Environmental Impacts of Severe Reactor and Spent Fuel Pool Accidents, 48235-48242 [2015-19843]

Download as PDF 48235 Rules and Regulations Federal Register Vol. 80, No. 155 Wednesday, August 12, 2015 This section of the FEDERAL REGISTER contains regulatory documents having general applicability and legal effect, most of which are keyed to and codified in the Code of Federal Regulations, which is published under 50 titles pursuant to 44 U.S.C. 1510. The Code of Federal Regulations is sold by the Superintendent of Documents. Prices of new books are listed in the first FEDERAL REGISTER issue of each week. NUCLEAR REGULATORY COMMISSION 10 CFR Part 51 [Docket Nos. PRM–51–14, et al.; NRC–2011– 0189] Environmental Impacts of Severe Reactor and Spent Fuel Pool Accidents Nuclear Regulatory Commission. ACTION: Petition for rulemaking; denial. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is denying 15 petitions for rulemaking submitted by the petitioners identified in the table in Section IV, ‘‘Availability of Documents.’’ The petitioners requested that the NRC rescind its regulations that ‘‘reach generic conclusions about the environmental impacts of severe reactor and/or spent fuel pool accidents and therefore prohibit considerations of those impacts in reactor licensing proceedings.’’ SUMMARY: The dockets for petitions for rulemaking (PRM) PRM–51–14, PRM– 51–15, PRM–51–16, PRM–51–17, PRM– 51–18, PRM–51–19, PRM–51–20, PRM– 51–21, PRM–51–22, PRM–51–23, PRM– 51–24, PRM–51–25, PRM–51–26, PRM– 51–27, and PRM–51–28 are closed on August 12, 2015. ADDRESSES: Please refer to Docket ID NRC–2011–0189 when contacting the NRC about the availability of information for any of these petitions. You may obtain publicly-available information related to this action by any of the following methods: • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2011–0189. Address questions about NRC dockets to Carol Gallagher, telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER mstockstill on DSK4VPTVN1PROD with RULES DATES: VerDate Sep<11>2014 18:35 Aug 11, 2015 Jkt 235001 section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301–415–4737, or by email to PDR.resource@nrc.gov. For the convenience of the reader, instructions about obtaining information regarding the 15 petitions and other materials referenced in this document are provided in the ‘‘Availability of Documents’’ section. • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. FOR FURTHER INFORMATION CONTACT: Jennifer Tobin, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415– 2328; email: Jennifer.Tobin@nrc.gov. SUPPLEMENTARY INFORMATION: INFORMATION CONTACT Table of Contents I. Background II. Environmental Impacts of Severe Reactor Accidents and Spent Fuel Pool Accidents III. Determination of Petitions IV. Availability of Documents I. Background The 15 petitions were filed in August 2011 in response to the publication of the NRC’s Near-Term Task Force (NTTF) report, ‘‘Recommendations for Enhancing Reactor Safety in the 21st Century, NTTF Review of Insights from the Fukushima Dai-ichi Accident,’’ dated July 12, 2011. The NTTF report provided the NRC staff’s recommendations to enhance U.S. nuclear power plant safety following the March 11, 2011, Fukushima accident in Japan. Based upon their interpretation of the NTTF report, the petitioners requested that the NRC rescind all regulations in part 51 of Title 10 of the Code of Federal Regulations (10 CFR) ‘‘to the extent that they reach generic conclusions about the environmental PO 00000 Frm 00001 Fmt 4700 Sfmt 4700 impacts of severe reactor and/or spent fuel pool accidents and therefore prohibit considerations of those impacts in reactor licensing proceedings.’’ 1 The NRC’s regulations in 10 CFR part 51 implement Section 102(2) of the National Environmental Policy Act of 1969, as amended (NEPA).2 The petitioners challenged the regulations that make generic environmental findings for license renewal proceedings regarding the environmental impacts of severe reactor accidents and spent fuel storage. The NTTF report, the 15 petitions, along with their NRC assigned docket numbers, and other pertinent documents are listed in Section IV, ‘‘Availability of Documents,’’ of this document. The NRC published a notice of receipt of the petitions in the Federal Register (FR) on November 10, 2011 (76 FR 70067).3 As explained in the November 10, 2011, notice, the Commission stated that it was: reviewing the [NTTF report], including the issues presented in the 15 petitions for rulemaking. The petitioners specifically cite the [NTTF report] as rationale for the PRMs [petitions for rulemaking]. The NRC will consider the issues raised by these PRMs through the process the Commission has established for addressing the recommendations from the [NTTF report] and is not providing a separate opportunity for public comment on the PRMs at this time.4 As such, the NRC staff placed the 15 petitions into abeyance pending the outcome of deliberations regarding the recommendations from the NTTF report. Although activities related to the NTTF report are ongoing, the NRC staff determined that sufficient information is now available to address the 15 petitions. A. Nuclear Power Plant License Renewal Actions and Table B–1 Under NEPA, the NRC must consider the environmental impacts of a major 1 See, e.g., San Luis Obispo Mothers for Peace Petition for Rulemaking, PRM–51–15 at 2 (August 11, 2011). All of the petitions have the same, or essentially the same, request for rulemaking. 2 10 CFR 51.1(a). 3 The petitioners also requested a suspension of ongoing reactor licensing proceedings. In its notice of the petitions’ receipt, the Commission referenced its September 9, 2011, decision, CLI–11–05, denying the petitioners’ suspension requests. 76 FR at 70068 citing Union Electric Company d/b/a Ameren Missouri (Callaway Plant, Unit 2), et al., CLI–11–05, 74 NRC 141, 173–76 (2011). 4 76 FR 70069. E:\FR\FM\12AUR1.SGM 12AUR1 48236 Federal Register / Vol. 80, No. 155 / Wednesday, August 12, 2015 / Rules and Regulations Federal action in an Environmental Impact Statement.5 The Commission has determined that power plant license renewal is a major Federal action that requires an Environmental Impact Statement.6 On many environmental issues related to license renewal, the Commission ‘‘found that it could draw generic conclusions applicable to all existing nuclear power plants, or to a specific subgroup of plants.’’ 7 Therefore, in accordance with 10 CFR 51.95(c), for nuclear power plant license renewal actions, the NRC relies upon NUREG–1437, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants’’ (GEIS). This environmental impact statement was initially published in May 1996 (1996 GEIS) and then revised and updated in June 2013 (2013 GEIS).8 The GEIS describes the potential environmental impacts of renewing the operating license of a nuclear power plant for an additional 20 years. The NRC classifies the environmental impacts of license renewal as either generic or sitespecific. Generic issues (i.e., environmental impacts common to all nuclear power plants) are addressed in the GEIS. Site-specific issues are addressed initially by the license renewal applicant (i.e., a nuclear power plant licensee seeking a renewal of its operating license under the NRC’s license renewal regulations in 10 CFR part 54), in its environmental report, which is required by 10 CFR 51.45, and then by the NRC in the supplemental environmental impact statement (SEIS) to the GEIS prepared for each license renewal application. The criteria for a license renewal applicant’s environmental report are set forth in 10 CFR 51.53(c). Under the NRC’s current regulatory framework in 10 CFR part 51 for evaluating the potential environmental impacts of renewing a nuclear power reactor’s operating license for an additional 20 years, neither the applicant’s environmental report nor the NRC’s SEIS are required to address 5 42 U.S.C. 4332(c). CFR 51.2(b)(2). 7 Florida Power & Light Co. (Turkey Point Nuclear Generating Plant, Units 3 and 4), CLI–01–17, 54 NRC 3,11 (2001). 8 The NRC regulation, 10 CFR 51.95(c), requires, for the consideration of potential environmental impacts of renewing a nuclear power plant’s operating license under 10 CFR part 54, that the NRC prepare an environmental impact statement, which is a supplement to the Commission’s NUREG–1437, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ issued in June 2013. At the time the petitions were filed in 2011, 10 CFR 51.95(c) referred to the initial 1996 GEIS. The NRC published a notice of issuance for the updated 2013 GEIS on June 20, 2013 (78 FR 37325). mstockstill on DSK4VPTVN1PROD with RULES 6 10 VerDate Sep<11>2014 18:35 Aug 11, 2015 Jkt 235001 issues previously determined to be generic, as addressed in the GEIS, absent new and significant information. The findings of the GEIS are codified in Table B–1 in appendix B to subpart A of 10 CFR part 51 (Table B–1).9 In Table B–1, generic issues are designated as ‘‘Category 1’’ issues and site-specific issues are designated as ‘‘Category 2’’ issues. All of the NRC regulations cited by the petitioners pertain, either directly or indirectly, to generic findings in the GEIS that are, in turn, codified in Table B–1. The petitioners object to those Table B–1 findings that make generic conclusions with respect to the potential environmental impacts of severe reactor and spent fuel pool accidents, namely, the findings for ‘‘Severe accidents’’ and ‘‘Onsite storage of spent nuclear fuel.’’ 10 The NRC defines ‘‘severe reactor accidents’’ as ‘‘those that could result in substantial damage to the reactor core, whether or not there are serious off-site consequences.’’ 11 In accordance with 10 CFR 2.335(a),12 NRC rules and regulations, such as Table B–1, generally cannot be challenged in NRC adjudicatory proceedings, including site-specific license renewal proceedings for a nuclear power plant before the NRC’s Atomic Safety and Licensing Board. Therefore, the petitioners request the rescission of the generic findings in Table B–1 so that they can challenge the NRC environmental impact findings now included in Table B–1 in future license renewal proceedings. In Table B–1, the ‘‘Severe accidents’’ issue has been classified as a Category 2, or site-specific, issue with an impact level finding of ‘‘small.’’ 13 Although not classified as a generic issue, the Table B–1 ‘‘Severe accidents’’ finding states that: 9 Table B–1 was amended to reflect the June 2013 GEIS update. The NRC rule amending Table B–1 and other 10 CFR part 51 regulations was published in the Federal Register on June 20, 2013 (78 FR 37282). 10 The petitions were filed in August 2011, before the June 2013 final rule that revised Table B–1 and other provisions of 10 CFR part 51 was published. The 2013 amendments to the Table B–1, ‘‘Severe accidents’’ finding, however, were of a minor, editorial nature (consisting of no more than deleting a regulatory reference). Otherwise, the language of Table B–1, ‘‘Severe accidents’’ finding is the same as the language that was in effect when the petitions were filed in 2011. 11 NUREG–1437, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ Vol.1, Chapter 1 at 1–27 (2013). 12 The NRC regulation, 10 CFR 2.335(a) states, in pertinent part, that ‘‘no rule or regulation of the Commission, or any provision thereof, concerning the licensing of production and utilization facilities, source material, special nuclear material, or byproduct material, is subject to attack by way of discovery, proof, argument, or other means in any adjudicatory proceeding subject to this [10 CFR part 2].’’ Paragraphs 2.335(b)–(d) provide exceptions to the provision in 10 CFR 2.335(a). 13 For most Table B–1 NEPA issues, the NRC determined whether the impacts of license renewal would have a small, moderate, or large environmental impact. The statement of considerations for the June 20, 2013, rulemaking stated that ‘‘[a] small impact means that the environmental effects are not detectable, or are so minor that they would neither destabilize nor noticeably alter any important attribute of the resource. A moderate impact means that the environmental effects are sufficient to alter noticeably, but not destabilize, important attributes of the resource. A large impact means that the environmental effects would be clearly noticeable and would be sufficient to destabilize important attributes of the resource’’ (78 FR 37285). 14 10 CFR part 51, subpart A, appendix B, Table B–1, ‘‘Severe accidents’’ finding (emphasis added). 15 Entergy Nuclear Generating Co. and Entergy Nuclear Operations, Inc. (Pilgrim Nuclear Power Station), CLI–12–15, 75 NRC 704, 709 (2012). 16 10 CFR part 51, subpart A, app. B, Table B–1, ‘‘Onsite storage of spent nuclear fuel’’ finding. Spent fuel is initially stored in spent fuel pools. Following a sufficient period of time to allow the spent fuel to cool, spent fuel may be removed from the pool and placed in large casks on the licensee controlled site (‘‘dry’’ storage). PO 00000 Frm 00002 Fmt 4700 Sfmt 4700 [t]he probability-weighted consequences of atmospheric releases, fallout onto open bodies of water, releases to groundwater, and societal and economic impacts from severe accidents are small for all plants. However, alternatives to mitigate severe accidents must be considered for all plants that have not considered such alternatives.14 The Commission has clarified that despite the Category 2 label, the severeaccidents-impact finding in Table B–1 equates to a generic environmental issue resolved by rule.15 The Table B–1 ‘‘Onsite storage of spent nuclear fuel’’ issue has been classified as a Category 1, or generic, issue also with an impact level finding of ‘‘small’’ since Table B–1’s inception in 1996. The ‘‘Onsite storage of spent nuclear fuel’’ finding states that: The expected increase in the volume of spent fuel from an additional 20 years of operation can be safely accommodated onsite during the license renewal term with small environmental effects through dry or pool storage at all plants. For the period after the licensed life for reactor operations, the impacts of onsite storage of spent nuclear fuel during the continued storage period are discussed in NUREG–2157 and as stated in § 51.23(b), shall be deemed incorporated into this issue.16 The 2013 amendments to the Table B–1 ‘‘Onsite storage of spent nuclear fuel’’ finding were made to comport with the U.S. Court of Appeals decision in New York v. NRC, 681 F.3d 471 (D.C. Cir. 2012), which vacated the NRC’s 2010 final rule that updated the NRC’s ‘‘waste confidence’’ decision and rule E:\FR\FM\12AUR1.SGM 12AUR1 Federal Register / Vol. 80, No. 155 / Wednesday, August 12, 2015 / Rules and Regulations mstockstill on DSK4VPTVN1PROD with RULES (75 FR 81032, 81037; December 23, 2010). On September 19, 2014, the NRC issued the final ‘‘continued storage’’ rule 17 (formerly known as the waste confidence rule), which addressed the New York vs. NRC decision. B. NTTF Report Following the March 11, 2011, Fukushima Dai-ichi accident, the Commission directed the NRC staff to establish a task force to conduct a methodical and systematic review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction.18 The NRC staff formed the NTTF, which submitted the NTTF report to the Commission in SECY–11–0093, ‘‘Near-Term Report and Recommendations for Agency Actions Following the Events in Japan,’’ dated July 12, 2011. The 15 petitions were filed in August 2011. The NTTF report provided various NRC staff recommendations to the Commission concerning the enhancement of reactor safety and a general implementation strategy, which included several proposals for new regulatory requirements. Recognizing that rulemaking and subsequent implementation would take several years to accomplish, the NTTF also recommended interim actions necessary to enhance reactor protection, severe reactor accident mitigation, and emergency preparedness while rulemaking activities were conducted.19 In addition, the NTTF report concluded that a sequence of events like the Fukushima accident is unlikely to occur in the United States and therefore, ongoing power reactor operations and related licensing activities do not pose an imminent risk to public health and safety. The NRC staff further refined the NTTF recommendations in SECY–11– 0124, ‘‘Recommended Actions to be Taken Without Delay from the NearTerm Task Force Report,’’ and SECY– 11–0137, ‘‘Prioritization of Recommended Actions to be Taken in Response to Fukushima Lessons Learned,’’ both of which described the NRC staff’s recommendations for enhancing reactor safety and the priority for implementing those recommendations. Based on those recommendations, the NRC has issued 17 79 FR 56238. Memorandum—COMGBJ–11–0002— NRC Actions Following the Events in Japan, March 21, 2011. 19 http://www.nrc.gov/reactors/operating/opsexperience/japan-dashboard.html. 18 Tasking VerDate Sep<11>2014 18:35 Aug 11, 2015 Jkt 235001 orders and initiated rulemaking activities to enhance the safety of reactors as a result of lessons learned from the Fukushima Dai-ichi accident. The petitioners contend that the recommendations of the NTTF report provide the justification for their request that the NRC rescind regulations in 10 CFR part 51 to the extent that they reach generic conclusions with respect to potential environmental impacts of severe reactor and spent fuel pool accidents and that preclude consideration of those conclusions in individual license renewal proceedings. Specifically, the petitions request that the NRC amend the following regulations: 10 CFR 51.45, 10 CFR 51.53, 10 CFR 51.95, and Table B–1. C. Other NRC Regulations Identified by the Petitioners The NRC regulation, 10 CFR 51.45, sets forth the general requirements for an environmental report, which the NRC defines as a document submitted to the Commission by an applicant for a permit, license, or other form of permission, or an amendment to or renewal of a permit, license or other form of permission, in order to aid the Commission in complying with Section 102(2) of NEPA.20 Paragraph 51.45(b) requires that the environmental report contain a description of the proposed action, a statement of its purposes, and a description of the environment affected. Section 51.45 also contains a list of items that the environmental report should discuss, such as the impact of the proposed action on the environment, any adverse effects that cannot be avoided if the proposed action were to be implemented, and alternatives to the proposed action.21 The NRC regulation, 10 CFR 51.53(c), describes the applicant’s preparation of an environmental report for the renewal of a nuclear power plant’s operating license. Paragraph 51.53(c)(3)(i) states that the environmental report is not required to include analyses of the potential environmental impacts identified as Category 1 issues in Table B–1. Paragraphs (c)(3)(ii)(A)–(P) of 10 CFR 51.53, describe the requirement to conduct environmental impact analyses for those Category 2 issues in Table B– 1 that must be addressed on a sitespecific basis by the license renewal applicant in its environmental report. In addition, paragraph 51.53(c)(3)(iv), requires the environmental report to include any new and significant information regarding the 20 10 CFR 51.14(a) (definition of ‘‘environmental report’’). 21 10 CFR 51.45(b)(1)–(5). PO 00000 Frm 00003 Fmt 4700 Sfmt 4700 48237 environmental impacts of license renewal of which the applicant is aware. The NRC regulation, 10 CFR 51.95, describes the preparation of a postconstruction environmental impact statement by the NRC, such as at the license renewal stage. Both 10 CFR 51.53 and 10 CFR 51.95 were among the regulations amended by the NRC to reflect the June 2013 update to the GEIS.22 D. Several Petitions Concern Actions Outside of License Renewal Several of the petitions were filed in relation to new reactor licensing proceedings, as opposed to proceedings concerning the renewal of an existing nuclear power plant’s operating license. The petitions filed for combined license (COL) actions are: PRM–51–14, –51–17, –51–18, –51–21, –51–23, –51–24, –51– 25, –51–27, and –51–28; PRM–51–16 was filed for an operating license (OL) action. The generic findings to which the petitioners object concern only license renewal actions conducted pursuant to 10 CFR part 54. Specifically, the NRC’s 10 CFR part 51 regulations that reach generic conclusions regarding severe accident or spent fuel storage issues in Table B–1 do not apply to new reactor applications made under the provisions of 10 CFR part 52 for either an early site permit (ESP) or a COL, or to a construction permit (CP) or OL application (e.g., the Watts Bar 2 application) made under the provisions of 10 CFR part 50. The NRC makes no generic conclusions about severe reactor and spent fuel pool accidents when preparing environmental impacts statements for ESP, COL, CP, or OL applications. For these types of applications, the NRC performs a sitespecific environmental review to address the potential environmental impacts. II. Environmental Impacts of Severe Reactor Accidents and Spent Fuel Pool Accidents A. Overview The petitioners assert that the lessons learned from the Fukushima Dai-ichi event, as documented in the recommendations of the NTTF report, provide ‘‘new and significant’’ information that would affect the NRC’s analysis of severe reactor and spent fuel pool accidents when considering whether to renew a nuclear power plant’s operating license for an additional 20 years in accordance with the NRC’s regulations in 10 CFR part 54, 22 The NRC rule amending these regulations was published in the Federal Register on June 20, 2013 (78 FR 37282). E:\FR\FM\12AUR1.SGM 12AUR1 48238 Federal Register / Vol. 80, No. 155 / Wednesday, August 12, 2015 / Rules and Regulations ‘‘Requirements for Renewal of Operating Licenses for Nuclear Power Plants.’’ It is upon this basis that the petitioners request that the NRC rescind all regulations in 10 CFR part 51 that ‘‘reach generic conclusions about the environmental impacts of severe reactor and/or spent fuel pool accidents and therefore prohibit considerations of those impacts in reactor licensing proceedings.’’ 23 Under NEPA case law, the standard for considering whether information is ‘‘new and significant’’ is that it must present ‘‘a seriously different picture of the environmental impact of the proposed project from what was previously envisioned.’’ 24 If the information is ‘‘new and significant,’’ and if the agency has not yet taken the proposed action, then the agency is required to supplement its environmental impact statement.25 The NRC has determined that the NTTF report recommendations do not constitute ‘‘new and significant’’ information. The NTTF report recommendations do not challenge the generic determinations in Table B–1. The NTTF report did not explicitly consider the complex analysis underlying the determinations in Table B–1, did not recommend changing the generic determinations in Table B–1 regarding severe reactor and spent fuel pool accidents, and did not make any recommendations relating to nuclear power plant license renewals. Any NRC regulatory action that has been taken or could have been taken as a result of the mstockstill on DSK4VPTVN1PROD with RULES 23 See, e.g., San Luis Obispo Mothers for Peace Petition for Rulemaking, PRM–51–15 at 1 (August 11, 2011). All of the petitions have the same, or essentially the same, request for rulemaking. 24 Union Electric Company d/b/a Ameren Missouri (Callaway Plant, Unit 2), et al, CLI–11–05, 74 NRC 141, 167–68 (2011) quoting Hydro Resources, Inc., CLI–99–22, 50 NRC 3, 14 (1999) (‘‘To merit this additional review, information must be both ‘new’ and ‘significant,’ and it must bear on the proposed action or its impacts. As we have explained, ‘[t]he new information must present ‘a seriously different picture of the environmental impact of the proposed project from what was previously envisioned’ ’’) (alteration in the original.); Sierra Club v. Froehlke, 816 F.2d 205, 210 (5th Cir. 1987) (‘‘In making its determination whether to supplement an existing EIS because of new information, the [United States Army, Corps of Engineers] should consider ‘the extent to which the new information presents a picture of the likely environmental consequences associated with the proposed action not envisioned by the original EIS’.’’) (alteration added); Wisconsin v. Weinberger, 745 F.2d 412, 418 (7th Cir.1984) (supplementation required where new information ‘‘provides a seriously different picture of the environmental landscape.’’); and see NRC Regulatory Guide 4.2, Supplement 1, Revision 1, ‘‘Preparation of Supplemental Environmental Reports for Applications to Renew Nuclear Power Plant Operating Licenses,’’ Chapter 5 (June 2013). 25 10 CFR 51.92(a). VerDate Sep<11>2014 18:35 Aug 11, 2015 Jkt 235001 information presented in the NTTF report would not have been deferred to the license renewal stage; any such action would have been taken as part of the NRC’s ongoing safety program. B. Severe Reactor Accidents First, the petitioners requested that the NRC rescind all of its regulations that reach generic conclusions about the environmental impacts of severe reactor accidents. As set forth in both Table B– 1 and 10 CFR 51.53(c)(3)(ii)(L), ‘‘Severe accidents’’ is listed as a Category 2 or site-specific issue, rather than a generic issue because the Commission determined the agency should consider severe accident mitigation measures on a site-specific basis for those reactors for which the agency had not previously performed a similar analysis. However, as noted above, the Commission has confirmed that because the agency made a generic determination regarding severe accident impacts in the GEIS that is codified in Table B–1, the impacts portion of the issue has been resolved by rule.26 GEIS Severe Accident Analysis When the NRC promulgated the license renewal rule and the severe accidents finding in Table B–1 in 1996, the NRC conducted a detailed analysis in the GEIS to determine that the probability weighted environmental impacts of severe accidents are small. The Commission summarized this analysis in the associated Federal Register notice. The GEIS provides an analysis of the consequences of severe accidents for each site in the country. The analysis adopts standard assumptions about each site for parameters such as evacuation speeds and distances traveled, and uses site-specific estimates for parameters such as population distribution and meteorological conditions. These latter two factors were used to evaluate the exposure indices for these analyses. The methods used result in predictions of risk that are adequate to illustrate the general magnitude and types of risks that may occur from reactor accidents. Regarding siteevacuation risk, the radiological risk to persons as they evacuate is taken into account within the individual plant risk assessments that form the basis for the GEIS. In addition, 10 CFR part 50 requires that licensees maintain up-to-date emergency plans. This requirement will apply in the license renewal term as well as in the current licensing term. As was done in the GEIS analysis, the use of generic source terms (one set for PWRs and another for BWRs) is consistent with the past practice that has been used and accepted by the NRC for individual plant Final 26 Florida Power & Light Co. (Turkey Point Nuclear Generating Plant, Units 3 and 4), CLI–01– 17, 54 NRC 3,11 (2001). PO 00000 Frm 00004 Fmt 4700 Sfmt 4700 Environmental Impact Statements (FEISs). The purpose of the source term discussion in the GEIS is to describe whether or not new information on source terms developed after the completion of the most recent FEISs indicates that the source terms used in the past under-predict environmental consequences. The NRC has concluded that analysis of the new source term information developed over the past 10 years indicates that the expected frequency and amounts of radioactive release under severe accident conditions are less than that predicted using the generic source terms. A summary of the evolution of this research is provided in NUREG–1150, ‘‘Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants’’ (December 1990), and its supporting documentation. Thus, the analyses performed for the GEIS represent adequate, plant-specific estimates of the impacts from severe accidents that would generally overpredict, rather than under-predict, environmental consequences. Therefore, the GEIS analysis of the impacts of severe accidents for license renewal is retained and is considered applicable to all plants.27 In preparing the 2013 GEIS, the NRC staff specifically considered and evaluated severe reactor accidents and found that the conclusions reached in the 1996 GEIS remained valid. Specifically, the NRC staff considered areas where new information showed increases in the consequences of severe accidents and compared them to areas where the new information showed decreases in the impacts from severe accidents.28 The NRC staff found that information showed that the areas that reflected an increase in impacts could potentially account for a 470 percent increase.29 But, the NRC staff found that the areas that reflected a decrease in impacts could account for a 500 percent to 10,000 percent reduction.30 The petitions for rulemaking and supporting affidavit do not challenge with any specificity the analyses underlying the 1996 GEIS. The NTTF report, upon which the petitioners’ rely, largely described the accident sequence at Fukushima, considered the NRC’s current regulatory framework, and recommended areas for improvement. Indeed, the NTTF report concluded that a sequence of events like the Fukushima accident is unlikely to occur in the United States and, therefore, ongoing power reactor operations and related licensing activities do not pose an imminent risk to public health and safety. As a result, on their face, the 27 61 FR 28467, 28480. See also NUREG–1437, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ Vol. 1, Chapter 5 at 5–1 to 5–116 (1996). 28 NUREG–1437, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ Vol. 1, Rev. 1, appendix E at E–46 to E–47 (2013). 29 Id. 30 Id. E:\FR\FM\12AUR1.SGM 12AUR1 Federal Register / Vol. 80, No. 155 / Wednesday, August 12, 2015 / Rules and Regulations safety conclusions in the NTTF report do not appear to relate to the environmental analysis challenged by the petitioners. Moreover, the petitioners have not demonstrated that any information in the NTTF report undermines the environmental analysis in the GEIS. For example, the petitioners have not shown, or even alleged, that the source terms relied on by the NRC staff were inadequate, that the analysis ignored or marginalized an exposure pathway, or that the NRC’s consideration of evacuation times was unreasonable. Moreover, the petitioners do not suggest that any errors in the severe accident analysis underlying the Table B–1 findings were significant enough to overcome the substantial margins noted by the Commission in 1996 and confirmed by the NRC staff in the 2013 update, let alone provide a ‘‘seriously different picture’’ of the likelihood and consequences of a severe accident beyond that already considered. Therefore, the findings of the NTTF report do not indicate that the NRC should revise the 2013 GEIS, or present a seriously different picture of the environmental consequences of severe accidents beyond those already considered by the agency. Petitioners’ Focus on License Renewal Regulations mstockstill on DSK4VPTVN1PROD with RULES The petitioners largely focus their arguments on a claim that currently operating reactors will need to undertake expensive improvements to comply with the NRC’s post-Fukushima requirements and that the agency’s environmental review must account for these costs. But these arguments reflect a misunderstanding of our regulatory process. As stated in the 2013 GEIS: As of the publication date of [the 2013] GEIS, the NRC’s evaluation of the consequences of the Fukushima events is ongoing. As such, the NRC will continue to evaluate the need to make improvements to existing regulatory requirements based on the task force report and additional studies and analyses of the Fukushima events as more information is learned. To the extent that any revisions are made to NRC regulatory requirements, they would be made applicable to nuclear power reactors regardless of whether or not they have a renewed license. Therefore, no additional analyses have been performed in this GEIS as a result of the Fukushima events. In the event that the NRC identifies information from the Fukushima events that constitutes new and significant information with respect to the environmental impacts of license renewal, the NRC will discuss that information in its site-specific supplemental EISs (SEISs) to the VerDate Sep<11>2014 18:35 Aug 11, 2015 Jkt 235001 GEIS, as it does with all such new and significant information.31 As that paragraph from the 2013 GEIS explains, if the NRC finds that an additional requirement should be imposed upon a reactor licensee the NRC will impose that requirement regardless of its license renewal posture. The renewal of a nuclear power plant’s operating license does not, in any way, prescribe the NRC’s ongoing safety surveillance of that plant. The regulations that the petitioners want rescinded pertain only to license renewal findings, not the NRC’s ongoing safety surveillance. The NRC continues to address severe accident-related issues in the day to day regulatory oversight of nuclear power plant licensees. The NRC’s regulatory efforts have reduced severe accident risks beyond what was considered in the 1996 and 2013 GEIS. In some cases, such as the NRC’s response to the accident at Fukushima Dai-ichi, these regulatory activities are ongoing. The NRC will continue to evaluate the need to make improvements to existing regulatory requirements as more information is learned. C. Spent Fuel Pool Accidents Last, the petitioners contend that the NTTF report provides new and significant information that warrants rescinding the NRC’s regulations codifying the GEIS’ generic environmental determinations of the impacts of onsite storage of spent nuclear fuel during the period of license renewal. The evaluation of the environmental impacts of the onsite storage of spent nuclear fuel during the license renewal term, including potential spent fuel pool accidents, was documented in the 1996 GEIS and reaffirmed in the 2013 GEIS. The NRC found that the probability of a fuel cladding fire is low even in the event of a ‘‘worst probable cause of a loss of spent-fuel pool coolant (a severe seismic-generated accident causing a catastrophic failure of the pool).’’ 32 Based on these evaluations, the ‘‘Onsite storage of spent nuclear fuel’’ NEPA issue in Table B–1 has been classified as a Category 1, or generic, issue with an impact level finding of ‘‘small.’’ As noted above, the NTTF report primarily focused on describing the Fukushima accident, analyzing the agency’s current 31 NUREG–1437, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ Vol. 1, Rev. 1, Chapter 1, Section 1.9. at 1–33 and 1–34 (2013) (citations omitted) (emphasis added). 32 See also NUREG–1437, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ Vol. 1, Chapter 6 at 6– 72 to 6–75 (1996). PO 00000 Frm 00005 Fmt 4700 Sfmt 4700 48239 regulatory structure, and making recommendations for improving the agency’s regulatory process. The NTTF report did not specifically address the agency’s environmental analysis for onsite spent fuel storage or the agency’s prior studies showing that the risk of an accident in a spent fuel pool would be small. Moreover, the petitioners have not provided any specific explanation of how information in the NTTF report would invalidate the findings in the GEIS and thereby call into question the regulations in 10 CFR part 51. Moreover, the NRC has thoroughly considered the question of spent fuel pool accidents before and after promulgating the 1996 GEIS, and these studies have consistently found that the probability of a spent fuel pool fire is low. Spent fuel pools are large, robust structures that contain thousands of gallons of water. Spent fuel pools have thick, reinforced, concrete walls and floors lined with welded, stainless-steel plates. After removal from the reactor, spent fuel assemblies are placed into these pools and stored under at least 20 feet of water, which provides adequate shielding from radiation. Redundant monitoring, cooling, and make-up water systems are part of the spent fuel pool system. Spent fuel pools at operating U.S. nuclear power plants were designed and licensed to maintain a large inventory of water to protect and cool spent fuel under normal and accident conditions, including earthquakes. Domestic and international operational experience and past NRC studies (e.g., NUREG–1353, NUREG– 1738, and SECY–13–0112) 33 have borne out that spent fuel pools are effectively designed to prevent accidents that could affect the safe storage of spent fuel. Regarding spent fuel pool accidents, the petitioners’ primary concern is a ‘‘seismically induced’’ spent fuel pool fire (i.e., an earthquake damaging the structure of the spent fuel pool and thereby causing a complete or partial drainage of the pool’s water.) 34 With 33 These studies include NUREG–1353, ‘‘Regulatory Analysis for the Resolution of Generic Issue 82, ‘Beyond Design Basis Accidents in Spent Fuel Pools’ ’’ (April 1989); NUREG–1738, ‘‘Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants’’ (February 2001); and SECY–13–0112, ‘‘Consequence Study of a Beyond-Design-Basis Earthquake Affecting the Spent Fuel Pool for a U.S. Mark I Boiling-Water Reactor’’ (October 2013). 34 Potential spent fuel pool fires caused by a successful terrorist strike were the subject of rulemaking petitions filed in 2006 (PRM–51–10) and 2007 (PRM–51–12). These petitions also requested the rescission of the generic finding in Table B–1 concerning onsite spent fuel storage. The NRC denied these petitions in 2008 (73 FR 46204; August 8, 2008). In its denial notice, the NRC E:\FR\FM\12AUR1.SGM Continued 12AUR1 48240 Federal Register / Vol. 80, No. 155 / Wednesday, August 12, 2015 / Rules and Regulations respect to the March 2011 Fukushima accident, a Japanese government report, issued in June 2011, found that the Fukushima Dai-ichi, Unit 4 spent fuel pool, the one believed to have sustained the most serious damage, actually remained ‘‘nearly undamaged.’’ 35 The report noted that visual inspections found no water leaks or serious damage to the Unit 4 spent fuel pool. On April 25, 2014, the NRC issued a report entitled, ‘‘NRC Overview of the Structural Integrity of the Spent Fuel Pool at Fukushima Dai-ichi, Unit 4,’’ which confirmed that the structural integrity of the Unit 4 spent fuel pool was not compromised. The accident at the Fukushima Daiichi nuclear facility in Japan also led to additional questions about the safe storage of spent fuel and whether the NRC should require the expedited transfer of spent fuel from spent fuel pools to dry cask storage at nuclear power plants in the United States. This issue was identified by NRC staff subsequent to the NTTF report along with the understanding that further study was needed to determine if regulatory action was warranted. Consequently, a regulatory analysis was conducted on the expedited transfer of spent fuel from pools to dry cask storage. The results of this analysis were provided to the Commission in COMSECY–13–0030, ‘‘Staff Evaluation and Recommendation for Japan Lessons Learned Tier 3 Issue on Expedited Transfer of Spent Fuel,’’ dated November 12, 2013. The Commission subsequently concluded that regulatory action need not be pursued in SRM– COMSECY–13–0030, issued on May 23, 2014. Nothing that the petitioners provided in these petitions invalidates this conclusion. On August 26, 2014, the Commission approved the ‘‘continued storage’’ final rule and its associated generic environmental impact statement amending 10 CFR part 51 to revise the generic determination on the environmental impacts of continued storage of spent nuclear fuel beyond the licensed life for operation of a reactor. The continued storage GEIS 36 also concluded that the environmental impacts from spent fuel pool fires are small during the short-term storage timeframe (the 60 years of continued storage after the end of a reactor’s licensed life for operation), which is consistent with the finding of the license renewal GEIS. Therefore, the petitioners have not shown that the NTTF report contains any new and significant information that would alter the analysis of spent fuel pool accidents in the GEIS. On the contrary, the NRC’s ongoing studies of this issue have consistently supported the finding in Table B–1 that the environmental impacts of spent fuel pool accidents would be small. III. Determination of Petitions For the reasons described in Section II of this document, the NRC has concluded that there is no basis to rescind the NRC’s generic conclusions in Table B–1 concerning the environmental impacts of the ‘‘Severe accidents’’ and ‘‘Onsite storage of spent nuclear fuel’’ issues nor to amend any other NRC regulation. Therefore, the NRC is denying the petitions in accordance with 10 CFR 2.803. IV. Availability of Documents The documents identified in the following table are available to interested persons through one or more of the following methods, as indicated. For more information on accessing ADAMS, see the ADDRESSES section of this document. ADAMS Accession No./Web link/Federal Register citation CLI–99–22, Hydro Resources, Inc., July 23, 1999 .................................. mstockstill on DSK4VPTVN1PROD with RULES Document http://www.nrc.gov/reading-rm/doc-collections/commission/orders/1999/ 1999-022cli.pdf. http://www.nrc.gov/reading-rm/doc-collections/commission/orders/2001/ 2001-017cli.pdf. http://www.nrc.gov/reading-rm/doc-collections/commission/orders/2011/ 2011-05cli.pdf. http://www.nrc.gov/reading-rm/doc-collections/commission/orders/2012/ 2012-15cli.pdf. http://www.nrc.gov/reading-rm/doc-collections/commission/comm-secy/ 2011/2011-0002comgbj.pdf. ML13329A918. CLI–01–17, Florida Power & Light Co. (Turkey Point Nuclear Generating Plant, Units 3 and 4), July 19, 2001. CLI–11–05, Union Electric Company d/b/a Ameren Missouri (Callaway Plant, Unit 2), September 9, 2011. CLI–12–15, Entergy Nuclear Generation Company and Entergy Nuclear Operations, Inc. (Pilgrim Nuclear Power Station), June 7, 2012. COMGBJ–11–0002, NRC Actions Following the Events in Japan, March 21, 2011. COMSECY–13–0030, Staff Evaluation and Recommendation for Japan Lessons-Learned Tier 3 Issue on Expedited Transfer of Spent Fuel, November 12, 2013. Federal Register notice—Consideration of Environmental Impacts of Temporary Storage of Spent Fuel After Cessation of Reactor Operation, December 23, 2010. Federal Register notice—Environmental Review for Renewal of Nuclear Power Plant Operating Licenses, June 5, 1996. Federal Register notice—License Renewal of Nuclear Power Plants; Generic Environmental Impact Statement and Standard Review Plans for Environmental Reviews, June 20, 2013. Federal Register notice—Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating Licenses, June 20, 2013. Federal Register notice—Taxpayers and Ratepayers United, et al.; Environmental Impacts of Severe Reactor and Spent Fuel Pool Accidents, November 10, 2011. Federal Register notice—The Attorney General of Commonwealth of Massachusetts, The Attorney General of California; Denial of Petitions for Rulemaking, August 8, 2008. described spent fuel pools as ‘‘massive, extremelyrobust structures designed to safely contain the spent fuel discharged from a nuclear reactor under a variety of normal, off-normal, and hypothetical accident conditions (e.g., loss of-electrical power, floods, earthquakes, or tornadoes).’’ 73 FR at 46206. VerDate Sep<11>2014 18:35 Aug 11, 2015 Jkt 235001 75 FR 81032. 61 FR 28467. 78 FR 37325. 78 FR 37282. 76 FR 70067. 73 FR 46204. The NRC’s denials of PRM–51–10 and PRM–51–12 were upheld in court. New York v. U.S. Nuclear Regulatory Commission, 589 F.3d 551 (2nd Cir. 2009). 35 See ‘‘Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety-The PO 00000 Frm 00006 Fmt 4700 Sfmt 4700 Accident at TEPCO’s Fukushima Nuclear Power Stations,’’ IV–91. English version available at http:// www.kantei.go.jp/foreign/kan/topics/201106/iaea_ houkokusho_e.html, last visited on April 22, 2013. 36 NUREG–2157, Appendix F, Section F.1.3, Page F–16, ‘‘Conclusion.’’ E:\FR\FM\12AUR1.SGM 12AUR1 Federal Register / Vol. 80, No. 155 / Wednesday, August 12, 2015 / Rules and Regulations mstockstill on DSK4VPTVN1PROD with RULES Document ADAMS Accession No./Web link/Federal Register citation Recommendations for Enhancing Reactor Safety in the 21st Century, Recommendations for Enhancing Reactor Safety in the 21st Century, Near-Term Task Force Review of Insights from the Fukushima DaiIchi Accident, July 12, 2011. Regulatory Guide 4.2, Supplement 1, Rev. 1, June 2013 ....................... NRC Overview of the Structural Integrity of the Spent Fuel Pool at Fukushima Dai-ichi, Unit 4, April 25, 2014. NUREG–1353, Regulatory Analysis for the Resolution of Generic Issue 82, Beyond Design Basis Accidents in Spent Fuel Pools, April 1989. NUREG–1437, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, June 20, 2013. NUREG–1738, Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants, February 2001. NUREG–2157, Generic Environmental Impact Statement for Continued Storage of Spent Nuclear Fuel, September, 2014. Petition submitted by Commonwealth of Massachusetts (PRM-51-10), September 19, 2006. Preparation of Supplemental Environmental Reports for Applications to Renew Nuclear Power Plant Operating Licenses, Chapter 5, Revision 1, June 20, 2013. PRM 51–14 submitted by Gene Stilp, on behalf of Taxpayers and Ratepayers United (Bell Bend—COL), August 11, 2011. PRM 51–15 submitted by Diane Curran, on behalf of San Luis Obispo Mothers for Peace (Diablo Canyon—LR), August 11, 2011. PRM 51–16 submitted by Diane Curran, on behalf of Southern Alliance for Clean Energy (Watts Bar—OL), August 11, 2011. PRM 51–17 submitted by Mindy Goldstein, on behalf of Center for a Sustainable Coast, Georgia Women’s Action for New Directions f/k/a/ Atlanta Women’s Action for New Directions, and Southern Alliance for Clean Energy (Vogtle—COL), August 11, 2011. PRM 51–18 submitted by Mindy Goldstein, on behalf of Southern Alliance for Clean Energy, National Parks Conservation Association, Dan Kipnis, and Mark Oncavage (Turkey Point—COL), August 11, 2011. PRM 51–19 submitted by Deborah Brancato, on behalf of Riverkeeper, Inc. & Hudson River Sloop Clearwater, Inc. (Indian Point—LR), August 11, 2011. PRM 51–20 submitted by Paul Gunter, on behalf of Beyond Nuclear, Seacoast Anti-Pollution League and Sierra Club of New Hampshire (Seabrook—LR), August 11, 2011. PRM 51–21 submitted by Michael Mariotte, on behalf of Nuclear Information and Resource Service, Beyond Nuclear, Public Citizen, and SOMDCARES (Calvert Cliffs—COL), August 11, 2011. PRM 51–22 submitted by Raymond Shadis, on behalf of Friends of the Coast and New England Coalition (Seabrook—LR), August 11, 2011. PRM 51–23 submitted by Robert V. Eye, on behalf of Intervenors in South Texas Project Nuclear Operating Co., Application for Units 3 and 4 Combined Operating License (South Texas—COL), August 11, 2011. PRM 51–24 submitted by Robert V. Eye, on behalf of Intervenors in Luminant Generation Company, LCC, Application for Comanche Peak Nuclear Power Plant Combined License (Comanche Peak— COL), August 11, 2011. PRM 51–25 submitted by Mary Olson, on behalf of the Ecology Party of Florida, Nuclear Information (Levy—COL), August 11, 2011. PRM 51–26 submitted by Terry Lodge, on behalf of Beyond Nuclear, Citizens Environment Alliance of Southwestern Ontario, Don’t Waste Michigan, and the Green Party of Ohio (Davis-Besse—LR), August 11, 2011. PRM 51–27 submitted by Terry Lodge, on behalf of Beyond Nuclear, Citizens for Alternatives to Chemical Contamination, Citizens Environmental Alliance of Southwestern Ontario, Don’t Waste Michigan, Sierra Club, Keith Gunter, Edward McArdle, Henry Newman, Derek Coronado, Sandra Bihn, Harold L. Stokes, Michael J. Keegan, Richard Coronado, George Steinman, Marilyn R. Timmer, Leonard Mandeville, Frank Mantei, Marcee Meyers, and Shirley Steinman (Fermi—COL), August 11, 2011. PRM 51–28 submitted by Barry White, on behalf of Citizens Allied for Safe Energy, Inc (Turkey Point—COL), August 11, 2011. Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety—The Accident at TEPCO’s Fukushima Nuclear Power Stations, June 2011. SECY–11–0093, Near-Term Report and Recommendations for Agency Actions Following the Events in Japan, July 12, 2011. VerDate Sep<11>2014 18:35 Aug 11, 2015 Jkt 235001 48241 PO 00000 Frm 00007 Fmt 4700 ML111861807. ML13067A354. ML14111A099. ML082330232. ML13107A023. ML010430066. ML14196A107. ML062640409. ML13106A244. ML112430559. ML11236A322. ML11223A291. ML11223A043. ML11223A044. ML11229A712. ML11223A371. ML11223A344. ML11223A465. ML11223A472. ML11223A477. ML11224A074. ML112450527. ML112450528. ML11224A232. http://www.kantei.go.jp/foreign/kan/topics/201106/iaea_houkokusho_ e.html. ML11186A959. Sfmt 4700 E:\FR\FM\12AUR1.SGM 12AUR1 48242 Federal Register / Vol. 80, No. 155 / Wednesday, August 12, 2015 / Rules and Regulations Document ADAMS Accession No./Web link/Federal Register citation SECY-11-0124, Recommended Actions to be Taken Without Delay from the Near Term Task Force Report, September 9, 2011. SECY–11–0137, Prioritization of Recommended Actions to be Taken in Response to Fukushima Lessons Learned, October 3, 2011. SECY–13–0112, Consequence Study of a Beyond-Design-Basis Earthquake Affecting the Spent Fuel Pool for a U.S. Mark I Boiling-Water Reactor, October 9, 2013. SRM–COMSECY–13–0030, Staff Evaluation and Recommendation for Japan Lessons-Learned Tier 3 Issue on Expedited Transfer of Spent Fuel, May 23, 2014. Dated at Rockville, Maryland, this 4th day of August, 2015. For the Nuclear Regulatory Commission. Annette L. Vietti-Cook, Secretary of the Commission. [FR Doc. 2015–19843 Filed 8–11–15; 8:45 am] BILLING CODE 7590–01–P DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 23 [Docket No. FAA–2015–2903; Special Conditions No. 23–270–SC] Special Conditions: Honda Aircraft Company, Model HA–420, HondaJet; Ventilation Requirements in High Altitude Operations Federal Aviation Administration (FAA), DOT. ACTION: Final special conditions; request for comments. AGENCY: These special conditions are issued for the Honda Aircraft Company, Model HA–420 airplane. This airplane will have a novel or unusual design feature associated with high altitude operations above 41,000 feet. The applicable airworthiness regulations do not contain adequate or appropriate safety standards for this design feature. These special conditions contain the additional safety standards that the Administrator considers necessary to establish a level of safety equivalent to that established by the existing airworthiness standards. DATES: The effective date of these special conditions is August 12, 2015. We must receive your comments by September 11, 2015 ADDRESSES: Send comments identified by docket number FAA–2015–2903 using any of the following methods: • Federal eRegulations Portal: Go to http://www.regulations.gov and follow the online instructions for sending your comments electronically. • Mail: Send comments to Docket Operations, M–30, U.S. Department of mstockstill on DSK4VPTVN1PROD with RULES SUMMARY: VerDate Sep<11>2014 18:35 Aug 11, 2015 Jkt 235001 ML11245A127. ML11269A204. ML13256A334. ML14143A360. Transportation (DOT), 1200 New Jersey Avenue SE., Room W12–140, West Building Ground Floor, Washington, DC 20590–0001. • Hand Delivery of Courier: Take comments to Docket Operations in Room W12–140 of the West Building Ground Floor at 1200 New Jersey Avenue SE., Washington, DC, between 9 a.m., and 5 p.m., Monday through Friday, except Federal holidays. • Fax: Fax comments to Docket Operations at 202–493–2251. Privacy: The FAA will post all comments it receives, without change, to http://regulations.gov, including any personal information the commenter provides. Using the search function of the docket Web site, anyone can find and read the electronic form of all comments received into any FAA docket, including the name of the individual sending the comment (or signing the comment for an association, business, labor union, etc.). DOT’s complete Privacy Act Statement can be found in the Federal Register published on April 11, 2000 (65 FR 19477–19478), as well as at http://DocketsInfo.dot.gov. Docket: Background documents or comments received may be read at http://www.regulations.gov at any time. Follow the online instructions for accessing the docket or go to the Docket Operations in Room W12–140 of the West Building Ground Floor at 1200 New Jersey Avenue SE., Washington, DC, between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. FOR FURTHER INFORMATION CONTACT: Leslie B. Taylor, Federal Aviation Administration, Small Airplane Directorate, Aircraft Certification Service, 901 Locust, Room 301, Kansas City, MO 64106; telephone (816) 329– 4134; facsimile (816) 329–4090. SUPPLEMENTARY INFORMATION: The FAA has determined, in accordance with 5 U.S. Code 553(b)(3)(B) and 553(d)(3), that notice and opportunity for prior public comment hereon are unnecessary because the substance of these special conditions has been subject to the public comment process in several prior instances with no substantive comments PO 00000 Frm 00008 Fmt 4700 Sfmt 4700 received. The FAA therefore finds that good cause exists for making these special conditions effective upon issuance. Special condition No. Company/airplane model 23–243–SC ....... 23–102–SC ....... 25–ANM–108 .... Embraer Model EMB–505. Cessna Model 525A. Gulfstream Aerospace Corporation, Model Gulfstream V. Comments Invited We invite interested people to take part in this rulemaking by sending written comments, data, or views. The most helpful comments reference a specific portion of the special conditions, explain the reason for any recommended change, and include supporting data. We ask that you send us two copies of written comments. We will consider all comments we receive on or before the closing date for comments. We will consider comments filed late if it is possible to do so without incurring expense or delay. We may change these special conditions based on the comments we receive. Background On October 11, 2006, Honda Aircraft Company applied for a type certificate for their new model HA–420. On October 10, 2013, Honda Aircraft Company requested an extension with an effective application date of October 1, 2013. This extension changed the type certification basis to amendment 23–62. The HA–420 is a four to five passenger (depending on configuration), two crew, lightweight business jet with a 43,000-foot service ceiling and a maximum takeoff weight of 9963 pounds. The airplane is powered by two GE-Honda Aero Engines (GHAE) HF– 120 turbofan engines. This airplane will have a novel or unusual design feature associated with high altitude operations above 41,000 feet. During the development of the supersonic transport special conditions, it was noted that certain pressurization E:\FR\FM\12AUR1.SGM 12AUR1

Agencies

[Federal Register Volume 80, Number 155 (Wednesday, August 12, 2015)]
[Rules and Regulations]
[Pages 48235-48242]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-19843]



========================================================================
Rules and Regulations
                                                Federal Register
________________________________________________________________________

This section of the FEDERAL REGISTER contains regulatory documents 
having general applicability and legal effect, most of which are keyed 
to and codified in the Code of Federal Regulations, which is published 
under 50 titles pursuant to 44 U.S.C. 1510.

The Code of Federal Regulations is sold by the Superintendent of Documents. 
Prices of new books are listed in the first FEDERAL REGISTER issue of each 
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Federal Register / Vol. 80, No. 155 / Wednesday, August 12, 2015 / 
Rules and Regulations

[[Page 48235]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 51

[Docket Nos. PRM-51-14, et al.; NRC-2011-0189]


Environmental Impacts of Severe Reactor and Spent Fuel Pool 
Accidents

AGENCY: Nuclear Regulatory Commission.

ACTION: Petition for rulemaking; denial.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is denying 15 
petitions for rulemaking submitted by the petitioners identified in the 
table in Section IV, ``Availability of Documents.'' The petitioners 
requested that the NRC rescind its regulations that ``reach generic 
conclusions about the environmental impacts of severe reactor and/or 
spent fuel pool accidents and therefore prohibit considerations of 
those impacts in reactor licensing proceedings.''

DATES: The dockets for petitions for rulemaking (PRM) PRM-51-14, PRM-
51-15, PRM-51-16, PRM-51-17, PRM-51-18, PRM-51-19, PRM-51-20, PRM-51-
21, PRM-51-22, PRM-51-23, PRM-51-24, PRM-51-25, PRM-51-26, PRM-51-27, 
and PRM-51-28 are closed on August 12, 2015.

ADDRESSES: Please refer to Docket ID NRC-2011-0189 when contacting the 
NRC about the availability of information for any of these petitions. 
You may obtain publicly-available information related to this action by 
any of the following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2011-0189. Address 
questions about NRC dockets to Carol Gallagher, telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to PDR.resource@nrc.gov. For 
the convenience of the reader, instructions about obtaining information 
regarding the 15 petitions and other materials referenced in this 
document are provided in the ``Availability of Documents'' section.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, MD 20852.

FOR FURTHER INFORMATION CONTACT: Jennifer Tobin, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-2328; email: Jennifer.Tobin@nrc.gov.

SUPPLEMENTARY INFORMATION:

Table of Contents

I. Background
II. Environmental Impacts of Severe Reactor Accidents and Spent Fuel 
Pool Accidents
III. Determination of Petitions
IV. Availability of Documents

I. Background

    The 15 petitions were filed in August 2011 in response to the 
publication of the NRC's Near-Term Task Force (NTTF) report, 
``Recommendations for Enhancing Reactor Safety in the 21st Century, 
NTTF Review of Insights from the Fukushima Dai-ichi Accident,'' dated 
July 12, 2011. The NTTF report provided the NRC staff's recommendations 
to enhance U.S. nuclear power plant safety following the March 11, 
2011, Fukushima accident in Japan. Based upon their interpretation of 
the NTTF report, the petitioners requested that the NRC rescind all 
regulations in part 51 of Title 10 of the Code of Federal Regulations 
(10 CFR) ``to the extent that they reach generic conclusions about the 
environmental impacts of severe reactor and/or spent fuel pool 
accidents and therefore prohibit considerations of those impacts in 
reactor licensing proceedings.'' \1\ The NRC's regulations in 10 CFR 
part 51 implement Section 102(2) of the National Environmental Policy 
Act of 1969, as amended (NEPA).\2\ The petitioners challenged the 
regulations that make generic environmental findings for license 
renewal proceedings regarding the environmental impacts of severe 
reactor accidents and spent fuel storage.
---------------------------------------------------------------------------

    \1\ See, e.g., San Luis Obispo Mothers for Peace Petition for 
Rulemaking, PRM-51-15 at 2 (August 11, 2011). All of the petitions 
have the same, or essentially the same, request for rulemaking.
    \2\ 10 CFR 51.1(a).
---------------------------------------------------------------------------

    The NTTF report, the 15 petitions, along with their NRC assigned 
docket numbers, and other pertinent documents are listed in Section IV, 
``Availability of Documents,'' of this document. The NRC published a 
notice of receipt of the petitions in the Federal Register (FR) on 
November 10, 2011 (76 FR 70067).\3\ As explained in the November 10, 
2011, notice, the Commission stated that it was:
---------------------------------------------------------------------------

    \3\ The petitioners also requested a suspension of ongoing 
reactor licensing proceedings. In its notice of the petitions' 
receipt, the Commission referenced its September 9, 2011, decision, 
CLI-11-05, denying the petitioners' suspension requests. 76 FR at 
70068 citing Union Electric Company d/b/a Ameren Missouri (Callaway 
Plant, Unit 2), et al., CLI-11-05, 74 NRC 141, 173-76 (2011).

reviewing the [NTTF report], including the issues presented in the 
15 petitions for rulemaking. The petitioners specifically cite the 
[NTTF report] as rationale for the PRMs [petitions for rulemaking]. 
The NRC will consider the issues raised by these PRMs through the 
process the Commission has established for addressing the 
recommendations from the [NTTF report] and is not providing a 
separate opportunity for public comment on the PRMs at this time.\4\
---------------------------------------------------------------------------

    \4\ 76 FR 70069.

As such, the NRC staff placed the 15 petitions into abeyance pending 
the outcome of deliberations regarding the recommendations from the 
NTTF report. Although activities related to the NTTF report are 
ongoing, the NRC staff determined that sufficient information is now 
available to address the 15 petitions.

A. Nuclear Power Plant License Renewal Actions and Table B-1

    Under NEPA, the NRC must consider the environmental impacts of a 
major

[[Page 48236]]

Federal action in an Environmental Impact Statement.\5\ The Commission 
has determined that power plant license renewal is a major Federal 
action that requires an Environmental Impact Statement.\6\ On many 
environmental issues related to license renewal, the Commission ``found 
that it could draw generic conclusions applicable to all existing 
nuclear power plants, or to a specific subgroup of plants.'' \7\ 
Therefore, in accordance with 10 CFR 51.95(c), for nuclear power plant 
license renewal actions, the NRC relies upon NUREG-1437, ``Generic 
Environmental Impact Statement for License Renewal of Nuclear Plants'' 
(GEIS). This environmental impact statement was initially published in 
May 1996 (1996 GEIS) and then revised and updated in June 2013 (2013 
GEIS).\8\ The GEIS describes the potential environmental impacts of 
renewing the operating license of a nuclear power plant for an 
additional 20 years. The NRC classifies the environmental impacts of 
license renewal as either generic or site-specific. Generic issues 
(i.e., environmental impacts common to all nuclear power plants) are 
addressed in the GEIS. Site-specific issues are addressed initially by 
the license renewal applicant (i.e., a nuclear power plant licensee 
seeking a renewal of its operating license under the NRC's license 
renewal regulations in 10 CFR part 54), in its environmental report, 
which is required by 10 CFR 51.45, and then by the NRC in the 
supplemental environmental impact statement (SEIS) to the GEIS prepared 
for each license renewal application. The criteria for a license 
renewal applicant's environmental report are set forth in 10 CFR 
51.53(c).
---------------------------------------------------------------------------

    \5\ 42 U.S.C. 4332(c).
    \6\ 10 CFR 51.2(b)(2).
    \7\ Florida Power & Light Co. (Turkey Point Nuclear Generating 
Plant, Units 3 and 4), CLI-01-17, 54 NRC 3,11 (2001).
    \8\ The NRC regulation, 10 CFR 51.95(c), requires, for the 
consideration of potential environmental impacts of renewing a 
nuclear power plant's operating license under 10 CFR part 54, that 
the NRC prepare an environmental impact statement, which is a 
supplement to the Commission's NUREG-1437, ``Generic Environmental 
Impact Statement for License Renewal of Nuclear Plants,'' issued in 
June 2013. At the time the petitions were filed in 2011, 10 CFR 
51.95(c) referred to the initial 1996 GEIS. The NRC published a 
notice of issuance for the updated 2013 GEIS on June 20, 2013 (78 FR 
37325).
---------------------------------------------------------------------------

    Under the NRC's current regulatory framework in 10 CFR part 51 for 
evaluating the potential environmental impacts of renewing a nuclear 
power reactor's operating license for an additional 20 years, neither 
the applicant's environmental report nor the NRC's SEIS are required to 
address issues previously determined to be generic, as addressed in the 
GEIS, absent new and significant information. The findings of the GEIS 
are codified in Table B-1 in appendix B to subpart A of 10 CFR part 51 
(Table B-1).\9\ In Table B-1, generic issues are designated as 
``Category 1'' issues and site-specific issues are designated as 
``Category 2'' issues. All of the NRC regulations cited by the 
petitioners pertain, either directly or indirectly, to generic findings 
in the GEIS that are, in turn, codified in Table B-1. The petitioners 
object to those Table B-1 findings that make generic conclusions with 
respect to the potential environmental impacts of severe reactor and 
spent fuel pool accidents, namely, the findings for ``Severe 
accidents'' and ``Onsite storage of spent nuclear fuel.'' \10\ The NRC 
defines ``severe reactor accidents'' as ``those that could result in 
substantial damage to the reactor core, whether or not there are 
serious off-site consequences.'' \11\
---------------------------------------------------------------------------

    \9\ Table B-1 was amended to reflect the June 2013 GEIS update. 
The NRC rule amending Table B-1 and other 10 CFR part 51 regulations 
was published in the Federal Register on June 20, 2013 (78 FR 
37282).
    \10\ The petitions were filed in August 2011, before the June 
2013 final rule that revised Table B-1 and other provisions of 10 
CFR part 51 was published. The 2013 amendments to the Table B-1, 
``Severe accidents'' finding, however, were of a minor, editorial 
nature (consisting of no more than deleting a regulatory reference). 
Otherwise, the language of Table B-1, ``Severe accidents'' finding 
is the same as the language that was in effect when the petitions 
were filed in 2011.
    \11\ NUREG-1437, ``Generic Environmental Impact Statement for 
License Renewal of Nuclear Plants,'' Vol.1, Chapter 1 at 1-27 
(2013).
---------------------------------------------------------------------------

    In accordance with 10 CFR 2.335(a),\12\ NRC rules and regulations, 
such as Table B-1, generally cannot be challenged in NRC adjudicatory 
proceedings, including site-specific license renewal proceedings for a 
nuclear power plant before the NRC's Atomic Safety and Licensing Board. 
Therefore, the petitioners request the rescission of the generic 
findings in Table B-1 so that they can challenge the NRC environmental 
impact findings now included in Table B-1 in future license renewal 
proceedings.
---------------------------------------------------------------------------

    \12\ The NRC regulation, 10 CFR 2.335(a) states, in pertinent 
part, that ``no rule or regulation of the Commission, or any 
provision thereof, concerning the licensing of production and 
utilization facilities, source material, special nuclear material, 
or byproduct material, is subject to attack by way of discovery, 
proof, argument, or other means in any adjudicatory proceeding 
subject to this [10 CFR part 2].'' Paragraphs 2.335(b)-(d) provide 
exceptions to the provision in 10 CFR 2.335(a).
---------------------------------------------------------------------------

    In Table B-1, the ``Severe accidents'' issue has been classified as 
a Category 2, or site-specific, issue with an impact level finding of 
``small.'' \13\ Although not classified as a generic issue, the Table 
B-1 ``Severe accidents'' finding states that:
---------------------------------------------------------------------------

    \13\ For most Table B-1 NEPA issues, the NRC determined whether 
the impacts of license renewal would have a small, moderate, or 
large environmental impact. The statement of considerations for the 
June 20, 2013, rulemaking stated that ``[a] small impact means that 
the environmental effects are not detectable, or are so minor that 
they would neither destabilize nor noticeably alter any important 
attribute of the resource. A moderate impact means that the 
environmental effects are sufficient to alter noticeably, but not 
destabilize, important attributes of the resource. A large impact 
means that the environmental effects would be clearly noticeable and 
would be sufficient to destabilize important attributes of the 
resource'' (78 FR 37285).

[t]he probability-weighted consequences of atmospheric releases, 
fallout onto open bodies of water, releases to groundwater, and 
societal and economic impacts from severe accidents are small for 
all plants. However, alternatives to mitigate severe accidents must 
be considered for all plants that have not considered such 
alternatives.\14\
---------------------------------------------------------------------------

    \14\ 10 CFR part 51, subpart A, appendix B, Table B-1, ``Severe 
accidents'' finding (emphasis added).

The Commission has clarified that despite the Category 2 label, the 
severe-accidents-impact finding in Table B-1 equates to a generic 
environmental issue resolved by rule.\15\
---------------------------------------------------------------------------

    \15\ Entergy Nuclear Generating Co. and Entergy Nuclear 
Operations, Inc. (Pilgrim Nuclear Power Station), CLI-12-15, 75 NRC 
704, 709 (2012).
---------------------------------------------------------------------------

    The Table B-1 ``Onsite storage of spent nuclear fuel'' issue has 
been classified as a Category 1, or generic, issue also with an impact 
level finding of ``small'' since Table B-1's inception in 1996. The 
``Onsite storage of spent nuclear fuel'' finding states that: The 
expected increase in the volume of spent fuel from an additional 20 
years of operation can be safely accommodated onsite during the license 
renewal term with small environmental effects through dry or pool 
storage at all plants. For the period after the licensed life for 
reactor operations, the impacts of onsite storage of spent nuclear fuel 
during the continued storage period are discussed in NUREG-2157 and as 
stated in Sec.  51.23(b), shall be deemed incorporated into this 
issue.\16\
---------------------------------------------------------------------------

    \16\ 10 CFR part 51, subpart A, app. B, Table B-1, ``Onsite 
storage of spent nuclear fuel'' finding. Spent fuel is initially 
stored in spent fuel pools. Following a sufficient period of time to 
allow the spent fuel to cool, spent fuel may be removed from the 
pool and placed in large casks on the licensee controlled site 
(``dry'' storage).
---------------------------------------------------------------------------

    The 2013 amendments to the Table B-1 ``Onsite storage of spent 
nuclear fuel'' finding were made to comport with the U.S. Court of 
Appeals decision in New York v. NRC, 681 F.3d 471 (D.C. Cir. 2012), 
which vacated the NRC's 2010 final rule that updated the NRC's ``waste 
confidence'' decision and rule

[[Page 48237]]

(75 FR 81032, 81037; December 23, 2010). On September 19, 2014, the NRC 
issued the final ``continued storage'' rule \17\ (formerly known as the 
waste confidence rule), which addressed the New York vs. NRC decision.
---------------------------------------------------------------------------

    \17\ 79 FR 56238.
---------------------------------------------------------------------------

B. NTTF Report

    Following the March 11, 2011, Fukushima Dai-ichi accident, the 
Commission directed the NRC staff to establish a task force to conduct 
a methodical and systematic review of NRC processes and regulations to 
determine whether the agency should make additional improvements to its 
regulatory system and to make recommendations to the Commission for its 
policy direction.\18\ The NRC staff formed the NTTF, which submitted 
the NTTF report to the Commission in SECY-11-0093, ``Near-Term Report 
and Recommendations for Agency Actions Following the Events in Japan,'' 
dated July 12, 2011. The 15 petitions were filed in August 2011.
---------------------------------------------------------------------------

    \18\ Tasking Memorandum--COMGBJ-11-0002--NRC Actions Following 
the Events in Japan, March 21, 2011.
---------------------------------------------------------------------------

    The NTTF report provided various NRC staff recommendations to the 
Commission concerning the enhancement of reactor safety and a general 
implementation strategy, which included several proposals for new 
regulatory requirements. Recognizing that rulemaking and subsequent 
implementation would take several years to accomplish, the NTTF also 
recommended interim actions necessary to enhance reactor protection, 
severe reactor accident mitigation, and emergency preparedness while 
rulemaking activities were conducted.\19\ In addition, the NTTF report 
concluded that a sequence of events like the Fukushima accident is 
unlikely to occur in the United States and therefore, ongoing power 
reactor operations and related licensing activities do not pose an 
imminent risk to public health and safety.
---------------------------------------------------------------------------

    \19\ http://www.nrc.gov/reactors/operating/ops-experience/japan-dashboard.html.
---------------------------------------------------------------------------

    The NRC staff further refined the NTTF recommendations in SECY-11-
0124, ``Recommended Actions to be Taken Without Delay from the Near-
Term Task Force Report,'' and SECY-11-0137, ``Prioritization of 
Recommended Actions to be Taken in Response to Fukushima Lessons 
Learned,'' both of which described the NRC staff's recommendations for 
enhancing reactor safety and the priority for implementing those 
recommendations. Based on those recommendations, the NRC has issued 
orders and initiated rulemaking activities to enhance the safety of 
reactors as a result of lessons learned from the Fukushima Dai-ichi 
accident. The petitioners contend that the recommendations of the NTTF 
report provide the justification for their request that the NRC rescind 
regulations in 10 CFR part 51 to the extent that they reach generic 
conclusions with respect to potential environmental impacts of severe 
reactor and spent fuel pool accidents and that preclude consideration 
of those conclusions in individual license renewal proceedings. 
Specifically, the petitions request that the NRC amend the following 
regulations: 10 CFR 51.45, 10 CFR 51.53, 10 CFR 51.95, and Table B-1.

C. Other NRC Regulations Identified by the Petitioners

    The NRC regulation, 10 CFR 51.45, sets forth the general 
requirements for an environmental report, which the NRC defines as a 
document submitted to the Commission by an applicant for a permit, 
license, or other form of permission, or an amendment to or renewal of 
a permit, license or other form of permission, in order to aid the 
Commission in complying with Section 102(2) of NEPA.\20\ Paragraph 
51.45(b) requires that the environmental report contain a description 
of the proposed action, a statement of its purposes, and a description 
of the environment affected. Section 51.45 also contains a list of 
items that the environmental report should discuss, such as the impact 
of the proposed action on the environment, any adverse effects that 
cannot be avoided if the proposed action were to be implemented, and 
alternatives to the proposed action.\21\
---------------------------------------------------------------------------

    \20\ 10 CFR 51.14(a) (definition of ``environmental report'').
    \21\ 10 CFR 51.45(b)(1)-(5).
---------------------------------------------------------------------------

    The NRC regulation, 10 CFR 51.53(c), describes the applicant's 
preparation of an environmental report for the renewal of a nuclear 
power plant's operating license. Paragraph 51.53(c)(3)(i) states that 
the environmental report is not required to include analyses of the 
potential environmental impacts identified as Category 1 issues in 
Table B-1. Paragraphs (c)(3)(ii)(A)-(P) of 10 CFR 51.53, describe the 
requirement to conduct environmental impact analyses for those Category 
2 issues in Table B-1 that must be addressed on a site-specific basis 
by the license renewal applicant in its environmental report. In 
addition, paragraph 51.53(c)(3)(iv), requires the environmental report 
to include any new and significant information regarding the 
environmental impacts of license renewal of which the applicant is 
aware.
    The NRC regulation, 10 CFR 51.95, describes the preparation of a 
post-construction environmental impact statement by the NRC, such as at 
the license renewal stage. Both 10 CFR 51.53 and 10 CFR 51.95 were 
among the regulations amended by the NRC to reflect the June 2013 
update to the GEIS.\22\
---------------------------------------------------------------------------

    \22\ The NRC rule amending these regulations was published in 
the Federal Register on June 20, 2013 (78 FR 37282).
---------------------------------------------------------------------------

D. Several Petitions Concern Actions Outside of License Renewal

    Several of the petitions were filed in relation to new reactor 
licensing proceedings, as opposed to proceedings concerning the renewal 
of an existing nuclear power plant's operating license. The petitions 
filed for combined license (COL) actions are: PRM-51-14, -51-17, -51-
18, -51-21, -51-23, -51-24, -51-25, -51-27, and -51-28; PRM-51-16 was 
filed for an operating license (OL) action. The generic findings to 
which the petitioners object concern only license renewal actions 
conducted pursuant to 10 CFR part 54. Specifically, the NRC's 10 CFR 
part 51 regulations that reach generic conclusions regarding severe 
accident or spent fuel storage issues in Table B-1 do not apply to new 
reactor applications made under the provisions of 10 CFR part 52 for 
either an early site permit (ESP) or a COL, or to a construction permit 
(CP) or OL application (e.g., the Watts Bar 2 application) made under 
the provisions of 10 CFR part 50. The NRC makes no generic conclusions 
about severe reactor and spent fuel pool accidents when preparing 
environmental impacts statements for ESP, COL, CP, or OL applications. 
For these types of applications, the NRC performs a site-specific 
environmental review to address the potential environmental impacts.

II. Environmental Impacts of Severe Reactor Accidents and Spent Fuel 
Pool Accidents

A. Overview

    The petitioners assert that the lessons learned from the Fukushima 
Dai-ichi event, as documented in the recommendations of the NTTF 
report, provide ``new and significant'' information that would affect 
the NRC's analysis of severe reactor and spent fuel pool accidents when 
considering whether to renew a nuclear power plant's operating license 
for an additional 20 years in accordance with the NRC's regulations in 
10 CFR part 54,

[[Page 48238]]

``Requirements for Renewal of Operating Licenses for Nuclear Power 
Plants.'' It is upon this basis that the petitioners request that the 
NRC rescind all regulations in 10 CFR part 51 that ``reach generic 
conclusions about the environmental impacts of severe reactor and/or 
spent fuel pool accidents and therefore prohibit considerations of 
those impacts in reactor licensing proceedings.'' \23\
---------------------------------------------------------------------------

    \23\ See, e.g., San Luis Obispo Mothers for Peace Petition for 
Rulemaking, PRM-51-15 at 1 (August 11, 2011). All of the petitions 
have the same, or essentially the same, request for rulemaking.
---------------------------------------------------------------------------

    Under NEPA case law, the standard for considering whether 
information is ``new and significant'' is that it must present ``a 
seriously different picture of the environmental impact of the proposed 
project from what was previously envisioned.'' \24\ If the information 
is ``new and significant,'' and if the agency has not yet taken the 
proposed action, then the agency is required to supplement its 
environmental impact statement.\25\ The NRC has determined that the 
NTTF report recommendations do not constitute ``new and significant'' 
information.
---------------------------------------------------------------------------

    \24\ Union Electric Company d/b/a Ameren Missouri (Callaway 
Plant, Unit 2), et al, CLI-11-05, 74 NRC 141, 167-68 (2011) quoting 
Hydro Resources, Inc., CLI-99-22, 50 NRC 3, 14 (1999) (``To merit 
this additional review, information must be both `new' and 
`significant,' and it must bear on the proposed action or its 
impacts. As we have explained, `[t]he new information must present 
`a seriously different picture of the environmental impact of the 
proposed project from what was previously envisioned' '') 
(alteration in the original.); Sierra Club v. Froehlke, 816 F.2d 
205, 210 (5th Cir. 1987) (``In making its determination whether to 
supplement an existing EIS because of new information, the [United 
States Army, Corps of Engineers] should consider `the extent to 
which the new information presents a picture of the likely 
environmental consequences associated with the proposed action not 
envisioned by the original EIS'.'') (alteration added); Wisconsin v. 
Weinberger, 745 F.2d 412, 418 (7th Cir.1984) (supplementation 
required where new information ``provides a seriously different 
picture of the environmental landscape.''); and see NRC Regulatory 
Guide 4.2, Supplement 1, Revision 1, ``Preparation of Supplemental 
Environmental Reports for Applications to Renew Nuclear Power Plant 
Operating Licenses,'' Chapter 5 (June 2013).
    \25\ 10 CFR 51.92(a).
---------------------------------------------------------------------------

    The NTTF report recommendations do not challenge the generic 
determinations in Table B-1. The NTTF report did not explicitly 
consider the complex analysis underlying the determinations in Table B-
1, did not recommend changing the generic determinations in Table B-1 
regarding severe reactor and spent fuel pool accidents, and did not 
make any recommendations relating to nuclear power plant license 
renewals. Any NRC regulatory action that has been taken or could have 
been taken as a result of the information presented in the NTTF report 
would not have been deferred to the license renewal stage; any such 
action would have been taken as part of the NRC's ongoing safety 
program.

B. Severe Reactor Accidents

    First, the petitioners requested that the NRC rescind all of its 
regulations that reach generic conclusions about the environmental 
impacts of severe reactor accidents. As set forth in both Table B-1 and 
10 CFR 51.53(c)(3)(ii)(L), ``Severe accidents'' is listed as a Category 
2 or site-specific issue, rather than a generic issue because the 
Commission determined the agency should consider severe accident 
mitigation measures on a site-specific basis for those reactors for 
which the agency had not previously performed a similar analysis. 
However, as noted above, the Commission has confirmed that because the 
agency made a generic determination regarding severe accident impacts 
in the GEIS that is codified in Table B-1, the impacts portion of the 
issue has been resolved by rule.\26\
---------------------------------------------------------------------------

    \26\ Florida Power & Light Co. (Turkey Point Nuclear Generating 
Plant, Units 3 and 4), CLI-01-17, 54 NRC 3,11 (2001).
---------------------------------------------------------------------------

GEIS Severe Accident Analysis
    When the NRC promulgated the license renewal rule and the severe 
accidents finding in Table B-1 in 1996, the NRC conducted a detailed 
analysis in the GEIS to determine that the probability weighted 
environmental impacts of severe accidents are small. The Commission 
summarized this analysis in the associated Federal Register notice.

    The GEIS provides an analysis of the consequences of severe 
accidents for each site in the country. The analysis adopts standard 
assumptions about each site for parameters such as evacuation speeds 
and distances traveled, and uses site-specific estimates for 
parameters such as population distribution and meteorological 
conditions. These latter two factors were used to evaluate the 
exposure indices for these analyses. The methods used result in 
predictions of risk that are adequate to illustrate the general 
magnitude and types of risks that may occur from reactor accidents. 
Regarding site-evacuation risk, the radiological risk to persons as 
they evacuate is taken into account within the individual plant risk 
assessments that form the basis for the GEIS. In addition, 10 CFR 
part 50 requires that licensees maintain up-to-date emergency plans. 
This requirement will apply in the license renewal term as well as 
in the current licensing term.
    As was done in the GEIS analysis, the use of generic source 
terms (one set for PWRs and another for BWRs) is consistent with the 
past practice that has been used and accepted by the NRC for 
individual plant Final Environmental Impact Statements (FEISs). The 
purpose of the source term discussion in the GEIS is to describe 
whether or not new information on source terms developed after the 
completion of the most recent FEISs indicates that the source terms 
used in the past under-predict environmental consequences. The NRC 
has concluded that analysis of the new source term information 
developed over the past 10 years indicates that the expected 
frequency and amounts of radioactive release under severe accident 
conditions are less than that predicted using the generic source 
terms. A summary of the evolution of this research is provided in 
NUREG-1150, ``Severe Accident Risks: An Assessment for Five U.S. 
Nuclear Power Plants'' (December 1990), and its supporting 
documentation. Thus, the analyses performed for the GEIS represent 
adequate, plant-specific estimates of the impacts from severe 
accidents that would generally over-predict, rather than under-
predict, environmental consequences. Therefore, the GEIS analysis of 
the impacts of severe accidents for license renewal is retained and 
is considered applicable to all plants.\27\

    \27\ 61 FR 28467, 28480. See also NUREG-1437, ``Generic 
Environmental Impact Statement for License Renewal of Nuclear 
Plants,'' Vol. 1, Chapter 5 at 5-1 to 5-116 (1996).
---------------------------------------------------------------------------

In preparing the 2013 GEIS, the NRC staff specifically considered and 
evaluated severe reactor accidents and found that the conclusions 
reached in the 1996 GEIS remained valid. Specifically, the NRC staff 
considered areas where new information showed increases in the 
consequences of severe accidents and compared them to areas where the 
new information showed decreases in the impacts from severe 
accidents.\28\ The NRC staff found that information showed that the 
areas that reflected an increase in impacts could potentially account 
for a 470 percent increase.\29\ But, the NRC staff found that the areas 
that reflected a decrease in impacts could account for a 500 percent to 
10,000 percent reduction.\30\
---------------------------------------------------------------------------

    \28\ NUREG-1437, ``Generic Environmental Impact Statement for 
License Renewal of Nuclear Plants,'' Vol. 1, Rev. 1, appendix E at 
E-46 to E-47 (2013).
    \29\ Id.
    \30\ Id.
---------------------------------------------------------------------------

    The petitions for rulemaking and supporting affidavit do not 
challenge with any specificity the analyses underlying the 1996 GEIS. 
The NTTF report, upon which the petitioners' rely, largely described 
the accident sequence at Fukushima, considered the NRC's current 
regulatory framework, and recommended areas for improvement. Indeed, 
the NTTF report concluded that a sequence of events like the Fukushima 
accident is unlikely to occur in the United States and, therefore, 
ongoing power reactor operations and related licensing activities do 
not pose an imminent risk to public health and safety. As a result, on 
their face, the

[[Page 48239]]

safety conclusions in the NTTF report do not appear to relate to the 
environmental analysis challenged by the petitioners. Moreover, the 
petitioners have not demonstrated that any information in the NTTF 
report undermines the environmental analysis in the GEIS. For example, 
the petitioners have not shown, or even alleged, that the source terms 
relied on by the NRC staff were inadequate, that the analysis ignored 
or marginalized an exposure pathway, or that the NRC's consideration of 
evacuation times was unreasonable. Moreover, the petitioners do not 
suggest that any errors in the severe accident analysis underlying the 
Table B-1 findings were significant enough to overcome the substantial 
margins noted by the Commission in 1996 and confirmed by the NRC staff 
in the 2013 update, let alone provide a ``seriously different picture'' 
of the likelihood and consequences of a severe accident beyond that 
already considered. Therefore, the findings of the NTTF report do not 
indicate that the NRC should revise the 2013 GEIS, or present a 
seriously different picture of the environmental consequences of severe 
accidents beyond those already considered by the agency.
Petitioners' Focus on License Renewal Regulations
    The petitioners largely focus their arguments on a claim that 
currently operating reactors will need to undertake expensive 
improvements to comply with the NRC's post-Fukushima requirements and 
that the agency's environmental review must account for these costs. 
But these arguments reflect a misunderstanding of our regulatory 
process. As stated in the 2013 GEIS:

    As of the publication date of [the 2013] GEIS, the NRC's 
evaluation of the consequences of the Fukushima events is ongoing. 
As such, the NRC will continue to evaluate the need to make 
improvements to existing regulatory requirements based on the task 
force report and additional studies and analyses of the Fukushima 
events as more information is learned. To the extent that any 
revisions are made to NRC regulatory requirements, they would be 
made applicable to nuclear power reactors regardless of whether or 
not they have a renewed license. Therefore, no additional analyses 
have been performed in this GEIS as a result of the Fukushima 
events. In the event that the NRC identifies information from the 
Fukushima events that constitutes new and significant information 
with respect to the environmental impacts of license renewal, the 
NRC will discuss that information in its site-specific supplemental 
EISs (SEISs) to the GEIS, as it does with all such new and 
significant information.\31\
---------------------------------------------------------------------------

    \31\ NUREG-1437, ``Generic Environmental Impact Statement for 
License Renewal of Nuclear Plants,'' Vol. 1, Rev. 1, Chapter 1, 
Section 1.9. at 1-33 and 1-34 (2013) (citations omitted) (emphasis 
added).

As that paragraph from the 2013 GEIS explains, if the NRC finds that an 
additional requirement should be imposed upon a reactor licensee the 
NRC will impose that requirement regardless of its license renewal 
posture. The renewal of a nuclear power plant's operating license does 
not, in any way, prescribe the NRC's ongoing safety surveillance of 
that plant. The regulations that the petitioners want rescinded pertain 
only to license renewal findings, not the NRC's ongoing safety 
---------------------------------------------------------------------------
surveillance.

    The NRC continues to address severe accident-related issues in the 
day to day regulatory oversight of nuclear power plant licensees. The 
NRC's regulatory efforts have reduced severe accident risks beyond what 
was considered in the 1996 and 2013 GEIS. In some cases, such as the 
NRC's response to the accident at Fukushima Dai-ichi, these regulatory 
activities are ongoing. The NRC will continue to evaluate the need to 
make improvements to existing regulatory requirements as more 
information is learned.

C. Spent Fuel Pool Accidents

    Last, the petitioners contend that the NTTF report provides new and 
significant information that warrants rescinding the NRC's regulations 
codifying the GEIS' generic environmental determinations of the impacts 
of onsite storage of spent nuclear fuel during the period of license 
renewal. The evaluation of the environmental impacts of the onsite 
storage of spent nuclear fuel during the license renewal term, 
including potential spent fuel pool accidents, was documented in the 
1996 GEIS and reaffirmed in the 2013 GEIS. The NRC found that the 
probability of a fuel cladding fire is low even in the event of a 
``worst probable cause of a loss of spent-fuel pool coolant (a severe 
seismic-generated accident causing a catastrophic failure of the 
pool).'' \32\ Based on these evaluations, the ``Onsite storage of spent 
nuclear fuel'' NEPA issue in Table B-1 has been classified as a 
Category 1, or generic, issue with an impact level finding of 
``small.'' As noted above, the NTTF report primarily focused on 
describing the Fukushima accident, analyzing the agency's current 
regulatory structure, and making recommendations for improving the 
agency's regulatory process. The NTTF report did not specifically 
address the agency's environmental analysis for on-site spent fuel 
storage or the agency's prior studies showing that the risk of an 
accident in a spent fuel pool would be small. Moreover, the petitioners 
have not provided any specific explanation of how information in the 
NTTF report would invalidate the findings in the GEIS and thereby call 
into question the regulations in 10 CFR part 51.
---------------------------------------------------------------------------

    \32\ See also NUREG-1437, ``Generic Environmental Impact 
Statement for License Renewal of Nuclear Plants,'' Vol. 1, Chapter 6 
at 6-72 to 6-75 (1996).
---------------------------------------------------------------------------

    Moreover, the NRC has thoroughly considered the question of spent 
fuel pool accidents before and after promulgating the 1996 GEIS, and 
these studies have consistently found that the probability of a spent 
fuel pool fire is low. Spent fuel pools are large, robust structures 
that contain thousands of gallons of water. Spent fuel pools have 
thick, reinforced, concrete walls and floors lined with welded, 
stainless-steel plates. After removal from the reactor, spent fuel 
assemblies are placed into these pools and stored under at least 20 
feet of water, which provides adequate shielding from radiation. 
Redundant monitoring, cooling, and make-up water systems are part of 
the spent fuel pool system. Spent fuel pools at operating U.S. nuclear 
power plants were designed and licensed to maintain a large inventory 
of water to protect and cool spent fuel under normal and accident 
conditions, including earthquakes. Domestic and international 
operational experience and past NRC studies (e.g., NUREG-1353, NUREG-
1738, and SECY-13-0112) \33\ have borne out that spent fuel pools are 
effectively designed to prevent accidents that could affect the safe 
storage of spent fuel. Regarding spent fuel pool accidents, the 
petitioners' primary concern is a ``seismically induced'' spent fuel 
pool fire (i.e., an earthquake damaging the structure of the spent fuel 
pool and thereby causing a complete or partial drainage of the pool's 
water.) \34\ With

[[Page 48240]]

respect to the March 2011 Fukushima accident, a Japanese government 
report, issued in June 2011, found that the Fukushima Dai-ichi, Unit 4 
spent fuel pool, the one believed to have sustained the most serious 
damage, actually remained ``nearly undamaged.'' \35\ The report noted 
that visual inspections found no water leaks or serious damage to the 
Unit 4 spent fuel pool. On April 25, 2014, the NRC issued a report 
entitled, ``NRC Overview of the Structural Integrity of the Spent Fuel 
Pool at Fukushima Dai-ichi, Unit 4,'' which confirmed that the 
structural integrity of the Unit 4 spent fuel pool was not compromised.
---------------------------------------------------------------------------

    \33\ These studies include NUREG-1353, ``Regulatory Analysis for 
the Resolution of Generic Issue 82, `Beyond Design Basis Accidents 
in Spent Fuel Pools' '' (April 1989); NUREG-1738, ``Technical Study 
of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power 
Plants'' (February 2001); and SECY-13-0112, ``Consequence Study of a 
Beyond-Design-Basis Earthquake Affecting the Spent Fuel Pool for a 
U.S. Mark I Boiling-Water Reactor'' (October 2013).
    \34\ Potential spent fuel pool fires caused by a successful 
terrorist strike were the subject of rulemaking petitions filed in 
2006 (PRM-51-10) and 2007 (PRM-51-12). These petitions also 
requested the rescission of the generic finding in Table B-1 
concerning onsite spent fuel storage. The NRC denied these petitions 
in 2008 (73 FR 46204; August 8, 2008). In its denial notice, the NRC 
described spent fuel pools as ``massive, extremely-robust structures 
designed to safely contain the spent fuel discharged from a nuclear 
reactor under a variety of normal, off-normal, and hypothetical 
accident conditions (e.g., loss of-electrical power, floods, 
earthquakes, or tornadoes).'' 73 FR at 46206. The NRC's denials of 
PRM-51-10 and PRM-51-12 were upheld in court. New York v. U.S. 
Nuclear Regulatory Commission, 589 F.3d 551 (2nd Cir. 2009).
    \35\ See ``Report of Japanese Government to the IAEA Ministerial 
Conference on Nuclear Safety-The Accident at TEPCO's Fukushima 
Nuclear Power Stations,'' IV-91. English version available at http://www.kantei.go.jp/foreign/kan/topics/201106/iaea_houkokusho_e.html, 
last visited on April 22, 2013.
---------------------------------------------------------------------------

    The accident at the Fukushima Dai-ichi nuclear facility in Japan 
also led to additional questions about the safe storage of spent fuel 
and whether the NRC should require the expedited transfer of spent fuel 
from spent fuel pools to dry cask storage at nuclear power plants in 
the United States. This issue was identified by NRC staff subsequent to 
the NTTF report along with the understanding that further study was 
needed to determine if regulatory action was warranted. Consequently, a 
regulatory analysis was conducted on the expedited transfer of spent 
fuel from pools to dry cask storage. The results of this analysis were 
provided to the Commission in COMSECY-13-0030, ``Staff Evaluation and 
Recommendation for Japan Lessons Learned Tier 3 Issue on Expedited 
Transfer of Spent Fuel,'' dated November 12, 2013. The Commission 
subsequently concluded that regulatory action need not be pursued in 
SRM-COMSECY-13-0030, issued on May 23, 2014. Nothing that the 
petitioners provided in these petitions invalidates this conclusion.
    On August 26, 2014, the Commission approved the ``continued 
storage'' final rule and its associated generic environmental impact 
statement amending 10 CFR part 51 to revise the generic determination 
on the environmental impacts of continued storage of spent nuclear fuel 
beyond the licensed life for operation of a reactor. The continued 
storage GEIS \36\ also concluded that the environmental impacts from 
spent fuel pool fires are small during the short-term storage timeframe 
(the 60 years of continued storage after the end of a reactor's 
licensed life for operation), which is consistent with the finding of 
the license renewal GEIS. Therefore, the petitioners have not shown 
that the NTTF report contains any new and significant information that 
would alter the analysis of spent fuel pool accidents in the GEIS. On 
the contrary, the NRC's ongoing studies of this issue have consistently 
supported the finding in Table B-1 that the environmental impacts of 
spent fuel pool accidents would be small.
---------------------------------------------------------------------------

    \36\ NUREG-2157, Appendix F, Section F.1.3, Page F-16, 
``Conclusion.''
---------------------------------------------------------------------------

III. Determination of Petitions

    For the reasons described in Section II of this document, the NRC 
has concluded that there is no basis to rescind the NRC's generic 
conclusions in Table B-1 concerning the environmental impacts of the 
``Severe accidents'' and ``Onsite storage of spent nuclear fuel'' 
issues nor to amend any other NRC regulation. Therefore, the NRC is 
denying the petitions in accordance with 10 CFR 2.803.

IV. Availability of Documents

    The documents identified in the following table are available to 
interested persons through one or more of the following methods, as 
indicated. For more information on accessing ADAMS, see the ADDRESSES 
section of this document.

------------------------------------------------------------------------
                                          ADAMS Accession No./Web link/
                Document                    Federal Register citation
------------------------------------------------------------------------
CLI-99-22, Hydro Resources, Inc., July   http://www.nrc.gov/reading-rm/
 23, 1999.                                doc-collections/commission/
                                          orders/1999/1999-022cli.pdf.
CLI-01-17, Florida Power & Light Co.     http://www.nrc.gov/reading-rm/
 (Turkey Point Nuclear Generating         doc-collections/commission/
 Plant, Units 3 and 4), July 19, 2001.    orders/2001/2001-017cli.pdf.
CLI-11-05, Union Electric Company d/b/a  http://www.nrc.gov/reading-rm/
 Ameren Missouri (Callaway Plant, Unit    doc-collections/commission/
 2), September 9, 2011.                   orders/2011/2011-05cli.pdf.
CLI-12-15, Entergy Nuclear Generation    http://www.nrc.gov/reading-rm/
 Company and Entergy Nuclear              doc-collections/commission/
 Operations, Inc. (Pilgrim Nuclear        orders/2012/2012-15cli.pdf.
 Power Station), June 7, 2012.
COMGBJ-11-0002, NRC Actions Following    http://www.nrc.gov/reading-rm/
 the Events in Japan, March 21, 2011.     doc-collections/commission/
                                          comm-secy/2011/2011-
                                          0002comgbj.pdf.
COMSECY-13-0030, Staff Evaluation and    ML13329A918.
 Recommendation for Japan Lessons-
 Learned Tier 3 Issue on Expedited
 Transfer of Spent Fuel, November 12,
 2013.
Federal Register notice--Consideration   75 FR 81032.
 of Environmental Impacts of Temporary
 Storage of Spent Fuel After Cessation
 of Reactor Operation, December 23,
 2010.
Federal Register notice--Environmental   61 FR 28467.
 Review for Renewal of Nuclear Power
 Plant Operating Licenses, June 5, 1996.
Federal Register notice--License         78 FR 37325.
 Renewal of Nuclear Power Plants;
 Generic Environmental Impact Statement
 and Standard Review Plans for
 Environmental Reviews, June 20, 2013.
Federal Register notice--Revisions to    78 FR 37282.
 Environmental Review for Renewal of
 Nuclear Power Plant Operating
 Licenses, June 20, 2013.
Federal Register notice--Taxpayers and   76 FR 70067.
 Ratepayers United, et al.;
 Environmental Impacts of Severe
 Reactor and Spent Fuel Pool Accidents,
 November 10, 2011.
Federal Register notice--The Attorney    73 FR 46204.
 General of Commonwealth of
 Massachusetts, The Attorney General of
 California; Denial of Petitions for
 Rulemaking, August 8, 2008.

[[Page 48241]]

 
Recommendations for Enhancing Reactor    ML111861807.
 Safety in the 21st Century,
 Recommendations for Enhancing Reactor
 Safety in the 21st Century, Near-Term
 Task Force Review of Insights from the
 Fukushima Dai-Ichi Accident, July 12,
 2011.
Regulatory Guide 4.2, Supplement 1,      ML13067A354.
 Rev. 1, June 2013.
NRC Overview of the Structural           ML14111A099.
 Integrity of the Spent Fuel Pool at
 Fukushima Dai-ichi, Unit 4, April 25,
 2014.
NUREG-1353, Regulatory Analysis for the  ML082330232.
 Resolution of Generic Issue 82, Beyond
 Design Basis Accidents in Spent Fuel
 Pools, April 1989.
NUREG-1437, Generic Environmental        ML13107A023.
 Impact Statement for License Renewal
 of Nuclear Plants, June 20, 2013.
NUREG-1738, Technical Study of Spent     ML010430066.
 Fuel Pool Accident Risk at
 Decommissioning Nuclear Power Plants,
 February 2001.
NUREG-2157, Generic Environmental        ML14196A107.
 Impact Statement for Continued Storage
 of Spent Nuclear Fuel, September, 2014.
Petition submitted by Commonwealth of    ML062640409.
 Massachusetts (PRM[dash]51[dash]10),
 September 19, 2006.
Preparation of Supplemental              ML13106A244.
 Environmental Reports for Applications
 to Renew Nuclear Power Plant Operating
 Licenses, Chapter 5, Revision 1, June
 20, 2013.
PRM 51-14 submitted by Gene Stilp, on    ML112430559.
 behalf of Taxpayers and Ratepayers
 United (Bell Bend--COL), August 11,
 2011.
PRM 51-15 submitted by Diane Curran, on  ML11236A322.
 behalf of San Luis Obispo Mothers for
 Peace (Diablo Canyon--LR), August 11,
 2011.
PRM 51-16 submitted by Diane Curran, on  ML11223A291.
 behalf of Southern Alliance for Clean
 Energy (Watts Bar--OL), August 11,
 2011.
PRM 51-17 submitted by Mindy Goldstein,  ML11223A043.
 on behalf of Center for a Sustainable
 Coast, Georgia Women's Action for New
 Directions f/k/a/ Atlanta Women's
 Action for New Directions, and
 Southern Alliance for Clean Energy
 (Vogtle--COL), August 11, 2011.
PRM 51-18 submitted by Mindy Goldstein,  ML11223A044.
 on behalf of Southern Alliance for
 Clean Energy, National Parks
 Conservation Association, Dan Kipnis,
 and Mark Oncavage (Turkey Point--COL),
 August 11, 2011.
PRM 51-19 submitted by Deborah           ML11229A712.
 Brancato, on behalf of Riverkeeper,
 Inc. & Hudson River Sloop Clearwater,
 Inc. (Indian Point--LR), August 11,
 2011.
PRM 51-20 submitted by Paul Gunter, on   ML11223A371.
 behalf of Beyond Nuclear, Seacoast
 Anti-Pollution League and Sierra Club
 of New Hampshire (Seabrook--LR),
 August 11, 2011.
PRM 51-21 submitted by Michael           ML11223A344.
 Mariotte, on behalf of Nuclear
 Information and Resource Service,
 Beyond Nuclear, Public Citizen, and
 SOMDCARES (Calvert Cliffs--COL),
 August 11, 2011.
PRM 51-22 submitted by Raymond Shadis,   ML11223A465.
 on behalf of Friends of the Coast and
 New England Coalition (Seabrook--LR),
 August 11, 2011.
PRM 51-23 submitted by Robert V. Eye,    ML11223A472.
 on behalf of Intervenors in South
 Texas Project Nuclear Operating Co.,
 Application for Units 3 and 4 Combined
 Operating License (South Texas--COL),
 August 11, 2011.
PRM 51-24 submitted by Robert V. Eye,    ML11223A477.
 on behalf of Intervenors in Luminant
 Generation Company, LCC, Application
 for Comanche Peak Nuclear Power Plant
 Combined License (Comanche Peak--COL),
 August 11, 2011.
PRM 51-25 submitted by Mary Olson, on    ML11224A074.
 behalf of the Ecology Party of
 Florida, Nuclear Information (Levy--
 COL), August 11, 2011.
PRM 51-26 submitted by Terry Lodge, on   ML112450527.
 behalf of Beyond Nuclear, Citizens
 Environment Alliance of Southwestern
 Ontario, Don't Waste Michigan, and the
 Green Party of Ohio (Davis-Besse--LR),
 August 11, 2011.
PRM 51-27 submitted by Terry Lodge, on   ML112450528.
 behalf of Beyond Nuclear, Citizens for
 Alternatives to Chemical
 Contamination, Citizens Environmental
 Alliance of Southwestern Ontario,
 Don't Waste Michigan, Sierra Club,
 Keith Gunter, Edward McArdle, Henry
 Newman, Derek Coronado, Sandra Bihn,
 Harold L. Stokes, Michael J. Keegan,
 Richard Coronado, George Steinman,
 Marilyn R. Timmer, Leonard Mandeville,
 Frank Mantei, Marcee Meyers, and
 Shirley Steinman (Fermi--COL), August
 11, 2011.
PRM 51-28 submitted by Barry White, on   ML11224A232.
 behalf of Citizens Allied for Safe
 Energy, Inc (Turkey Point--COL),
 August 11, 2011.
Report of Japanese Government to the     http://www.kantei.go.jp/foreign/
 IAEA Ministerial Conference on Nuclear   kan/topics/201106/
 Safety--The Accident at TEPCO's          iaea_houkokusho_e.html.
 Fukushima Nuclear Power Stations, June
 2011.
SECY-11-0093, Near-Term Report and       ML11186A959.
 Recommendations for Agency Actions
 Following the Events in Japan, July
 12, 2011.

[[Page 48242]]

 
SECY[dash]11[dash]0124, Recommended      ML11245A127.
 Actions to be Taken Without Delay from
 the Near Term Task Force Report,
 September 9, 2011.
SECY-11-0137, Prioritization of          ML11269A204.
 Recommended Actions to be Taken in
 Response to Fukushima Lessons Learned,
 October 3, 2011.
SECY-13-0112, Consequence Study of a     ML13256A334.
 Beyond-Design-Basis Earthquake
 Affecting the Spent Fuel Pool for a
 U.S. Mark I Boiling-Water Reactor,
 October 9, 2013.
SRM-COMSECY-13-0030, Staff Evaluation    ML14143A360.
 and Recommendation for Japan Lessons-
 Learned Tier 3 Issue on Expedited
 Transfer of Spent Fuel, May 23, 2014.
------------------------------------------------------------------------


    Dated at Rockville, Maryland, this 4th day of August, 2015.

    For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. 2015-19843 Filed 8-11-15; 8:45 am]
BILLING CODE 7590-01-P