuclear facilities into the regulatory framework. DOE is proposing to change the definitions to clearly recognize that all current DOE nuclear facilities are already within this regulatory framework and that new DOE nuclear facilities would be those that are in design or under construction that do not yet have a DOE approved safety basis. Additionally, the specific definition of an existing DOE nuclear facility is being proposed to be deleted. DOE proposes instead to rely upon a new definition of Hazard Category 1, 2, and 3 DOE nuclear facilities and the specific endpoint of a DOE approved safety basis to delineate between a new facility and an existing facility. DOE also proposes to change the definition of a Major modification to remove the completion date of the facility. The definition would rely upon a criteria of a substantial change to the existing safety basis for the facility. This would link the meaning of ``Major modification'' to changes to existing Hazard Category 1, 2, or 3 nuclear facilities via the existence of a safety basis for the facility. Furthermore, additional clarity is proposed within 10 CFR part 830, subpart B, to highlight that the concept of ``Major modification'' would only apply to existing Hazard Category 1, 2, or 3 DOE nuclear facilities (i.e., nuclear facilities with an approved safety basis). DOE proposes to change the definition of Preliminary documented safety analysis to maintain consistency with other proposed changes to the definitions related to nuclear facilities. B. Proposed Changes in Order of Appearance The specific proposed changes to 10 CFR part 830 are summarized below in the order in which they appear: 1. In proposed Sec. 830.3 ``Definitions,'' the current definition for Existing DOE nuclear facility would be deleted, a definition for Hazard Category 1, 2, and 3 DOE nuclear facilities has been proposed, and there would be a modification of the current definition of New Hazard Category 1, 2, and 3 DOE nuclear facility. These changes are designed to improve the delineation between new and existing facilities. The definition for Major modification would be changed to remove the effective date associated with the original issuance of the rule. The definition for Preliminary documented safety analysis would be changed to better reflect the intent of preliminary documented safety analysis being associated with Hazard Category 1, 2, or 3 DOE nuclear facilities rather than all DOE nuclear facilities. The definition for Safety management system would be changed to include the specific title of 48 CFR 970.5223-1, Integration of environment, safety, and health into work planning and execution. The definition for Unreviewed Safety Question (USQ) would be changed by adding ``or'' to the end of (2), deleting ``(3) A margin of safety could be reduced; or'', and renumbering (4) as (3). 2. In proposed Sec. 830.201 ``Performance of Work,'' current Sec. 830.201 would be changed by adding ``DOE-approved'' to modify safety basis to maintain consistency with Sec. 830.207, DOE approval of safety basis. 3. Proposed Sec. 830.202(b)(3) would be changed to add ``or successor document'' to modify DOE-STD-1027-92 (``Hazard Categorization and Accident Analysis Techniques for compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports,'' Change Notice 1, September 1997). This proposed change would allow DOE to modify the methodology used to perform hazard categorization consistent with DOE's policy of maintaining technical standards to reflect updated knowledge and methods. Current Sec. 830.202(c)(2) would be changed to read, ``(2) Annually provide DOE the current documented safety analysis or a letter stating that [[Page 38985]] there have been no changes in the documented safety analysis since the prior submittal; and''. These proposed changes reflect the removal of the requirement for DOE to annually approve the documented safety analysis, and are intended to focus DOE's approval on the existing requirement to approve changes through the USQ process. 4. In proposed Sec. 830.203 ``Unreviewed safety question process,'' current Sec. 830.203(a) would be changed by adding ``DOE- approved'' as a modifier to USQ, and by changing the word ``process'' to ``procedure''. These proposed changes are to clarify the connection between references to the DOE-approved procedure in proposed Sec. 830.203(a), Sec. 830.203(b), and Sec. 830.203(c). Current Sec. 830.203(b) would be deleted, since DOE no longer has existing facilities operating outside of 10 CFR part 830. In the current Sec. 830.203(c), which is proposed to be redesignated as Sec. 830.203(b), the word ``new'' has been proposed to be moved to match a proposed change in the definition of New Hazard Category 1, 2, and 3 nuclear facility, and ``207(d)'' would be changed to ``207(a)'' to reflect changes to Sec. 830.207. Current Sec. 830.203(d) would be redesignated as Sec. 830.203(c). Current Sec. 830.203(e) would be redesignated as Sec. 830.203(d). Current Sec. 830.203(f) would be redesignated as Sec. 830.203(e), ``submit'' would be replaced by ``provide'', and ``submissions'' would be replaced by ``submittal'' to better reflect that the document is being given to DOE for review, but not for approval. Current Sec. 830.203(g) would be redesignated as Sec. 830.203(f), and the text would be changed to read ``initiated to meet paragraph (f)(1) of this section'' consistent with citation changes in this section. 5. In proposed Sec. 830.204 ``Documented safety analysis,'' current Sec. 830.204(a) would be updated by changing ``Table 2'' to ``Table 1'' to reflect the deletion of Table 1 and re-numbering of subsequent tables. 6. In proposed Sec. 830.206 ``Preliminary documented safety analysis,'' current Sec. 830.206 would be changed to read ``Prior to construction of a new Hazard Category 1, 2, or 3 DOE nuclear facility or a major modification to an existing Hazard Category 1, 2, or 3 DOE nuclear facility, the contractor responsible for the design and construction of the new facility or major modification must:'' To reflect changes to the definitions in Sec. 830.3. Current Sec. 830.206(b)(1) would be changed to add, ``, or successor document'' as a modifier to ``DOE Order 420.1, Facility Safety'' to reflect the ongoing updates to the current version of the DOE order. 7. In proposed Sec. 830.207 ``DOE approval of safety basis,'' current Sec. 830.207(a) would be deleted, as DOE no longer has existing Hazard Category 1, 2, or 3 facilities operated outside of 10 CFR part 830. Current Sec. 830.207(b) would be changed by adding ``updated or amended'' to modify ``safety basis'', moving the word ``existing'' to before the phrase ``Hazard Category 1, 2, or 3 DOE nuclear facility'' to better match the revised definition, and by deleting ``in effect on October 10, 2000, or as approved by DOE at a later date'' to reflect that all Hazard Category 1, 2, or 3 DOE nuclear facilities already operate within 10 CFR part 830. Current Sec. 830.207(c) would be deleted, as DOE no longer has existing Hazard Category 1, 2, or 3 facilities operated outside of 10 CFR part 830. Current Sec. 830.207(d) would be redesignated as Sec. 830.207(a) and updated to reflect the changes in definitions in Sec. 830.3. As a result, the proposed Sec. 830.207(a) would now read as: ``With respect to a new Hazard Category 1, 2, or 3 DOE nuclear facility or a major modification to an existing Hazard Category 1, 2, or 3 DOE nuclear facility, a contractor may not begin operation of the facility or modification prior to the issuance of a safety evaluation report in which DOE approves the safety basis for the facility or modification.'' 8. In proposed Appendix A to Subpart B to 10 CFR part 830--General Statement of Safety Basis Policy current ``A. Introduction'' would be modified by replacing a reference to an outdated DOE Policy with a specific statement that reflects current DOE policy and would now read as follows, ``This Appendix does not create any new requirements and should be used consistently with DOE's policy that work be conducted safely and efficiently and in a manner that ensures protection of workers, the public, and the environment.'' 9. In proposed Appendix A to Subpart B to 10 CFR part 830--General Statement of Safety Basis Policy current ``C. Scope, 1.'' would be changed by replacing the reference to ``DOE-STD-1027-92 Change Notice 1, September 1997'' with a general reference to DOE-STD-1027 to reflect the proposed change to allow successor versions of DOE-STD-1027 to be used, the reference to ``Table 1'' would be deleted to reflect the proposed deletion of Table 1. The proposed sentences now would read, ``A contractor must establish and maintain a safety basis for a Hazard Category 1, 2, or 3 DOE nuclear facility because these facilities have the potential for significant radiological consequences. DOE-STD-1027 sets forth the methodology for categorizing a DOE nuclear facility based on the inventory of radioactive materials.'' Current ``C. Scope, 2.'' Would be changed to delete the parenthetical reference to ``including radiological facilities'', and by adding ``DOE'' to the reference to Hazard Category 1, 2, and 3 nuclear facilities to match changes to definitions within Sec. 830.3. Current ``C. Scope'' Table 1 is proposed for deletion for consistency with the proposal to allow use of subsequent versions of DOE-STD-1027, since Table 1 references the specific content of DOE-STD-1027-92, Change Notice 1, September 1997. 10. In proposed Appendix A to Subpart B to 10 CFR part 830--General Statement of Safety Basis Policy, current ``E. Enforcement of Safety Basis Requirements, 4.'' would be changed by deleting the word ``however'' to improve clarity. 11. In proposed Appendix A to Subpart B to 10 CFR part 830--General Statement of Safety Basis Policy current ``F. Documented Safety Analysis, 3.'' would be changed by adding ``as: (1) part of the initial submittal; (2) when revisions are submitted as part of a positive USQ or major modification; (3) if DOE has reason to believe a portion of the safety basis to be inadequate, or; (4) if DOE has reason to believe a portion of the safety basis has substantially changed. DOE will review the DSA'' to better define when and why DOE would review a DSA. This change is proposed to be consistent with proposed changes to DOE's requirement to annually approve the DSA. Current ``F. Documented Safety Analysis, 3.'' would also be changed by adding ``in the Safety Evaluation Report'' to the end of the last sentence in that section, which currently reads, ``A documented safety analysis must contain any conditions or changes required by DOE.'' This change is proposed to clarify how DOE directs conditions and changes required by DOE. Additionally, Current ``F. Documented Safety Analysis, 3.'' would be changed by adding the following sentences, ``Generally, DOE's review of the annual submittal may be limited to ensuring that the results of USQs have been adequately incorporated into the DSA. If additional changes are proposed by the contractor and included in the annual update that have not been previously approved by DOE or have not been evaluated as a part of the USQ process, DOE must review and approve these changes. DOE has the authority to review the safety basis at any time.'' [[Page 38986]] This proposed change is in support of focusing DOE's approval of changes in the DSA to the incorporation of USQ's or as DOE determines are necessary to maintain safe operations, rather than the previous annual process. Current ``F. Documented Safety Analysis, 4.'' would be changed by renumbering the reference to ``Table 2'' to ``Table 1'' to reflect the deletion of Table 1. Current ``F. Documented Safety Analysis'' would be changed by changing the title of ``Table 2'' to ``Table 1'' to reflect the deletion of Table 1. Current ``F. Documented Safety Analysis, 5.'' would be changed by renumbering the reference to ``Table 2'' to ``Table 1'' to reflect the deletion of Table 1, by changing the reference to the definition of nuclear facility to re- state the existing definition within Sec. 830.3 instead of paraphrasing the definition, by renumbering the reference to ``Table 3'' to ``Table 2'' to reflect the deletion of Table 1, and by replacing ``specific nuclear facilities'' with ``terms'' in reference to the content within Table 1. Current ``F. Documented Safety Analysis'' would be changed by renumbering the title of ``Table 3'' to ``Table 2'' to reflect the proposed deletion of Table 1 and changing the reference to ``Table 2'' to ``Table 1'' to reflect the proposed deletion of Table 1. Current ``F. Documented Safety Analysis, 6.'' would be changed to delete the phrase ``If construction begins after December 11, 2000'' and by adding ``or successor document'' as a modifier to ``DOE Order 420.1, Facility Safety'' to reflect the ongoing updates to the current version of the DOE order. 12. In proposed Appendix A to Subpart B to 10 CFR part 830--General Statement of Safety Basis Policy current ``G. Hazard Controls, 2.'' would be changed to add ``or successor document'' as a modifier to ``DOE Order 420.1, Facility Safety'' to reflect the ongoing updates to the current version of the DOE order. Current ``G. Hazard Controls, 4.'' would be changed to update the reference to DOE Guide 423.1-1B and by adding, ``or successor document'' to reflect the ongoing updates to the current version of the DOE guide. Current ``G. Hazard Controls, 4.'' would be changed by changing the reference to ``Table 4'' to ``Table 3'' to reflect the proposed deletion of Table 1. Current ``G. Hazard Controls'' would be changed by changing the title of the table from ``Table 4'' to ``Table 3'' to reflect the proposed deletion of Table 1. 13. In proposed Appendix A to Subpart B to 10 CFR part 830--General Statement of Safety Basis Policy current ``H. Unreviewed Safety Questions, 3.'' Would be changed to update the reference to DOE Guide 424.1-1B Chg 2, to update the title of the referenced guide to ``Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements,'' to add ``or successor document'' to reflect the ongoing updates to the current version of the DOE guide, and by adding the sentence, ``The contractor is allowed to make editorial and format changes to its USQ procedure while maintaining DOE approval.'' The additional sentence wold be provided to better delineate those aspects of the USQ process on which DOE approval focuses. 14. Throughout 10 CFR part 830, the term ``Hazard Category'' would be capitalized to improve consistency with the usage within the DOE regulatory structure. III. Public Comment Procedures A. Written Comments Interested persons are invited to participate in this proceeding by submitting data, views, or arguments. Written comments should be submitted to the address, and in the form, indicated in the ADDRESSES section of this notice of proposed rulemaking. To help DOE review the comments, interested persons are asked to refer to specific proposed rule provisions, if possible. If you submit information that you believe to be exempt by law from public disclosure, you should submit one complete copy, as well as one copy from which the information claimed to be exempt by law from public disclosure has been deleted. DOE is responsible for the final determination with regard to disclosure or nondisclosure of the information and for treating it accordingly under the DOE Freedom of Information regulations at 10 CFR 1004.11. B. Public Meetings Public meetings will be held at the times, dates, and places indicated at the start of the SUPPLEMENTARY INFORMATION section of this notice of proposed rulemaking. Any person who is interested in making an oral presentation should make a phone request to the person and telephone number in the SUPPLEMENTARY INFORMATION section by 4:30 p.m. on the date specified for making such requests. The person should provide a daytime phone number where he or she can be reached. Each oral presentation will be limited to 20 minutes. Persons making an oral presentation are requested to bring 3 copies of their prepared statement to the meeting and submit them to the registration desk prior to the meeting. IV. Regulatory Review A. Review Under Executive Order 12866 This notice of proposed rulemaking has been determined not to be a significant regulatory action under Executive Order 12866, ``Regulatory Planning and Review,'' 58 FR 51735 (Oct. 4, 1993). Accordingly, this notice of proposed rulemaking was not subject to review by the Office of Information and Regulatory Affairs of the Office of Management and Budget. B. Review Under Executive Orders 13771 and 13777 On January 30, 2017, the President issued Executive Order 13771, ``Reducing Regulation and Controlling Regulatory Costs.'' That Order stated the policy of the executive branch is to be prudent and financially responsible in the expenditure of funds, from both public and private sources. The Order stated it is essential to manage the costs associated with the governmental imposition of private expenditures required to comply with Federal regulations. This proposed rule is expected to be an E.O. 13771 deregulatory action. Additionally, on February 24, 2017, the President issued Executive Order 13777, ``Enforcing the Regulatory Reform Agenda.'' The Order required the head of each agency designate an agency official as its Regulatory Reform Officer (RRO). Each RRO oversees the implementation of regulatory reform initiatives and policies to ensure that agencies effectively carry out regulatory reforms, consistent with applicable law. Further, E.O. 13777 requires the establishment of a regulatory task force at each agency. The regulatory task force is required to make recommendations to the agency head regarding the repeal, replacement, or modification of existing regulations, consistent with applicable law. At a minimum, each regulatory reform task force must attempt to identify regulations that: (i) Eliminate jobs, or inhibit job creation; (ii) Are outdated, unnecessary, or ineffective; (iii) Impose costs that exceed benefits; (iv) Create a serious inconsistency or otherwise interfere with regulatory reform initiatives and policies; (v) Are inconsistent with the requirements of Information Quality Act, or the guidance issued pursuant to that Act, in particular those regulations that rely in whole or in part on data, information, or methods that are not [[Page 38987]] publicly available or that are insufficiently transparent to meet the standard for reproducibility; or (vi) Derive from or implement Executive Orders or other Presidential directives that have been subsequently rescinded or substantially modified. DOE concludes that this final rule is consistent with the directives set forth in these executive orders. This provisions in this proposed rule are intended, as described in section II, to enhance operational efficiency while maintaining robust safety performance at DOE nuclear facilities. C. Regulatory Flexibility Act The Regulatory Flexibility Act (5 U.S.C. 601 et seq.) requires preparation of an initial regulatory flexibility analysis for any rule that by law must be proposed for public comment, unless the agency certifies that the rule, if promulgated, will not have a significant economic impact on a substantial number of small entities. As required by Executive Order 13272, ``Proper Consideration of Small Entities in Agency Rulemaking,'' 67 FR 53461 (Aug. 16, 2002), DOE published procedures and policies on February 19, 2003, to ensure that the potential impacts of its rules on small entities are properly considered during the rulemaking process. 68 FR 7990. DOE has made its procedures and policies available on the Office of the General Counsel's website (http://energy.gov/gc/office-general-counsel). DOE has reviewed this proposed rule under the provisions of the Regulatory Flexibility Act and the procedures and policies published on February 19, 2003. The proposed rule would incorporate the experience of more than a decade of implementation to improve the effectiveness of the DOE nuclear safety regulatory framework while maintaining safety performance. Requirements that are considered duplicative or of little value have been proposed to be removed. DOE is proposing four key changes in this proposed rule, as described in II. Discussion of Proposed Rule, A. Discussion of Key Proposed Changes. The changes in this proposed rule are all expected to reduce burden on affected DOE contractors. On this basis, DOE certifies that this proposed rule would not have a significant economic impact on a substantial number of small entities. Accordingly, DOE has not prepared a regulatory flexibility analysis for this rulemaking. DOE's certification and supporting statement of factual basis will be provided to the Chief Counsel for Advocacy of the Small Business Administration pursuant to 5 U.S.C. 605(b). D. Paperwork Reduction Act The information collection necessary to administer DOE's nuclear safety program under 10 CFR part 830 is subject to OMB approval under the Paperwork Reduction Act, 44 U.S.C. 3501 et seq. The information collection provisions of this rule are not substantially different from those contained in DOE contracts with DOE prime contractors covered by this rule and were previously approved by the Office of Management and Budget (OMB) and under OMB Control No. 1910-0300. Public reporting burden for the certification is estimated to average 1.91 hours per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information. Notwithstanding any other provision of the law, no person is required to respond to, nor shall any person be subject to a penalty for failure to comply with, a collection of information subject to the requirements of the PRA, unless that collection of information displays a currently valid OMB Control Number. E. National Environmental Policy Act DOE has determined that this proposed rule is covered under the Categorical Exclusion in DOE's National Environmental Policy Act regulations at paragraph A.5 of Appendix A to Subpart D, 10 CFR part 1021, which applies to rulemaking that interprets or amends an existing rule or regulation without changing the environmental effect of the rule or regulation that is being amended. The proposed rule would amend DOE's regulations by removing duplicative approval requirements, updating definitions, and increasing the efficiency of internal processes. These proposed amendments are primarily procedural and would not change the environmental effect of 10 CFR part 830. Accordingly, neither an environmental assessment nor an environmental impact statement is required. F. Unfunded Mandates Reform Act of 1995 Title II of the Unfunded Mandates Reform Act of 1995 (UMRA) requires each Federal agency to assess the effects of Federal regulatory actions on State, local, and Tribal governments and the private sector. Public Law 104-4, sec. 201 (codified at 2 U.S.C. 1531). For regulatory actions likely to result in a rule that may cause the expenditure by State, local, and Tribal governments, in the aggregate, or by the private sector of $100 million or more in any one year (adjusted annually for inflation), section 202 of UMRA requires a Federal agency to publish a written statement that estimates the resulting costs, benefits, and other effects on the national economy. (2 U.S.C. 1532(a), (b)) UMRA also requires a Federal agency to develop an effective process to permit timely input by elected officers of State, local, and Tribal governments on a ``significant intergovernmental mandate,'' and requires an agency plan for giving notice and opportunity for timely input to potentially affected small governments before establishing any requirements that might significantly or uniquely affect them. On March 18, 1997, DOE published a statement of policy on its process for intergovernmental consultation under UMRA. 62 FR 12820. (This policy is also available at http://energy.gov/gc/office-general-counsel.) DOE examined this proposed rule according to UMRA and its statement of policy and has tentatively determined that the rule contains neither an intergovernmental mandate, nor a mandate that may result in the expenditure by State, local, and Tribal government, in the aggregate, or by the private sector, of $100 million or more in any year. Accordingly, no further assessment or analysis is required under UMRA. G. Treasury and General Government Appropriations Act, 1999 Section 654 of the Treasury and General Government Appropriations Act, 1999, 5 U.S.C. 601 note, requires Federal agencies to issue a Family Policymaking Assessment for any proposed rule that may affect family wellbeing. While this proposed rule would apply to individuals who may be members of a family, the rule would not have any impact on the autonomy or integrity of the family as an institution. Accordingly, DOE has concluded that it is not necessary to prepare a Family Policymaking Assessment. H. Executive Order 13132 Executive Order 13132, ``Federalism,'' 64 FR 43255 (Aug. 4, 1999), imposes certain requirements on agencies formulating and implementing policies or regulations that preempt State law or that have federalism implications. Agencies are required to examine the constitutional and statutory authority supporting any action that would limit the policymaking discretion of the States and carefully assess the necessity for such actions. DOE has examined this proposed rule and has determined that it would not preempt State law and [[Page 38988]] would not have a substantial direct effect on the States, on the relationship between the national government and the States, or on the distribution of power and responsibilities among the various levels of government. No further action is required by Executive Order 13132. I. Executive Order 12988 With respect to the review of existing regulations and the promulgation of new regulations, section 3(a) of Executive Order 12988, ``Civil Justice Reform,'' 61 FR 4729 (Feb. 7, 1996), imposes on Executive agencies the general duty to adhere to the following requirements: (1) Eliminate drafting errors and ambiguity; (2) write regulations to minimize litigation; and (3) provide a clear legal standard for affected conduct rather than a general standard and promote simplification and burden reduction. With regard to the review required by section 3(a), section 3(b) of Executive Order 12988 specifically requires that Executive agencies make every reasonable effort to ensure that the regulation: (1) Clearly specifies the preemptive effect, if any; (2) clearly specifies any effect on existing Federal law or regulation; (3) provides a clear legal standard for affected conduct while promoting simplification and burden reduction; (4) specifies the retroactive effect, if any; (5) adequately defines key terms; and (6) addresses other important issues affecting clarity and general draftsmanship under any guidelines issued by the Attorney General. Section 3(c) of Executive Order 12988 requires Executive agencies to review regulations in light of applicable standards in section 3(a) and section 3(b) to determine whether they are met or it is unreasonable to meet one or more of them. DOE has completed the required review and determined that, to the extent permitted by law, this proposed rule meets the relevant standards of Executive Order 12988. J. Treasury and General Government Appropriations Act, 2001 The Treasury and General Government Appropriations Act, 2001, 44 U.S.C. 3516 note, provides for agencies to review most disseminations of information to the public under guidelines established by each agency pursuant to general guidelines issued by OMB. OMB's guidelines were published at 67 FR 8452 (Feb. 22, 2002), and DOE's guidelines were published at 67 FR 62446 (Oct. 7, 2002). DOE has reviewed this proposed rule under the OMB and DOE guidelines and has concluded that it is consistent with applicable policies in those guidelines. K. Executive Order 13211 Executive Order 13211, ``Actions Concerning Regulations That Significantly Affect Energy Supply, Distribution, or Use,'' 66 FR 28355 (May 22, 2001), requires Federal agencies to prepare and submit to the Office of Information and Regulatory Affairs (OIRA) a Statement of Energy Effects for any proposed significant energy action. A ``significant energy action'' is defined as any action by an agency that promulgated or is expected to lead to promulgation of a final rule, and that: (1) Is a significant regulatory action under Executive Order 12866, or any successor order; and (2) is likely to have a significant adverse effect on the supply, distribution, or use of energy, or (3) is designated by the Administrator of OIRA as a significant energy action. For any proposed significant energy action, the agency must give a detailed statement of any adverse effects on energy supply, distribution, or use should the proposal be implemented, and of reasonable alternatives to the action and their expected benefits on energy supply, distribution, and use. This regulatory action has been determined to not be a significant regulatory action, and it would not have an adverse effect on the supply, distribution, or use of energy. Thus, this action is not a significant energy action. Accordingly, DOE has not prepared a Statement of Energy Effects. V. Approval of the Office of the Secretary The Secretary of Energy has approved the publication of this proposed rule. List of Subjects in 10 CFR Part 830 Administrative practice and procedure, DOE contracts, Environment, Federal buildings and facilities, Government contracts, Nuclear materials, Nuclear power plants and reactors, Nuclear safety, Penalties, Public health, Reporting and recordkeeping requirements, and Safety. Issued in Washington, DC, on August 1, 2018. Dan Brouillette, Deputy Secretary of Energy. For the reasons stated in the preamble, DOE proposes to revise 10 CFR part 830 to read as follows: PART 830--NUCLEAR SAFETY MANAGEMENT Sec. 830.1 Scope. 830.2 Exclusions. 830.3 Definitions. 830.4 General requirements. 830.5 Enforcement. 830.6 Recordkeeping. 830.7 Graded approach. Subpart A--Quality Assurance Requirements 830.120 Scope. 830.121 Quality Assurance Program (QAP). 830.122 Quality assurance criteria. Subpart B--Safety Basis Requirements 830.200 Scope. 830.201 Performance of work. 830.202 Safety basis. 830.203 Unreviewed safety question process. 830.204 Documented safety analysis. 830.205 Technical safety requirements. 830.206 Preliminary documented safety analysis. 830.207 DOE approval of safety basis. Appendix A to Subpart B to Part 830--General Statement of Safety Basis Policy Authority: 42 U.S.C. 2201; 42 U.S.C. 7101 et seq.; and 50 U.S.C. 2401 et seq. Sec. 830.1 Scope. This part governs the conduct of DOE contractors, DOE personnel, and other persons conducting activities (including providing items and services) that affect, or may affect, the safety of DOE nuclear facilities. Sec. 830.2 Exclusions. This part does not apply to: (a) Activities that are regulated through a license by the Nuclear Regulatory Commission (NRC) or a State under an Agreement with the NRC, including activities certified by the NRC under section 1701 of the Atomic Energy Act (Act); (b) Activities conducted under the authority of the Director, Naval Nuclear Propulsion, pursuant to Executive Order 12344, as set forth in Public Law 106-65; (c) Transportation activities which are regulated by the Department of Transportation; (d) Activities conducted under the Nuclear Waste Policy Act of 1982, as amended, and any facility identified under section 202(5) of the Energy Reorganization Act of 1974, as amended; and (e) Activities related to the launch approval and actual launch of nuclear energy systems into space. Sec. 830.3 Definitions. (a) The following definitions apply to this part: Administrative controls means the provisions relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. [[Page 38989]] Bases appendix means an appendix that describes the basis of the limits and other requirements in technical safety requirements. Critical assembly means special nuclear devices designed and used to sustain nuclear reactions, which may be subject to frequent core and lattice configuration change and which frequently may be used as mockups of reactor configurations. Criticality means the condition in which a nuclear fission chain reaction becomes self-sustaining. Design features means the design features of a nuclear facility specified in the technical safety requirements that, if altered or modified, would have a significant effect on safe operation. Document means recorded information that describes, specifies, reports, certifies, requires, or provides data or results. Documented safety analysis means a documented analysis of the extent to which a nuclear facility can be operated safely with respect to workers, the public, and the environment, including a description of the conditions, safe boundaries, and hazard controls that provide the basis for ensuring safety. Environmental restoration activities means the process(es) by which contaminated sites and facilities are identified and characterized and by which contamination is contained, treated, or removed and disposed. Fissionable materials means a nuclide capable of sustaining a neutron-induced chain reaction (e.g., uranium-233, uranium-235, plutonium-238, plutonium-239, plutonium-241, neptunium-237, americium- 241, and curium-244). Graded approach means the process of ensuring that the level of analysis, documentation, and actions used to comply with a requirement in this part are commensurate with: (i) The relative importance to safety, safeguards, and security; (ii) The magnitude of any hazard involved; (iii) The life cycle stage of a facility; (iv) The programmatic mission of a facility; (v) The particular characteristics of a facility; (vi) The relative importance of radiological and nonradiological hazards; and (vii) Any other relevant factor. Hazard means a source of danger (i.e., material, energy source, or operation) with the potential to cause illness, injury, or death to a person or damage to a facility or to the environment (without regard to the likelihood or credibility of accident scenarios or consequence mitigation). Hazard Category 1, 2, and 3 DOE nuclear facilities means nuclear facilities that meet the criteria for their respective hazard category consistent with the provisions of DOE-STD-1027-92, Change Notice 1, or successor document. Hazard Category 1, 2, and 3 DOE nuclear facilities are required to have safety bases established in accordance with Subpart B of this part. Hazard categories are based on their radioactive material inventories and the potential consequences to the public, workers, and the environment. Hazard Category 1 represents the highest potential consequence and Hazard Category 3 represents the lowest potential consequence of the facilities required to establish safety bases. Hazard controls means measures to eliminate, limit, or mitigate hazards to workers, the public, or the environment, including (i) Physical, design, structural, and engineering features; (ii) Safety structures, systems, and components; (iii) Safety management programs; (iv) Technical safety requirements; and (v) Other controls necessary to provide adequate protection from hazards. Item is an all-inclusive term used in place of any of the following: Appurtenance, assembly, component, equipment, material, module, part, product, structure, subassembly, subsystem, system, unit, or support systems. Limiting conditions for operation means the limits that represent the lowest functional capability or performance level of safety structures, systems, and components required for safe operations. Limiting control settings means the settings on safety systems that control process variables to prevent exceeding a safety limit. Low-level residual fixed radioactivity means the remaining radioactivity following reasonable efforts to remove radioactive systems, components, and stored materials. The remaining radioactivity is composed of surface contamination that is fixed following chemical cleaning or some similar process; a component of surface contamination that can be picked up by smears; or activated materials within structures. The radioactivity can be characterized as low-level if the smearable radioactivity is less than the values defined for removable contamination by 10 CFR part 835, Appendix D, Surface Contamination Values, and the hazard analysis results show that no credible accident scenario or work practices would release the remaining fixed radioactivity or activation components at levels that would prudently require the use of active safety systems, structures, or components to prevent or mitigate a release of radioactive materials. Major modification means a modification to a DOE nuclear facility that substantially changes the existing safety basis for the facility. New Hazard Category 1, 2, and 3 DOE nuclear facility means a Hazard Category 1, 2, or 3 DOE nuclear facility that is in design or under construction that does not yet have a DOE approved safety basis. Nonreactor nuclear facility means those facilities, activities or operations that involve, or will involve, radioactive and/or fissionable materials in such form and quantity that a nuclear or a nuclear explosive hazard potentially exists to workers, the public, or the environment, but does not include accelerators and their operations and does not include activities involving only incidental use and generation of radioactive materials or radiation such as check and calibration sources, use of radioactive sources in research and experimental and analytical laboratory activities, electron microscopes, and X- ray machines. Nuclear facility means a reactor or a nonreactor nuclear facility where an activity is conducted for or on behalf of DOE and includes any related area, structure, facility, or activity to the extent necessary to ensure proper implementation of the requirements established by this Part. Operating limits means those limits required to ensure the safe operation of a nuclear facility, including limiting control settings and limiting conditions for operation. Preliminary documented safety analysis means documentation prepared in connection with the design and construction of a new Hazard Category 1, 2, or 3 DOE nuclear facility or a major modification to an existing Hazard Category 1, 2, or 3 DOE nuclear facility that provides a reasonable basis for the preliminary conclusion that the nuclear facility can be operated safely through the consideration of factors such as: (i) The nuclear safety design criteria to be satisfied; (ii) A safety analysis that derives aspects of design that are necessary to satisfy the nuclear safety design criteria; and (iii) An initial listing of the safety management programs that must be developed to address operational safety considerations. [[Page 38990]] Process means a series of actions that achieves an end or result. Quality means the condition achieved when an item, service, or process meets or exceeds the user's requirements and expectations. Quality assurance means all those actions that provide confidence that quality is achieved. Quality Assurance Program (QAP) means the overall program or management system established to assign responsibilities and authorities, define policies and requirements, and provide for the performance and assessment of work. Reactor means any apparatus that is designed or used to sustain nuclear chain reactions in a controlled manner such as research, test, and power reactors, and critical and pulsed assemblies and any assembly that is designed to perform subcritical experiments that could potentially reach criticality; and, unless modified by words such as containment, vessel, or core, refers to the entire facility, including the housing, equipment and associated areas devoted to the operation and maintenance of one or more reactor cores. Record means a completed document or other media that provides objective evidence of an item, service, or process. Safety basis means the documented safety analysis and hazard controls that provide reasonable assurance that a DOE nuclear facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Safety class structures, systems, and components means the structures, systems, or components, including portions of process systems, whose preventive or mitigative function is necessary to limit radioactive hazardous material exposure to the public, as determined from safety analyses. Safety evaluation report means the report prepared by DOE to document: (i) The sufficiency of the documented safety analysis for a Hazard Category 1, 2, or 3 DOE nuclear facility; (ii) The extent to which a contractor has satisfied the requirements of Subpart B of this part; and (iii) The basis for approval by DOE of the safety basis for the facility, including any conditions for approval. Safety limits means the limits on process variables associated with those safety class physical barriers, generally passive, that are necessary for the intended facility function and that are required to guard against the uncontrolled release of radioactive materials. Safety management program means a program designed to ensure a facility is operated in a manner that adequately protects workers, the public, and the environment by covering a topic such as: Quality assurance; maintenance of safety systems; personnel training; conduct of operations; inadvertent criticality protection; emergency preparedness; fire protection; waste management; or radiological protection of workers, the public, and the environment. Safety management system means an integrated safety management system established consistent with 48 CFR 970.5223-1, Integration of environment, safety, and health into work planning and execution. Safety significant structures, systems, and components means the structures, systems, and components which are not designated as safety class structures, systems, and components, but whose preventive or mitigative function is a major contributor to defense in depth and/or worker safety as determined from safety analyses. Safety structures, systems, and components means both safety class structures, systems, and components and safety significant structures, systems, and components. Service means the performance of work, such as design, manufacturing, construction, fabrication, assembly, decontamination, environmental restoration, waste management, laboratory sample analyses, inspection, nondestructive examination/testing, environmental qualification, equipment qualification, repair, installation, or the like. Surveillance requirements means requirements relating to test, calibration, or inspection to ensure that the necessary operability and quality of safety structures, systems, and components and their support systems required for safe operations are maintained, that facility operation is within safety limits, and that limiting control settings and limiting conditions for operation are met. Technical safety requirements (TSRs) means the limits, controls, and related actions that establish the specific parameters and requisite actions for the safe operation of a nuclear facility and include, as appropriate for the work and the hazards identified in the documented safety analysis for the facility: Safety limits, operating limits, surveillance requirements, administrative and management controls, use and application provisions, and design features, as well as a bases appendix. Unreviewed Safety Question (USQ) means a situation where: (i) The probability of the occurrence or the consequences of an accident or the malfunction of equipment important to safety previously evaluated in the documented safety analysis could be increased; (ii) The possibility of an accident or malfunction of a different type than any evaluated previously in the documented safety analysis could be created; or (iii) The documented safety analysis may not be bounding or may be otherwise inadequate. Unreviewed Safety Question process means the mechanism for keeping a safety basis current by reviewing potential unreviewed safety questions, reporting unreviewed safety questions to DOE, and obtaining approval from DOE prior to taking any action that involves an unreviewed safety question. Use and application provisions means the basic instructions for applying technical safety requirements. (b) Terms defined in the Act or in 10 CFR part 820 and not defined in this section of the rule are to be used consistent with the meanings given in the Act or in 10 CFR part 820. Sec. 830.4 General requirements. (a) No person may take or cause to be taken any action inconsistent with the requirements of this part. (b) A contractor responsible for a nuclear facility must ensure implementation of, and compliance with, the requirements of this part. (c) The requirements of this part must be implemented in a manner that provides reasonable assurance of adequate protection of workers, the public, and the environment from adverse consequences, taking into account the work to be performed and the associated hazards. (d) If there is no contractor for a DOE nuclear facility, DOE must ensure implementation of, and compliance with, the requirements of this part. Sec. 830.5 Enforcement. The requirements in this part are DOE Nuclear Safety Requirements and are subject to enforcement by all appropriate means, including the imposition of civil and criminal penalties in accordance with the provisions of 10 CFR part 820. Sec. 830.6 Recordkeeping. A contractor must maintain complete and accurate records as necessary to substantiate compliance with the requirements of this part. [[Page 38991]] Sec. 830.7 Graded approach. Where appropriate, a contractor must use a graded approach to implement the requirements of this part, document the basis of the graded approach used, and submit that documentation to DOE. The graded approach may not be used in implementing the unreviewed safety question (USQ) process or in implementing technical safety requirements. Subpart A--Quality Assurance Requirements Sec. 830.120 Scope. This subpart establishes quality assurance requirements for contractors conducting activities, including providing items or services that affect, or may affect, nuclear safety of DOE nuclear facilities. Sec. 830.121 Quality Assurance Program (QAP). (a) Contractors conducting activities, including providing items or services, that affect, or may affect, the nuclear safety of DOE nuclear facilities must conduct work in accordance with the Quality Assurance criteria in Sec. 830.122. (b) The contractor responsible for a DOE nuclear facility must: (1) Submit a QAP to DOE for approval and regard the QAP as approved 90 days after submittal, unless it is approved or rejected by DOE at an earlier date. (2) Modify the QAP as directed by DOE. (3) Annually submit any changes to the DOE-approved QAP to DOE for approval. Justify in the submittal why the changes continue to satisfy the quality assurance requirements. (4) Conduct work in accordance with the QAP. (c) The QAP must: (1) Describe how the quality assurance criteria of Sec. 830.122 are satisfied. (2) Integrate the quality assurance criteria with the Safety Management System, or describe how the quality assurance criteria apply to the Safety Management System. (3) Use voluntary consensus standards in its development and implementation, where practicable and consistent with contractual and regulatory requirements, and identify the standards used. (4) Describe how the contractor responsible for the nuclear facility ensures that subcontractors and suppliers satisfy the criteria of Sec. 830.122. Sec. 830.122 Quality assurance criteria. The QAP must address the following management, performance, and assessment criteria: (a) Criterion 1--Management/Program. (1) Establish an organizational structure, functional responsibilities, levels of authority, and interfaces for those managing, performing, and assessing the work. (2) Establish management processes, including planning, scheduling, and providing resources for the work. (b) Criterion 2--Management/Personnel Training and Qualification. (1) Train and qualify personnel to be capable of performing their assigned work. (2) Provide continuing training to personnel to maintain their job proficiency. (c) Criterion 3--Management/Quality Improvement. (1) Establish and implement processes to detect and prevent quality problems. (2) Identify, control, and correct items, services, and processes that do not meet established requirements. (3) Identify the causes of problems and work to prevent recurrence as a part of correcting the problem. (4) Review item characteristics, process implementation, and other quality-related information to identify items, services, and processes needing improvement. (d) Criterion 4--Management/Documents and Records. (1) Prepare, review, approve, issue, use, and revise documents to prescribe processes, specify requirements, or establish design. (2) Specify, prepare, review, approve, and maintain records. (e) Criterion 5--Performance/Work Processes. (1) Perform work consistent with technical standards, administrative controls, and other hazard controls adopted to meet regulatory or contract requirements, using approved instructions, procedures, or other appropriate means. (2) Identify and control items to ensure their proper use. (3) Maintain items to prevent their damage, loss, or deterioration. (4) Calibrate and maintain equipment used for process monitoring or data collection. (f) Criterion 6--Performance/Design. (1) Design items and processes using sound engineering/scientific principles and appropriate standards. (2) Incorporate applicable requirements and design bases in design work and design changes. (3) Identify and control design interfaces. (4) Verify or validate the adequacy of design products using individuals or groups other than those who performed the work. (5) Verify or validate work before approval and implementation of the design. (g) Criterion 7--Performance/Procurement. (1) Procure items and services that meet established requirements and perform as specified. (2) Evaluate and select prospective suppliers on the basis of specified criteria. (3) Establish and implement processes to ensure that approved suppliers continue to provide acceptable items and services. (h) Criterion 8--Performance/Inspection and Acceptance Testing. (1) Inspect and test specified items, services, and processes using established acceptance and performance criteria. (2) Calibrate and maintain equipment used for inspections and tests. (i) Criterion 9--Assessment/Management Assessment. Ensure managers assess their management processes and identify and correct problems that hinder the organization from achieving its objectives. (j) Criterion 10--Assessment/Independent Assessment. (1) Plan and conduct independent assessments to measure item and service quality, to measure the adequacy of work performance, and to promote improvement. (2) Establish sufficient authority, and freedom from line management, for the group performing independent assessments. (3) Ensure persons who perform independent assessments are technically qualified and knowledgeable in the areas to be assessed. Subpart B--Safety Basis Requirements Sec. 830.200 Scope. This Subpart establishes safety basis requirements for Hazard Category 1, 2, and 3 DOE nuclear facilities. Sec. 830.201 Performance of work. A contractor must perform work in accordance with the DOE-approved safety basis for a Hazard Category 1, 2, or 3 DOE nuclear facility and, in particular, with the hazard controls that ensure adequate protection of workers, the public, and the environment. Sec. 830.202 Safety basis. (a) The contractor responsible for a Hazard Category 1, 2, or 3 DOE nuclear facility must establish and maintain the safety basis for the facility. (b) In establishing the safety basis for a Hazard Category 1, 2, or 3 DOE [[Page 38992]] nuclear facility, the contractor responsible for the facility must: (1) Define the scope of the work to be performed; (2) Identify and analyze the hazards associated with the work; (3) Categorize the facility consistent with DOE-STD-1027-92 (``Hazard Categorization and Accident Analysis Techniques for compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports,'' Change Notice 1, September 1997), or successor document; (4) Prepare a documented safety analysis for the facility; and (5) Establish the hazard controls upon which the contractor will rely to ensure adequate protection of workers, the public, and the environment. (c) In maintaining the safety basis for a Hazard Category 1, 2, or 3 DOE nuclear facility, the contractor responsible for the facility must: (1) Update the safety basis to keep it current and to reflect changes in the facility, the work and the hazards as they are analyzed in the documented safety analysis; (2) Annually provide DOE the current documented safety analysis or a letter stating that there have been no changes in the documented safety analysis since the prior submittal; and (3) Incorporate in the safety basis any changes, conditions, or hazard controls directed by DOE. Sec. 830.203 Unreviewed safety question process. (a) The contractor responsible for a Hazard Category 1, 2, or 3 DOE nuclear facility must establish, implement, and take actions consistent with a DOE-approved USQ procedure that meets the requirements of this section. (b) The contractor responsible for a new Hazard Category 1, 2, or 3 DOE nuclear facility must submit for DOE approval a procedure for its USQ process on a schedule that allows DOE approval in a safety evaluation report issued pursuant to section 207(a) of this Part. (c) The contractor responsible for a Hazard Category 1, 2, or 3 DOE nuclear facility must implement the DOE- approved USQ procedure in situations where there is a: (1) Temporary or permanent change in the facility as described in the existing documented safety analysis; (2) Temporary or permanent change in the procedures as described in the existing documented safety analysis; (3) Test or experiment not described in the existing documented safety analysis; or (4) Potential inadequacy of the documented safety analysis because the analysis potentially may not be bounding or may be otherwise inadequate. (d) A contractor responsible for a Hazard Category 1, 2, or 3 DOE nuclear facility must obtain DOE approval prior to taking any action determined to involve a USQ. (e) The contractor responsible for a Hazard Category 1, 2, or 3 DOE nuclear facility must annually provide to DOE a summary of the USQ determinations performed since the prior submittal. (f) If a contractor responsible for a Hazard Category 1, 2, or 3 DOE nuclear facility discovers or is made aware of a potential inadequacy of the documented safety analysis, it must: (1) Take action, as appropriate, to place or maintain the facility in a safe condition until an evaluation of the safety of the situation is completed; (2) Notify DOE of the situation; (3) Perform a USQ determination and notify DOE promptly of the results; and (4) Submit the evaluation of the safety of the situation to DOE prior to removing any operational restrictions initiated to meet paragraph (f)(1) of this section. Sec. 830.204 Documented safety analysis. (a) The contractor responsible for a Hazard Category 1, 2, or 3 DOE nuclear facility must obtain approval from DOE for the methodology used to prepare the documented safety analysis for the facility unless the contractor uses a methodology set forth in Table 1 of Appendix A to this Part. (b) The documented safety analysis for a Hazard Category 1, 2, or 3 DOE nuclear facility must, as appropriate for the complexities and hazards associated with the facility: (1) Describe the facility (including the design of safety structures, systems and components) and the work to be performed; (2) Provide a systematic identification of both natural and man- made hazards associated with the facility; (3) Evaluate normal, abnormal, and accident conditions, including consideration of natural and man-made external events, identification of energy sources or processes that might contribute to the generation or uncontrolled release of radioactive and other hazardous materials, and consideration of the need for analysis of accidents which may be beyond the design basis of the facility; (4) Derive the hazard controls necessary to ensure adequate protection of workers, the public, and the environment, demonstrate the adequacy of these controls to eliminate, limit, or mitigate identified hazards, and define the process for maintaining the hazard controls current at all times and controlling their use; (5) Define the characteristics of the safety management programs necessary to ensure the safe operation of the facility, including (where applicable) quality assurance, procedures, maintenance, personnel training, conduct of operations, emergency preparedness, fire protection, waste management, and radiation protection; and (6) With respect to a nonreactor nuclear facility with fissionable material in a form and amount sufficient to pose a potential for criticality, define a criticality safety program that: (i) Ensures that operations with fissionable material remain subcritical under all normal and credible abnormal conditions; (ii) Identifies applicable nuclear criticality safety standards; and (iii) Describes how the program meets applicable nuclear criticality safety standards. Sec. 830.205 Technical safety requirements. (a) A contractor responsible for a Hazard Category 1, 2, or 3 DOE nuclear facility must: (1) Develop technical safety requirements that are derived from the documented safety analysis; (2) Prior to use, obtain DOE approval of technical safety requirements and any change to technical safety requirements; and (3) Notify DOE of any violation of a technical safety requirement. (b) A contractor may take emergency actions that depart from an approved technical safety requirement when no actions consistent with the technical safety requirement are immediately apparent, and when these actions are needed to protect workers, the public or the environment from imminent and significant harm. Such actions must be approved by a certified operator for a reactor or by a person in authority as designated in the technical safety requirements for nonreactor nuclear facilities. The contractor must report the emergency actions to DOE as soon as practicable. (c) A contractor for an environmental restoration activity may follow the provisions of 29 CFR 1910.120 or 1926.65 to develop the appropriate hazard controls (rather than the provisions for technical safety requirements in paragraph (a) of this section), provided the activity involves either: (1) Work not done within a permanent structure, or [[Page 38993]] (2) The decommissioning of a facility with only low-level residual fixed radioactivity. Sec. 830.206 Preliminary documented safety analysis. Prior to construction of a new Hazard Category 1, 2, or 3 DOE nuclear facility or a major modification to an existing Hazard Category 1, 2, or 3 DOE nuclear facility, the contractor responsible for the design and construction of the new facility or major modification must: (a) Prepare a preliminary documented safety analysis for the facility, and (b) Obtain DOE approval of: (1) The nuclear safety design criteria to be used in preparing the preliminary documented safety analysis unless the contractor uses the design criteria in DOE Order 420.1, Facility Safety, or successor document; and (2) The preliminary documented safety analysis before the contractor can procure materials or components or begin construction; provided that DOE may authorize the contractor to perform limited procurement and construction activities without approval of a preliminary documented safety analysis if DOE determines that the activities are not detrimental to public health and safety and are in the best interests of DOE. Sec. 830.207 DOE approval of safety basis. (a) With respect to a new Hazard Category 1, 2, or 3 DOE nuclear facility or a major modification to an existing Hazard Category 1, 2, or 3 DOE nuclear facility, a contractor may not begin operation of the facility or modification prior to the issuance of a safety evaluation report in which DOE approves the safety basis for the facility or modification. (b) Pending issuance of a safety evaluation report in which DOE approves an updated or amended safety basis for an existing Hazard Category 1, 2, or 3 DOE nuclear facility, the contractor responsible for the facility must continue to perform work in accordance with the DOE-approved safety basis for the facility and maintain the existing safety basis consistent with the requirements of this Subpart. Appendix A to Subpart B to Part 830--General Statement of Safety Basis Policy A. Introduction This appendix describes DOE's expectations for the safety basis requirements of 10 CFR part 830, acceptable methods for implementing these requirements, and criteria DOE will use to evaluate compliance with these requirements. This Appendix does not create any new requirements and should be used consistently with DOE's policy that work be conducted safely and efficiently and in a manner that ensures protection of workers, the public, and the environment. B. Purpose 1. The safety basis requirements of part 830 require the contractor responsible for a DOE nuclear facility to analyze the facility, the work to be performed, and the associated hazards and to identify the conditions, safe boundaries, and hazard controls necessary to protect workers, the public and the environment from adverse consequences. These analyses and hazard controls constitute the safety basis upon which the contractor and DOE rely to conclude that the facility can be operated safely. Performing work consistent with the safety basis provides reasonable assurance of adequate protection of workers, the public, and the environment. 2. The safety basis requirements are intended to further the objective of making safety an integral part of how work is performed throughout the DOE complex. Developing a thorough understanding of a nuclear facility, the work to be performed, the associated hazards and the needed hazard controls is essential to integrating safety into management and work at all levels. Performing work in accordance with the safety basis for a nuclear facility is the realization of that objective. C. Scope 1. A contractor must establish and maintain a safety basis for a Hazard Category 1, 2, or 3 DOE nuclear facility because these facilities have the potential for significant radiological consequences. DOE-STD-1027 sets forth the methodology for categorizing a DOE nuclear facility based on the inventory of radioactive materials. 2. Unlike the quality assurance requirements of part 830 that apply to all DOE nuclear facilities the safety basis requirements only apply to Hazard Category 1, 2, and 3 DOE nuclear facilities and do not apply to nuclear facilities below Hazard Category 3. D. Integrated Safety Management 1. The safety basis requirements are consistent with integrated safety management. DOE expects that, if a contractor complies with the Department of Energy Acquisition Regulation (DEAR) clause on integration of environment, safety, and health into work planning and execution (48 CFR 970.5223-1, Integration of Environment, Safety and Health into Work Planning and Execution) and the DEAR clause on laws, regulations, and DOE directives (48 CFR 970.5204-2, Laws, Regulations and DOE Directives), the contractor will have established the foundation to meet the safety basis requirements. 2. The processes embedded in a safety management system should lead to a contractor establishing adequate safety bases and safety management programs that will meet the safety basis requirements of this Subpart. Consequently, the DOE expects if a contractor has adequately implemented integrated safety management, few additional requirements will stem from this Subpart and, in such cases, the existing safety basis prepared in accordance with integrated safety management provisions, including existing DOE safety requirements in contracts, should meet the requirements of this Subpart. 3. DOE does not expect there to be any conflict between contractual requirements and regulatory requirements. In fact, DOE expects that contract provisions will be used to provide more detail on implementation of safety basis requirements such as preparing a documented safety analysis, developing technical safety requirements, and implementing a USQ process. E. Enforcement of Safety Basis Requirements 1. Enforcement of the safety basis requirements will be performance oriented. That is, DOE will focus its enforcement efforts on whether a contractor operates a nuclear facility consistent with the safety basis for the facility and, in particular, whether work is performed in accordance with the safety basis. 2. As part of the approval process, DOE will review the content and quality of the safety basis documentation. DOE intends to use the approval process to assess the adequacy of a safety basis developed by a contractor to ensure that workers, the public, and the environment are provided reasonable assurance of adequate protection from identified hazards. Once approved by DOE, the safety basis documentation will not be subject to regulatory enforcement actions unless DOE determines that the information which supports the documentation is not complete and accurate in all material respects, as required by 10 CFR 820.11. This is consistent with the DOE enforcement provisions and policy in 10 CFR part 820. 3. DOE does not intend the adoption of the safety basis requirements to affect the existing quality assurance requirements or the existing obligation of contractors to comply with the quality assurance requirements. In particular, in conjunction with the adoption of the safety basis requirements, DOE revised the language in 10 CFR 830.122(e)(1) to make clear that hazard controls are part of the work processes to which a contractor and other persons must adhere when performing work. This obligation to perform work consistent with hazard controls adopted to meet regulatory or contract requirements existed prior to the adoption of the safety basis requirements and is both consistent with and independent of the safety basis requirements. 4. A documented safety analysis must address all hazards (that is, both radiological and nonradiological hazards) and the controls necessary to provide adequate protection to the public, workers, and the environment from these hazards. Section 234A of the Atomic Energy Act only authorizes DOE to issue civil penalties for violations of requirements related to nuclear safety. Therefore, DOE will impose civil penalties for violations of the safety basis requirements (including hazard controls) only if they are related to nuclear safety. F. Documented Safety Analysis 1. A documented safety analysis must demonstrate the extent to which a nuclear facility can be operated safely with respect to workers, the public, and the environment. [[Page 38994]] 2. DOE expects a contractor to use a graded approach to develop a documented safety analysis and describe how the graded approach was applied. The level of detail, analysis, and documentation will reflect the complexity and hazards associated with a particular facility. Thus, the documented safety analysis for a simple, low hazard facility may be relatively short and qualitative in nature, while the documented safety analysis for a complex, high hazard facility may be quite elaborate and more quantitative. DOE will work with its contractors to ensure a documented safety analysis is appropriate for the facility for which it is being developed. 3. Because DOE has ultimate responsibility for the safety of its facilities, DOE will review each documented safety analysis as: (1) Part of the initial submittal; (2) when revisions are submitted as part of a positive USQ or major modification; (3) if DOE has reason to believe a portion of the safety basis to be inadequate, or; (4) if DOE has reason to believe a portion of the safety basis has substantially changed. DOE will review the DSA to determine whether the rigor and detail of the documented safety analysis are appropriate for the complexity and hazards expected at the nuclear facility. In particular, DOE will evaluate the documented safety analysis by considering the extent to which the documented safety analysis (1) satisfies the provisions of the methodology used to prepare the documented safety analysis and (2) adequately addresses the criteria set forth in 10 CFR 830.204(b). DOE will prepare a Safety Evaluation Report to document the results of its review of the documented safety analysis. A documented safety analysis must contain any conditions or changes required by DOE in the Safety Evaluation Report. Generally, DOE's review of the annual submittal may be limited to ensuring that the results of USQs have been adequately incorporated into the DSA. If additional changes are proposed by the contractor and included in the annual update that have not been previously approved by DOE or have not been evaluated as a part of the USQ process, DOE must review and approve these changes. DOE has the authority to review the safety basis at any time. 4. In most cases, the contract will provide the framework for specifying the methodology and schedule for developing a documented safety analysis. Table 1 sets forth acceptable methodologies for preparing a documented safety analysis. Table 1 ------------------------------------------------------------------------ The contractor responsible May prepare its document safety analysis for: by: ------------------------------------------------------------------------ (1) A DOE reactor............ Using the method in U.S. Nuclear Regulatory Commission Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, or successor document. (2) A DOE nonreactor nuclear Using the method in DOE-STD-3009, Change facility. Notice No. 1, January 2000, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, July 1994, or successor document. (3) A DOE nuclear facility Using the method in either: with a limited operational (1) DOE-STD-3009-, Change Notice No. 1, life. January 2000, or successor document, or (2) DOE-STD-3011-94, Guidance for Preparation of DOE 5480.22 (TSR) and DOE 5480.23 (SAR) Implementation Plans, November 1994, or successor document. (4) The deactivation or the Using the method in either: transition surveillance and (1) DOE-STD-3009, Change Notice No. 1, maintenance of a DOE nuclear January 2000, or successor document, or facility. (2) DOE-STD-3011-94 or successor document. (5) The decommissioning of a (1) Using the method in DOE-STD-1120-98, DOE nuclear facility. Integration of Environment, Safety, and Health into Facility Disposition Activities, May 1998, or successor document; (2) Using the provisions in 29 CFR 1910.120 (or 29 CFR 1926.65 for construction activities) for developing Safety and Health Programs, Work Plans, Health and Safety Plans, and Emergency Response Plans to address public safety, as well as worker safety; and (3) Deriving hazard controls based on the Safety and Health Programs, the Work Plans, the Health and Safety Plans, and the Emergency Response Plans. (6) A DOE environmental (1) Using the method in DOE-STD-1120-98 restoration activity that or successor document, and involves either work not (2) Using the provisions in 29 CFR done within a permanent 1910.120 (or 29 CFR 1926.65 for structure or the construction activities) for developing decommissioning of a a Safety and Health Program and a site- facility with only low-level specific Health and Safety Plan residual fixed radioactivity. (including elements for Emergency Response Plans, conduct of operations, training and qualifications, and maintenance management). (7) A DOE nuclear explosive Developing its documented safety analysis facility and the nuclear in two pieces: explosive operations (1) A Safety Analysis Report for the conducted therein.. nuclear facility that considers the generic nuclear explosive operations and is prepared in accordance with DOE-STD- 3009, Change Notice No. 1, January 2000, or successor document, and (2) A Hazard Analysis Report for the specific nuclear explosive operations prepared in accordance with DOE-STD-3016- 99, Hazards Analysis Reports for Nuclear Explosive Operations, February 1999, or successor document. (8) A DOE Hazard Category 3 Using the methods in Chapters 2, 3, 4, nonreactor nuclear facility. and 5 of DOE-STD-3009, Change Notice No. 1, January 2000, or successor document to ad- dress in a simplified fashion: (1) The basic description of the facility/ activity and its operations, including safety structures, systems, and components; (2) A qualitative hazards analysis; and (3) The hazard controls (consisting primarily of inventory limits and safety management programs) and their bases. (9) Transportation activities (1) Preparing a Safety Analysis Report for Packaging in accordance with DOE-O- 460.1A, Packaging and Transportation Safety, October 2, 1996, or successor document and (2) Preparing a Transportation Safety Document in accordance with DOE-G-460.1- 1, Implementation Guide for Use with DOE O 460.1A, Packaging and Transportation Safety, June 5, 1997, or successor document. (10) Transportation and (1) Preparing a Safety Analysis Report onsite transfer of nuclear for Packaging in accordance with DOE-O- explosives, nuclear 461.1, Packaging and Transportation of components, Navel nuclear Materials of National Security Interest, fuel elements, Category I September 29, 2000, or successor and Category II special document and nuclear materials, special (2) Preparing a Transportation Safety assemblies, and other Document in accordance with DOE-M-461.1- materials of national 1, Packaging and Transfer of Materials security. of National Security Interest Manual, September 29, 2000, or successor document. ------------------------------------------------------------------------ [[Page 38995]] 5. Table 1 refers to specific types of nuclear facilities. These references are not intended to constitute an exhaustive list of the specific types of nuclear facilities. Part 830 defines nuclear facility broadly to include reactor or a nonreactor nuclear facilities where an activity is conducted for or on behalf of DOE and includes any related area, structure, facility, or activity to the extent necessary to ensure proper implementation of the requirements established by this Part. The only exceptions are those facilities specifically excluded such as accelerators. Table 2 defines the terms referenced in Table 1 that are not defined in 10 CFR 830.3. Table 2 ------------------------------------------------------------------------ For purposes of Table 1: Means: ------------------------------------------------------------------------ (1) Deactivation............. The process of placing a facility in a stable and known condition, including the removal of hazardous and radioactive materials. (2) Decontamination.......... The removal or reduction of residual radioactive and hazardous materials by mechanical, chemical, or other techniques to achieve a stated objective or end condition. (3) Decommissioning.......... Those actions taking place after deactivation of a nuclear facility to retire it from service and includes surveillance and maintenance, decontamination, and/or dismantlement. (4) Environmental restoration The process by which contaminated sites activities. and facilities are identified and characterized and by which existing contamination is contained, or removed and disposed. (5) Generic nuclear explosive A characterization that considers the operation. collective attributes (such as special facility system requirements, physical weapon characteristics, or quantities and chemical/physical forms of hazardous materials) for all projected nuclear explosive operations to be conducted at a facility. (6) Nuclear explosive A nuclear facility at which nuclear facility. operations and activities involving a nuclear explosive may be conducted. (7) Nuclear explosive Any activity involving a nuclear operation. explosive, including activities in which main-charge, high-explosive parts and pits are collocated. (8) Nuclear facility with a A nuclear facility for which there is a limited operational life. short remaining operational period before ending the facility's mission and initiating deactivation and decommissioning and for which there are no intended additional missions other than cleanup. (9) Specific nuclear A specific nuclear explosive subjected to explosive operation. the stipulated steps of an individual operation, such as assembly or disassembly. (10) Transition surveillance Activities conducted when a facility is and maintenance activities. not operating or during deactivation, decontamination, and decommissioning operations when surveillance and maintenance are the predominant activities being conducted at the facility. These activities are necessary for satisfactory containment of hazardous materials and protection of workers, the public, and the environment. These activities include providing periodic inspections, maintenance of structures, systems, and components, and actions to prevent the alteration of hazardous materials to an unsafe state. ------------------------------------------------------------------------ 6. The contractor responsible for the design and construction of a new Hazard Category 1, 2, or 3 DOE nuclear facility or a major modification to an existing Hazard Category 1, 2, or 3 DOE nuclear facility must prepare a preliminary documented safety analysis. A preliminary documented safety analysis can ensure that substantial costs and time are not wasted in constructing a nuclear facility that will not be acceptable to DOE. If a contractor is required to prepare a preliminary documented safety analysis, the contractor must obtain DOE approval of the preliminary documented safety analysis prior to procuring materials or components or beginning construction. DOE, however, may authorize the contractor to perform limited procurement and construction activities without approval of a preliminary documented safety analysis if DOE determines that the activities are not detrimental to public health and safety and are in the best interests of DOE. DOE Order 420.1, or successor document, sets forth acceptable nuclear safety design criteria for use in preparing a preliminary documented safety analysis. As a general matter, DOE does not expect preliminary documented safety analyses to be needed for activities that do not involve significant construction such as environmental restoration activities, decontamination and decommissioning activities, specific nuclear explosive operations, or transition surveillance and maintenance activities. G. Hazard Controls 1. Hazard controls are measures to eliminate, limit, or mitigate hazards to workers, the public, or the environment. They include: (1) Physical, design, structural, and engineering features; (2) safety structures, systems, and components; (3) safety management programs; (4) technical safety requirements; and (5) other controls necessary to provide adequate protection from hazards. 2. The types and specific characteristics of the safety management programs necessary for a DOE nuclear facility will be dependent on the complexity and hazards associated with the nuclear facility and the work being performed. In most cases, however, a contractor should consider safety management programs covering topics such as quality assurance, procedures, maintenance, personnel training, conduct of operations, criticality safety, emergency preparedness, fire protection, waste management, and radiation protection. In general, DOE Orders set forth DOE's expectations concerning specific topics. For example, DOE Order 420.1, or successor document provides DOE's expectations with respect to fire protection and criticality safety. 3. Safety structures, systems, and components require formal definition of minimum acceptable performance in the documented safety analysis. This is accomplished by first defining a safety function, then describing the structure, systems, and components, placing functional requirements on those portions of the structures, systems, and components required for the safety function, and identifying performance criteria that will ensure functional requirements are met. Technical safety requirements are developed to ensure the operability of the safety structures, systems, and components and define actions to be taken if a safety structure, system, or component is not operable. 4. Technical safety requirements establish limits, controls, and related actions necessary for the safe operation of a nuclear facility. The exact form and contents of technical safety requirements will depend on the circumstances of a particular nuclear facility as defined in the documented safety analysis for the nuclear facility. As appropriate, technical safety requirements may have sections on: (1) Safety limits; (2) operating limits; (3) surveillance requirements; (4) administrative controls; (5) use and application; and (6) design features. It may also have an appendix on the bases for the limits and requirements. DOE Guide 423.1-1B, Implementation Guide for Use in Developing Technical Safety Requirements, or successor document, provides a complete description of what technical safety requirements should contain and how they should be developed and maintained. [[Page 38996]] 5. DOE will examine and approve the technical safety requirements as part of preparing the safety evaluation report and reviewing updates to the safety basis. As with all hazard controls, technical safety requirements must be kept current and reflect changes in the facility, the work and the hazards as they are analyzed in the documented safety analysis. In addition, DOE expects a contractor to maintain technical safety requirements, and other hazard controls as appropriate, as controlled documents with an authorized users list. 6. Table 3 sets forth DOE's expectations concerning acceptable technical safety requirements. Table 3 ------------------------------------------------------------------------ As appropriate for a particular DOE nuclear facility, the section of the Will provide information on: technical safety requirements on: ------------------------------------------------------------------------ (1) Safety limits............ The limits on process variables associated with those safety class physical barriers, generally passive, that are necessary for the intended facility function and that are required to guard against the uncontrolled release of radioactive materials. The safety limit section describes, as precisely as possible, the parameters being limited, states the limit in measurable units (pressure, temperature, flow, etc.), and indicates the applicability of the limit. The safety limit section also describes the actions to be taken in the event that the safety limit is exceeded. These actions should first place the facility in the safe, stable condition attainable, including total shutdown (except where such action might reduce the margin of safety) or should verify that the facility already is safe and stable and will remain so. The technical safety requirement should state that the contractor must obtain DOE authorization to restart the nuclear facility following a violation of a safety limit. The safety limit section also establishes the steps and time limits to correct the out-of- specification condition. (2) Operating limits......... Those limits which are required to ensure the safe operation of a nuclear facility. The operating limits section may include subsections on limiting control settings and limiting conditions for operation. (3) Limiting control settings The settings on safety systems that control process variables to prevent exceeding a safety limit. The limited control settings section normally contains the settings for automatic alarms and for the automatic or non- automatic initiation of protective actions related to those variables associated with the function of safety class structures, systems, or components if the safety analysis shows that they are relied upon to mitigate or prevent an accident. The limited control settings section also identifies the protective actions to be taken at the specific settings chosen in order to correct a situation automatically or manually such that the related safety limit is not exceeded. Protective actions may include maintaining the variables within the requirements and repairing the automatic device promptly or shutting down the affected part of the process and, if required, the entire facility. (4) Limiting conditions for The limits that represent the lowest operations. functional capability or performance level of safety structures, systems, and components required to perform an activity safely. The limiting conditions for operation section describes, as precisely as possible, the lowest functional capability or performance level of equipment required for continued safe operation of the facility. The limiting conditions for operation section also states the action to be taken to address a condition not meeting the limiting conditions for operation section. Normally this simply provides for the adverse condition being corrected in a certain time frame and for further action if this is impossible. (5) Surveillance requirements Requirements relating to test, calibration, or inspection to assure that the necessary operability and quality of safety structures, systems, and components is maintained; that facility operation is within safety limits; and that limiting control settings and limiting conditions for operation are met. If a required surveillance is not successfully completed, the contractor is expected to assume the systems or components involved are inoperable and take the actions defined by the technical safety requirement until the systems or components can be shown to be operable. If, however, a required surveillance is not performed within its required frequency, the contractor is allowed to perform the surveillance within 24 hours or the original frequency, whichever is smaller, and confirm operability. (6) Administrative controls.. Organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility consistent with the technical safety requirement. In general, the administrative controls section addresses (1) the requirements associated with administrative controls, (including those for reporting violations of the technical safety requirement); (2) the staffing requirements for facility positions important to safe conduct of the facility; and (3) the commitments to the safety management programs identified in the documented safety analysis as necessary components of the safety basis for the facility. (7) Use and application The basic instructions for applying the provisions. safety restrictions contained in a technical safety requirement. The use and application section includes definitions of terms, operating modes, logical connectors, completion times, and frequency notations. (8) Design features.......... Design features of the facility that, if altered or modified, would have a significant effect on safe operation. (9) Bases appendix........... The reasons for the safety limits, operating limits, and associated surveillance requirements in the technical safety requirements. The statements for each limit or requirement shows how the numeric value, the condition, or the surveillance fulfills the purpose derived from the safety documentation. The primary purpose for describing the basis of each limit or requirement is to ensure that any future changes to the limit or requirement is done with full knowledge of the original intent or purpose of the limit or requirement. ------------------------------------------------------------------------ [[Page 38997]] H. Unreviewed Safety Questions 1. The USQ process is an important tool to evaluate whether changes affect the safety basis. A contractor must use the USQ process to ensure that the safety basis for a DOE nuclear facility is not undermined by changes in the facility, the work performed, the associated hazards, or other factors that support the adequacy of the safety basis. 2. The USQ process permits a contractor to make physical and procedural changes to a nuclear facility and to conduct tests and experiments without prior approval, provided these changes do not cause a USQ. The USQ process provides a contractor with the flexibility needed to conduct day-to-day operations by requiring only those changes and tests with a potential to impact the safety basis (and therefore the safety of the nuclear facility) be approved by DOE. This allows DOE to focus its review on those changes significant to safety. The USQ process helps keep the safety basis current by ensuring appropriate review of and response to situations that might adversely affect the safety basis. 3. DOE Guide 424.1-1B Chg 2, Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements, or successor document provides DOE's expectations for a USQ process. The contractor must obtain DOE approval of its procedure used to implement the USQ process. The contractor is allowed to make editorial and format changes to its USQ procedure while maintaining DOE approval. I. Functions and Responsibilities 1. The DOE Management Official for a DOE nuclear facility (that is, the Assistant Secretary, the Assistant Administrator, or the Office Director who is primarily responsible for the management of the facility) has primary responsibility within DOE for ensuring that the safety basis for the facility is adequate and complies with the safety basis requirements of Part 830. The DOE Management Official is responsible for ensuring the timely and proper (1) review of all safety basis documents submitted to DOE and (2) preparation of a safety evaluation report concerning the safety basis for a facility. 2. DOE will maintain a public list on the internet that provides the status of the safety basis for each Hazard Category 1, 2, or 3 DOE nuclear facility and, to the extent practicable, provides information on how to obtain a copy of the safety basis and related documents for a facility. [FR Doc. 2018-16863 Filed 8-7-18; 8:45 am] BILLING CODE 6450-01-P
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Proposed Rules | |
| Action | Notice of proposed rulemaking and notice of public meetings. | |
| Dates | Public comment on this proposed rule will be accepted until October 9, 2018. For dates and more information on the public meetings for this proposed rulemaking, see SUPPLEMENTARY INFORMATION. | |
| Contact | Mr. Garrett Smith, U.S. Department of Energy, Office of Nuclear Safety, AU-30, 1000 Independence Avenue SW, Washington, DC 20585; (301) 903-2996 or [email protected] | |
| FR Citation | 83 FR 38982 | |
| RIN Number | 1992-AA57 | |
| CFR Associated | Administrative Practice and Procedure; Doe Contracts; Environment; Federal Buildings and Facilities; Government Contracts; Nuclear Materials; Nuclear Power Plants and Reactors; Nuclear Safety; Penalties; Public Health; Reporting and Recordkeeping Requirements and Safety |