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 Nuclear Regulatory Commission [Docket No. 50-305; NRC-2014-0219]
 AGENCY: Nuclear Regulatory Commission.
 ACTION: Exemption; issuance.
 SUMMARY: Kewaunee Power Station (KPS) is a decommissioning nuclear power reactor that permanently shut down on May 7, 2013, and permanently defueled on May 14, 2013. In response to a request from Dominion Energy Kewaunee, Inc. (DEK or the licensee), the U.S. Nuclear Regulatory Commission (NRC) is granting exemptions from certain emergency planning (EP) requirements. The exemptions will eliminate the requirements to maintain offsite radiological emergency plans and reduce the scope of the onsite emergency planning activities at the Kewaunee Power Station (KPS) based on the reduced risks of accidents that could result in an offsite radiological 
                        ( print page 65716)
                        release when compared to operating power reactors. The exemptions will continue to maintain requirements for onsite radiological emergency planning and include provisions for capabilities to communicate and coordinate with offsite response authorities. The NRC staff has concluded that the exemptions being granted by this action will maintain an acceptable level of emergency preparedness at KPS given its permanently shutdown and defueled status, and that there is reasonable assurance that adequate offsite protective measures can and will be taken by State and local government agencies, if needed, in the event of a radiological emergency at the KPS facility.
 ADDRESSES: Please refer to Docket ID NRC-2014-0219 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods: *Federal Rulemaking Web site:*
                         Go to 
                        *http://www.regulations.gov*
                         and search for Docket ID NRC-2014-0219. Address questions about NRC dockets to Carol Gallagher; telephone: 301-287-3422; email: 
                        *Carol.Gallagher@nrc.gov.*
                         For technical questions, contact the individual listed in the 
                        **FOR FURTHER INFORMATION CONTACT**
                         section of this document.
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 FOR FURTHER INFORMATION CONTACT: William Huffman, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-2046; email: 
                        *William.Huffman@nrc.gov.* I. Background The KPS facility is a decommissioning power reactor located on approximately 900 acres in Carlton (Kewaunee County), Wisconsin, 27 miles southeast of Green Bay, Wisconsin. The licensee, DEK, is the holder of KPS Renewed Facility Operating License No. DPR-43. The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the NRC now or hereafter in effect. By letter dated February 25, 2013 (ADAMS Accession No. ML13058A065), DEK submitted a certification to the NRC indicating it would permanently cease power operations at KPS on May 7, 2013. On May 7, 2013, DEK permanently shut down the KPS reactor. On May 14, 2013, DEK certified that it had permanently defueled the KPS reactor vessel (ADAMS Accession No. ML13135A209). As a permanently shutdown and defueled facility, and in accordance with § 50.82(a)(2) of Title 10 of the 
                        *Code of Federal Regulations*
                         (10 CFR), KPS is no longer authorized to operate the reactor or emplace nuclear fuel into the reactor vessel. Kewaunee Power Station is still authorized to possess and store irradiated nuclear fuel. Irradiated fuel is currently being stored onsite in a spent fuel pool (SFP) and in Independent Spent Fuel Storage Installation (ISFSI) dry casks. During normal power reactor operations, the forced flow of water through the reactor coolant system (RCS) removes heat generated by the reactor. The RCS, operating at high temperatures and pressures, transfers this heat through the steam generator tubes converting non-radioactive feedwater to steam, which then flows to the main turbine generator to produce electricity. Many of the accident scenarios postulated in the updated safety analysis reports (USARs) for operating power reactors involve failures or malfunctions of systems which could affect the fuel in the reactor core, which in the most severe postulated accidents, would involve the release of large quantities of fission products. With the permanent cessation of reactor operations at KPS and the permanent removal of the fuel from the reactor core, such accidents are no longer possible. The reactor, RCS, and supporting systems are no longer in operation and have no function related to the storage of the irradiated fuel. Therefore, postulated accidents involving failure or malfunction of the reactor, RCS, or supporting systems are no longer applicable. Since KPS is permanently shutdown and defueled, the only design basis accident that could potentially result in an offsite radiological release at KPS is the fuel handling accident. Analysis performed by DEK showed that 90 days after KPS permanently shutdown, the radiological consequence of the fuel handling accident would not exceed the limits established by the U.S. Environmental Protection Agency's (EPA's) Protective Action Guidelines (PAGs) at the exclusion area boundary. Based on the time that KPS has been permanently shutdown (approximately 17 months), there is no longer any possibility of an offsite radiological release from a design basis-accident that could exceed the EPA PAGs. The EP requirements of 10 CFR 50.47, “Emergency plans,” and Appendix E to 10 CFR Part 50, “Emergency Planning and Preparedness for Production and Utilization Facilities,” continue to apply to nuclear power reactors that have permanently ceased operation and have removed all fuel from the reactor vessel. There are no explicit regulatory provisions distinguishing EP requirements for a power reactor that is permanently shutdown and defueled from a reactor that is authorized to operate. In order for DEK to modify the KPS emergency plan to reflect the reduced risk associated with the permanently shutdown and defueled condition of KPS, certain exemptions from the EP regulations must be obtained before the KPS emergency plan can be amended. II. Request/Action By letter dated July 31, 2013, “Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E” (ADAMS Accession No. ML13221A182), DEK requested exemptions from certain EP requirements of 10 CFR Part 50 for KPS. More specifically, DEK requested exemptions from certain planning standards in 10 CFR 50.47(b) regarding onsite and offsite radiological emergency plans for nuclear power reactors; from certain requirements in 10 CFR 50.47(c)(2) that require establishment of plume exposure and ingestion pathway emergency planning zones for nuclear power reactors; and from certain requirements in 10 CFR Part 50, Appendix E, Section IV, which establishes the elements that make up the content of emergency plans. In a letter dated December 11, 2013 (ADAMS Accession No. ML13351A040), DEK provided responses to the NRC staff's request for additional information (RAI) concerning the proposed exemptions. In a letter dated January 10, 2014, DEK 
                        ( print page 65717)
                        provided a supplemental response to the RAI (ADAMS Accession No. ML14016A078), which contained information applicable to the SFP inventory makeup strategies for mitigating the potential loss of water inventory due to a beyond design-basis accident. The information provided by DEK included justifications for each exemption requested. The exemptions requested by DEK will eliminate the requirements to maintain offsite radiological emergency plans, reviewed by the Federal Emergency Management Agency (FEMA) under the requirements of 44 CFR Part 350, and reduce the scope of onsite emergency planning activities. DEK stated that application of all of the standards and requirements in 10 CFR 50.47(b), 10 CFR 50.47(c) and 10 CFR Part 50, Appendix E is not needed for adequate emergency response capability based on the reduced risks at the permanently shutdown and defueled facility. If offsite protective actions where needed for a very unlikely accident that could challenge the safe storage of spent fuel at KPS, provisions exist for offsite agencies to take protective actions using a comprehensive emergency management plan (CEMP) under the National Preparedness System to protect the health and safety of the public. A CEMP in this context, also referred to as an emergency operations plan (EOP), is addressed in FEMA Comprehensive Preparedness Guide 101, “Developing and Maintaining Emergency Operations Plans.” Comprehensive Preparedness Guide 101 is the foundation for State, territorial, Tribal, and local emergency planning in the United States. It promotes a common understanding of the fundamentals of risk-informed planning and decision making and helps planners at all levels of government in their efforts to develop and maintain viable, all-hazards, all-threats emergency plans. An EOP is flexible enough for use in all emergencies. It describes how people and property will be protected; details who is responsible for carrying out specific actions; identifies the personnel, equipment, facilities, supplies and other resources available; and outlines how all actions will be coordinated. A comprehensive emergency management plan is often referred to as a synonym for “all hazards planning.” III. Discussion In accordance with 10 CFR 50.12, “Specific exemptions,” the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50 when: (1) The exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) any of the special circumstances listed in 10 CFR 50.12(a)(2) are present. These special circumstances include, among other things, that the application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule. As noted previously, the current EP regulations contained in 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50 apply to both operating and shutdown power reactors. The NRC has consistently acknowledged that the risk of an offsite radiological release at a power reactor that has permanently ceased operations and removed fuel from the reactor vessel is significantly lower, and the types of possible accidents are significantly fewer, than at an operating power reactor. However, EP regulations are silent with regard to the fact that once a power reactor permanently ceases operation, the consequences of credible emergency accident scenarios are reduced. The reduced risks generally relate to a decrease in the potential for any significant offsite radiological release based on the preclusion of accidents applicable to an operating power reactor and on the reduced decay heat, and the decay of short-lived radionuclides as spent fuel ages. NUREG-1738, “Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants,” dated February 2001 (ADAMS Accession No. ML010430066), confirmed that for permanently shutdown and defueled power reactors bounded by the assumptions and conditions in the report, the risk of offsite radiological release is significantly less than for an operating power reactor. Similar to the EP exemptions requested by DEK, prior EP exemptions granted to permanently shutdown and defueled power reactors did not relieve the licensees of all EP requirements. Rather, the exemptions allowed the licensees to modify their emergency plans commensurate with the credible site-specific risks that were consistent with a permanently shutdown and defueled status. Specifically, precedent for the approval of the exemptions from certain EP requirements for previous permanently shutdown and defueled power reactors were based on demonstrating that: (1) The radiological consequences of design-basis accidents would not exceed the limits of the EPA PAGs at the exclusion area boundary, and; (2) in the unlikely event of a beyond design-basis accident resulting in a loss of all modes of heat transfer from the fuel stored in the SFP, there is sufficient time to initiate appropriate mitigating actions, and if needed, for offsite authorities to implement offsite protective actions using a CEMP approach to protect the health and safety of the public. With respect to design-basis accidents at KPS, the licensee provided analysis demonstrating that 90 days after KPS was permanently shutdown, the radiological consequences of the only remaining design-basis accident with potential for offsite radiological release (the fuel handling accident) will not exceed the limits of the EPA PAGs at the exclusion area boundary. Therefore, because KPS has been permanently shutdown for approximately 17 months, there is no longer any design-basis accident that would warrant an offsite radiological emergency plan meeting the requirements of 10 CFR Part 50. With respect to beyond design-basis accidents at KPS, the licensee analyzed the two bounding beyond design-basis accidents that have a potential for a significant offsite release. One of these beyond design-basis accidents involves a complete loss of SFP water inventory, where cooling of the spent fuel would be primarily accomplished by natural circulation of air through the uncovered spent fuel assemblies. The licensee's analysis of this accident shows that by October 30, 2014, air cooling of the spent fuel assemblies will be sufficient to keep the fuel within a safe temperature range indefinitely without fuel damage or offsite radiological release. The other beyond design-basis accident analysis performed by the licensee could not completely rule out the possibility of a radiological release from a SFP. This more limiting analysis assumes an incomplete drain down of the SFP water, or some other catastrophic event (such as a complete drainage of the SFP with rearrangement of spent fuel rack geometry and/or the addition of rubble to the SFP), that would effectively impede any decay heat removal through all possible modes of cooling. The licensee's analysis demonstrates that as of October 21, 2014, there would be at least 10 hours after the loss of all cooling means considered in the analysis for the described beyond design-basis accident, before the spent fuel cladding would reach a temperature where the potential for a significant offsite radiological release could occur. This analysis conservatively does not consider the period of time from the initiating event 
                        ( print page 65718)
                        causing a loss of SFP water inventory until all cooling means are lost. The NRC staff has verified DEK's analyses and its calculations. The analyses provide reasonable assurance that in granting the requested exemption to DEK, there is no design-basis accident that will result in an offsite radiological release exceeding the EPA PAGs at the site boundary. In the unlikely event of a beyond design-basis accident affecting the SFP that results in a complete loss of heat removal via all modes of heat transfer, there will be at least 10 hours available before an offsite release might occur and, therefore, at least 10 hours to initiate appropriate mitigating actions to restore a means of heat removal to the spent fuel. If a radiological release were projected to occur under this unlikely scenario, a minimum of 10 hours is considered sufficient time for offsite authorities to implement protective actions using a CEMP approach to protect the health and safety of the public. The NRC staff reviewed the licensee's justification for the requested exemptions against the criteria in 10 CFR 50.12(a), in addition to considering the basis for prior EP exemption requests as discussed above, to determine whether the exemptions should be granted. After evaluating the exemption requests, the staff determined, as described below, that the criteria in 10 CFR50.12(a) are met, and that the exemptions should be granted. Assessment of the DEK EP exemptions is described in SECY-14-0066, “Request by Dominion Energy Kewaunee, Inc. for Exemptions from Certain Emergency Planning Requirements,” dated June 27, 2014 (ADAMS Accession No. ML14072A257). The Commission approved the NRC staff's intention to grant the exemptions in the staff requirements memorandum (SRM) to SECY-14-0066, dated August 7, 2014 (ADAMS Accession No. ML14219A366). Descriptions of the specific exemptions being granted to DEK, with the NRC staff's basis for granting each exemption, are provided in SECY-14-0066 and summarized in a table at the end of this document. The staff's detailed review and technical basis for the approval of the specific EP exemptions being granted to DEK are provided in the NRC staff's safety evaluation enclosed in NRC letter dated October 27, 2014 (ADAMS Accession No. ML14261A223). A. Authorized by Law The licensee has proposed exemptions from certain EP requirements in 10 CFR 50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV, that would allow DEK to revise the KPS Emergency Plan to reflect the permanently shutdown and defueled condition of the station. As stated above, in accordance with 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50. The NRC staff has determined that granting of the licensee's proposed exemptions will not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission's regulations. Therefore, the exemptions are authorized by law. B. No Undue Risk to Public Health and Safety As stated previously, DEK provided analyses that show the radiological consequences of design-basis accidents will not exceed the limits of the EPA PAGs at the exclusion area boundary. Therefore, offsite radiological emergency plans required under 10 CFR Part 50 are no longer needed for protection of the public beyond the exclusion area boundary based on the radiological consequences of design-basis accidents still possible at KPS. Although very unlikely, there are postulated beyond design-basis accidents that might result in significant offsite radiological releases. However, NUREG-1738 confirms that the risk of beyond design-basis accidents is greatly reduced at permanently shutdown and defueled reactors. The staff's analyses in NUREG-1738 concludes that the event sequences important to risk at permanently shutdown and defueled power reactors are limited to large earthquakes and cask drop events. For EP assessments, this is an important difference relative to operating power reactors where typically a large number of different sequences make significant contributions to risk. Per NUREG-1738, relaxation of offsite EP requirements under 10 CFR Part 50 a few months after shutdown resulted in only a small change in risk. The report further concludes that the change in risk due to relaxation of offsite EP requirements is small because the overall risk is low, and because even under current EP requirements for operating power reactors, EP was judged to have marginal impact on evacuation effectiveness in the severe earthquakes that dominate SFP risk. All other sequences including cask drops (for which offsite radiological emergency plans are expected to be more effective) are too low in likelihood to have a significant impact on risk. Therefore, granting exemptions eliminating the requirements of 10 CFR 50 to maintain offsite radiological emergency plans and reducing the scope of onsite emergency planning activities will not present an undue risk to the public health and safety. C. Consistent With the Common Defense and Security The requested exemptions by DEK only involve EP requirements under 10 CFR Part 50 and will allow DEK to revise the KPS Emergency Plan to reflect the permanently shutdown and defueled condition of the facility. Physical security measures at KPS are not affected by the requested EP exemptions. The discontinuation of offsite radiological emergency plans and the reduction in scope of the onsite emergency planning activities at KPS will not adversely affect DEK's ability to physically secure the site or protect special nuclear material. Therefore, the proposed exemptions are consistent with the common defense and security. D. Special Circumstances Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii), are present whenever application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule. The underlying purpose of 10 CFR 50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV, is to provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency, to establish plume exposure and ingestion pathway emergency planning zones for nuclear power plants, and to ensure that licensees maintain effective offsite and onsite radiological emergency plans. The standards and requirements in these regulations were developed by considering the risks associated with operation of a power reactor at its licensed full-power level. These risks include the potential for a reactor accident with offsite radiological dose consequences. As discussed previously, because KPS is permanently shutdown and defueled, there is no longer a risk of offsite radiological release from a design-basis accident and the risk of a significant offsite radiological release from a beyond design-basis accident is greatly reduced when compared to an operating power reactor. The NRC staff has confirmed the reduced risks at KPS by comparing the generic risk assumptions in the analyses in NUREG-1738 to site specific conditions at KPS and determined that the risk values in NUREG-1738 bound the risks presented by KPS. Furthermore, the staff has 
                        ( print page 65719)
                        recently concluded in NUREG-2161, “Consequence Study of a Beyond-Design-Basis Earthquake Affecting the Spent Fuel Pool for a U.S. Mark I Boiling Water Reactor,” dated September 2014 (ADAMS Accession No. ML14255A365), that, consistent with earlier research studies, SFPs are robust structures that are likely to withstand severe earthquakes without leaking cooling water and potentially uncovering the spent fuel. The NUREG-2161 study shows the likelihood of a radiological release from the spent fuel after the analyzed severe earthquake at the reference plant to be about one time in 10 million years or lower. The licensee has analyzed site-specific beyond design-basis accidents to determine the risk of a significant offsite radiological release. In one such analysis, DEK determined that if all the normal cooling systems used to cool the SFP were lost and not restored for the duration of the postulated accident, then as of September 20, 2014, the SFP at the KPS would take 120 hours before it would begin to boil and, due to the loss of SFP water level from the resulting boil off, it would take 26 days for the water inventory to lower to a level of three feet from the top of the fuel. Additionally, DEK analysis shows that as of October 30, 2014, in the event of a complete SFP drain down due to a loss of water inventory, assuming natural circulation of air through the spent fuel racks was available, then the peak fuel clad temperature would remain below 1049 °F (565 °C), the temperature at which incipient cladding failure may occur. Therefore, in this postulated accident, fuel cladding remains intact and an offsite radiological release would not take place. The only beyond design-basis accident analysis that reached a condition where a significant offsite release might occur involved a scenario where the SFP drained in such a way that all modes of cooling or heat transfer are assumed to be unavailable. This results in an adiabatic heat-up of the spent fuel. DEK analysis of this beyond design-basis accident shows that as of October 21, 2014, a minimum of 10 hours would be available between the time the fuel is uncovered (at which time adiabatic heat-up begins), until the fuel cladding reaches a temperature of 1652 °F (900 °C), the temperature associated with rapid cladding oxidation and the potential for a significant radiological release. Exemptions from the offsite EP requirements in 10 CFR 50 have previously been approved by the NRC when the site-specific analyses show that at least 10 hours is available following a loss of SFP coolant inventory accident with no air cooling (or other methods of removing decay heat) until cladding of the hottest fuel assembly reaches the zirconium rapid oxidation temperature. The staff concluded in its previously granted exemptions, as it does with the DEK requested EP exemptions, that if a minimum of 10 hours is available to initiate mitigative actions consistent with plant conditions, or if needed, for offsite authorities to implement protective actions using a CEMP approach, then offsite radiological emergency plans, required under 10 CFR Part 50, are not necessary at permanently shutdown and defueled power reactor licensees. Additionally, DEK committed to enhanced SFP makeup strategies in its letter to the NRC dated August 23, 2014 (ADAMS Accession No. ML13242A019). The multiple strategies for providing makeup to the SFP include: Using existing plant systems for inventory makeup; supplying water through hoses to a spool piece connection to the existing SFP piping; or using a diesel-driven portable pump to take suction from Lake Michigan and provide makeup or spray to the SFP. These strategies will continue to be required as a license condition. DEK further provides that the equipment needed to perform these actions will continue to be located onsite, and that the external makeup strategy (using a diesel driven portable pump) is capable of being deployed within 2 hours. Considering the very low probability of beyond design-basis accidents affecting the SFP, these diverse strategies provide defense-in-depth and time to provide makeup or spray to the SFP before the onset of any postulated offsite radiological release. For all the reasons stated above, the staff finds that the licensee's requested exemptions to meet the underlying purpose of all of the standards in 10 CFR 50.47(b), and requirements in 10 CFR 50.47(c)(2) and Appendix E, acceptably satisfy the special circumstances in 10 CFR 50.12(a)(2)(ii) in view of the greatly reduced risk of offsite radiological consequences associated with the permanently shutdown and defueled state of the KPS facility. The NRC staff has concluded that the exemptions being granted by this action will maintain an acceptable level of emergency preparedness at KPS and, if needed, that there is reasonable assurance that adequate offsite protective measures can and will be taken by State and local government agencies using a CEMP approach in the event of a radiological emergency at the KPS facility. Since the underlying purposes of the rules, as exempted, would continue to be achieved, even with the elimination of the requirements under 10 CFR Part 50 to maintain offsite radiological emergency plans and reduction in the scope of the onsite emergency planning activities at KPS, the special circumstances required by 10 CFR 50.12(a)(2)(ii) exist. E. Environmental Considerations In accordance with 10 CFR 51.31(a), the Commission has determined that the granting of this exemption will not have a significant effect on the quality of the human environment as discussed in the NRC staff's Finding of No Significant Impact and associated Environmental Assessment published October 7, 2014 (79 FR 60513). V. Conclusions Accordingly, the Commission has determined, pursuant to 10 CFR 50.12(a), that DEK's request for exemptions from certain EP requirements in 10 CFR 50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV, and as summarized in the table at the end of this document, are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. Also, special circumstances are present. Therefore, the Commission hereby grants DEK exemptions from certain EP requirements of 10 CFR 50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV, as discussed and evaluated in detail in the staff's safety evaluation dated October 27, 2014. The exemptions are effective as of October 30, 2014. Dated at Rockville, Maryland, this 27th day of October, 2014. For the Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
 
 
 IV—Table of Exemptions Granted to DEK
10 CFR 50.47
NRC staff basis for exemption10 CFR 50.47(b)
                                 The NRC is granting exemption from portions of the rule language that would otherwise require offsite emergency response plans
In the Statement of Considerations (SOC) for the final rule for emergency planning (EP) requirements for independent spent fuel storage installations (ISFSIs) and for monitor retrievable storage installations (MRS) (60 
                                **Federal Register**
                                 (FR) 32430; June 22, 1995), the Commission responded to comments concerning offsite EP for ISFSIs or an MRS and concluded that, “the offsite consequences of potential accidents at an ISFSI or a MRS would not warrant establishing Emergency Planning Zones [EPZ].”In a nuclear power reactor's permanently defueled state, the accident risks are more similar to an ISFSI or MRS than an operating nuclear power plant. The EP program would be similar to that required for an ISFSI under Section 72.32(a) of Title 10 of the 
                                *Code of Federal Regulations*
                                 (10 CFR) when fuel stored in the spent fuel pool (SFP) has more than 5 years of decay time and would not change substantially when all the fuel is transferred from the SFP to an onsite ISFSI. Exemptions from offsite EP requirements have previously been approved when the site-specific analyses show that at least 10 hours is available from a partial drain-down event where cooling of the spent fuel is not effective until the hottest fuel assembly reaches 900 °C. The technical basis that underlied the approval of the exemption request is based partly on the analysis of a time period that spent fuel stored in the SFP is unlikely to reach the zirconium ignition temperature in less than 10 hours. This time period is based on a heat-up calculation which uses several simplifying assumptions. Some of these assumptions are conservative (adiabatic conditions), while others are non-conservative (no oxidation below 900 °C). Weighing the conservatisms and non-conservatisms, the NRC staff judges that this calculation reasonably represents conditions which may occur in the event of an SFP accident. The staff concluded that if 10 hours were available to initiate mitigative actions, or if needed, offsite protective actions using a comprehensive emergency management plan (CEMP), formal offsite radiological emergency plans are not necessary for these permanently defueled nuclear power reactor licensees.As supported by the licensee's SFP analysis, the NRC staff believes an exemption to the requirements for formal offsite radiological emergency plans is justified for a zirconium fire scenario considering the low likelihood of this event together with time available to take mitigative or protective actions between the initiating event and before the onset of a postulated fire.The Dominion Energy Kewaunee, Inc. (DEK) analysis has demonstrated that 90 days after shutdown, the radiological consequences of design-basis accidents will not exceed the limits of the U.S. Environmental Protection Agency's (EPA) Protective Action Guidelines (PAGs) at the exclusion area boundary. These analyses also show that after the spent fuel has decayed for 17 months, for beyond-design-basis events where the SFP is drained, air cooling will prevent the fuel from reaching the lowest temperature where incipient cladding failure may occur (565 °C). In the event that air cooling is not possible, 10 hours is available to take mitigative or, if needed, offsite protective actions using a CEMP from the time the fuel is uncovered until it reaches the auto-ignition temperature of 900 °C.DEK has also furnished information on its SFP inventory makeup strategies for mitigating the loss of water inventory. The multiple strategies for providing makeup to the SPF include: using existing plant systems for inventory makeup; supplying water via hoses to a spool piece connection to the existing SFP piping; or using a diesel-driven portable pump to take suction from Lake Michigan and provide makeup or spray to the SFP. DEK also stated that the tools and equipment needed to perform these actions are located on site and that the external makeup strategy (using a diesel driven portable pump) was able to be deployed within 2 hours. DEK believes these diverse strategies provide defense-in-depth and ample time to provide makeup or spray to the SFP prior to the onset of zirconium cladding ignition when considering very low probability of beyond design-basis events affecting the SFP.10 CFR 50.47(b)(1)
Refer to basis for 10 CFR 50.47(b).The NRC is granting exemption from portions of the rule language that would otherwise require the need for Emergency Planning Zones (EPZs).( print page 65721)10 CFR 50.47(b)(3)
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the need for an Emergency Operations Facility
Decommissioning power reactors present a low likelihood of any credible accident resulting in a radiological release together with the time available to take mitigative or, if needed, offsite protective actions using a CEMP between the initiating event and before the onset of a postulated fire. As such, an emergency operations facility would not be required. The “nuclear island,” control room, or other onsite location can provide for the communication and coordination with offsite organizations for the level of support required.Also refer to basis for 10 CFR 50.47(b).10 CFR 50.47(b)(4)
                                 The NRC is granting exemption from portions of the rule language that would otherwise require reference to formal offsite radiological emergency response plans
Decommissioning power reactors present a low likelihood of any credible accident resulting in a radiological release together with the time available to take mitigative or if needed, offsite protective actions using a CEMP between the initiating event and before the onset of a postulated fire. As such, formal offsite radiological emergency response plans are not required.The Nuclear Energy Institute (NEI) document NEI 99-01, “Development of Emergency Action Levels for Non-Passive Reactors” (Revision 6), was found to be an acceptable method for development of emergency action levels (EALs) and was endorsed by the U.S. Nuclear Regulatory Commission (NRC) in a letter dated March 28, 2013 (ADAMS Accession No. ML12346A463). NEI 99-01 provides EALs for non-passive operating nuclear power reactors, permanently defueled reactors, and ISFSIs.Also refer to basis for 10 CFR 50.47(b).10 CFR 50.47(b)(5)
Refer to basis for 10 CFR 50.47(b).The NRC is granting exemption from portions of the rule language that would otherwise require early notification of the public and a means to provide instructions to the public within the plume exposure pathway Emergency Planning Zone.10 CFR 50.47(b)(6)
Refer to basis for 10 CFR 50.47(b).The NRC is granting exemption from portions of the rule language that would otherwise require prompt communications with the public.10 CFR 50.47(b)(7)
Refer to basis for 10 CFR 50.47(b).The NRC is granting exemption from portions of the rule language that would otherwise require information to be made available to the public on a periodic basis about how they will be notified and what their initial protective actions should be.10 CFR 50.47(b)(9)
Refer to basis for 10 CFR 50.47(b).The NRC is granting exemption from portions of the rule language that would otherwise require the capability for monitoring offsite consequences.10 CFR 50.47(b)(10)
                                 The NRC is granting exemption from portions of the rule language that would reduce the range of protective actions developed for emergency workers and the public. Consideration of evacuation, sheltering, or the use of potassium iodide will no longer be necessary. Evacuation times will no longer need to developed or updated. Protective actions for the ingestion exposure pathway EPZ will not need to be developed
In the unlikely event of an SFP accident, the iodine isotopes, which contribute to an off-site dose from an operating reactor accident, are not present, so potassium iodide distribution would no longer serve as an effective or necessary supplemental protective action.
                                 The Commission responded to comments in its SOC for the final rule for emergency planning requirements for ISFSIs and MRS facilities (60 FR 32435), and concluded that, “the offsite consequences of potential accidents at an ISFSI or an MRS would not warrant establishing Emergency Planning Zones.” Additionally, in the SOC for the final rule for EP requirements for ISFSIs and for MRS facilities (60 FR 32430), the Commission responded to comments concerning site-specific EP that includes evacuation of surrounding population for an ISFSI not at a reactor site, and concluded that, “The Commission does not agree that as a general matter emergency plans for an ISFSI must include evacuation planning.”Also refer to basis for 10 CFR 50.47(b).10 CFR 50.47(c)(2)
Refer to basis for 10 CFR 50.47(b)(10).The NRC is granting exemption from portions of the rule language that would otherwise require the establishment of a 10 mile radius plume exposure pathway EPZ and a 50 mile radius ingestion pathway EPZ.
 
 
 10 CFR Part 50, Appendix E, Section IV
NRC staff basis for exemption10 CFR Part 50, App. E, Section IV 1
                                 The NRC is granting exemption from portions of the rule language that would otherwise require onsite protective actions during hostile action
The EP Rule published in the 
                                **Federal Register**
                                 (76 FR 72560; November 23, 2011) amended certain requirements in 10 CFR Part 50. Among the changes, the definition of “hostile action” was added as an act directed toward a nuclear power plant or its personnel. This definition is based on the definition of “hostile action” provided in NRC Bulletin 2005-02, “Emergency Preparedness and Response Actions for Security-Based Events.” NRC Bulletin 2005-02 was not applicable to nuclear power reactors that have permanently ceased operations and have certified that fuel has been removed from the reactor vessel.The NRC excluded non-power reactors from the scope of “hostile action” at the time of the rulemaking because, as defined in 10 CFR 50.2, a non-power reactor is not considered a nuclear power reactor and a regulatory basis had not been developed to support the inclusion of non-power reactors within the scope of “hostile action.” Similarly, a decommissioning power reactor or an ISFSI is not a “nuclear reactor” as defined in 10 CFR Part 50. A decommissioning power reactor also has a low likelihood of a credible accident resulting in radiological releases requiring offsite protective measures. For all of these reasons, the staff concludes that a decommissioning power reactor is not a facility that falls within the scope of “hostile action.”Similarly, for security, risk insights can be used to determine which targets are important to protect against sabotage. A level of security commensurate with the consequences of a sabotage event is required and is evaluated on a site-specific basis. The severity of the consequences declines as fuel ages and, thereby, removes over time the underlying concern that a sabotage attack could cause offsite radiological consequences.Although, this analysis provides a justification for exempting KPS from “hostile action” related requirements, some EP requirements for security-based events are maintained. The classification of security-based events, notification of offsite authorities and coordination with offsite agencies under a CEMP concept are still required.10 CFR Part 50, App. E, Section IV 2
Refer to basis for 10 CFR 50.47(b)(10).The NRC is granting exemption from portions of the rule language concerning the evacuation time analyses within the plume exposure pathway EPZ for the licensee's initial application10 CFR Part 50, App. E, Section IV 3
                                 The NRC is granting exemption from portions of the rule language that would otherwise require use of NRC-approved evacuation time estimates (ETEs) and updates to State and local governments when developing protective action strategies
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.2.10 CFR Part 50, App. E, Section IV 4
                                 The NRC is granting exemption from portions of the rule language that would otherwise require licensees to develop evacuation time estimates based on the most recent census data and submit the ETE analysis to the NRC prior to providing it to State and local government for developing protective action strategies
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.2.10 CFR Part 50, App. E, Section IV 5
                                 The NRC is granting exemption from portions of the rule language that would otherwise require licensees to estimate the EPZ permanent resident population changes once a year between decennial censuses
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.2.10 CFR Part 50, App. E, Section IV 6
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to submit an updated ETE analysis to the NRC based on changes in the resident population that result in exceeding specific evacuation time increase criteria
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.2.10 CFR Part 50, App. E, Section IV A.1
                                 The NRC is granting exemption from the word “operating” in the requirement to describe the normal plant organization
Based on the permanently shutdown and defueled status of the reactor, a decommissioning reactor is not authorized to operate under 10 CFR 50.82(a). Because the licensee cannot operate the reactors, the licensee does not have a “plant operating organization.”10 CFR Part 50, App. E, Section IV A.3
                                 The NRC is granting exemption to the requirement to describe the licensee's headquarters personnel sent to the site to augment the onsite emergency response organization
The number of staff at decommissioning sites is generally small but is commensurate with the need to safely store spent fuel at the facility in a manner that is protective of public health and safety. Decommissioning sites typically have a level of emergency response that does not require response by the licensee's headquarters personnel.( print page 65723)10 CFR Part 50, App. E, Section IV A. 4
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to identify a position and function within its organization which will carry the responsibility for making offsite dose projections
Although, the likelihood of events that would result in doses in excess of the EPA PAGs to the public beyond the owner controlled area boundary based on the permanently shutdown and defueled status of the reactor is extremely low, the licensee still must be able to determine if a radiological release is occurring. If a release is occurring, then the licensee staff should promptly communicate that information to offsite authorities for their consideration. The offsite organizations are responsible for deciding what, if any, protective actions should be taken based on comprehensive emergency planning.10 CFR Part 50, App. E, Section IV A. 5
                                 The NRC is granting exemption from the requirement for the licensee to identify individuals with special qualifications for coping with emergencies
The number of staff at decommissioning sites is generally small but should be commensurate with the need to operate the facility in a manner that is protective of public health and safety.10 CFR Part 50, App. E, Section IV A.7
                                 The NRC is granting exemption from portions of the rule language that would otherwise require a description of the assistance expected from State, local, and Federal agencies for coping with a hostile action
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.1.10 CFR Part 50, App. E, Section IV A.8
                                 The NRC is granting exemption from the requirement to identify the State and local officials for ordering protective actions and evacuations
Offsite emergency measures are limited to support provided by local police, fire departments, and ambulance and hospital services, as appropriate. Due to the low probability of design basis accidents or other credible events to exceed the EPA PAGs, protective actions such as evacuation should not be required, but could be implemented at the discretion of offsite authorities using a CEMP.Also refer to basis for 10 CFR 50.47(b)(10).10 CFR Part 50, App. E, Section IV A.9
                                 The NRC is granting exemption from the requirement for the licensee to provide an analysis demonstrating that on-shift personnel are not assigned responsibilities that would prevent them from performing their assigned emergency plan functions
Responsibilities should be well defined in the emergency plan and procedures, regularly tested through drills and exercises audited and inspected by the licensee and the NRC. The duties of the onshift personnel at a decommissioning reactor facility are not as complicated and diverse as those for an operating power reactor.The NRC staff considered the similarity between the staffing levels at a permanently shutdown and defueled reactor and staffing levels at an operating power reactor site. The minimal systems and equipment needed to maintain the spent nuclear fuel in the SFP or in a dry cask storage system in a safe condition requires minimal personnel and is governed by Technical Specifications. In the EP final rule published in the 
                                **Federal Register**
                                 (76 FR 72560; November 23, 2011), the NRC concluded that the staffing analysis requirement was not necessary for non-power reactor licensees due to the small staffing levels required to operate the facility.The NRC staff also examined the actions required to mitigate the very low probability beyond design-basis events for the SFP. Additionally, DEK also furnished information on its SFP inventory makeup strategies for mitigating the loss of water inventory. The multiple strategies for providing makeup to the SFP include: using existing plant systems for inventory makeup; supplying water via hoses to a spool piece connection to the existing SFP piping; or using a diesel-driven portable pump to take suction from Lake Michigan and provide makeup or spray to the SFP. DEK further provided that the tools and equipment needed to perform these actions are located on site and the external makeup strategy (using a diesel driven portable pump) was demonstrated to be capable of being deployed within 2 hours, significantly less time than the 10 hours that would be available for ad hoc response. DEK believes, and the NRC staff agrees, that these diverse strategies provide defense-in-depth and ample time to provide makeup or spray to the SFP prior to the onset of zirconium cladding ignition when considering very low probability beyond design-basis events affecting the SFP.10 CFR Part 50, App. E, Section IV B.1
                                 The NRC is granting exemption from portions of the rule language that would otherwise require offsite emergency actions levels and offsite protective measures and associate offsite monitoring for the emergency conditions 
                                 In addition, the NRC is granting exemption from portions of the rule language that would otherwise require emergency action levels based on hostile action
NEI 99-01, “Development of Emergency Action levels for Non-Passive Reactors” (Revision 6), was found to be an acceptable method for development of EALs and was endorsed by the NRC in a letter dated March 28, 2013 (ADAMS Accession No. ML12346A463). No offsite protective actions are anticipated to be necessary, so classification above the alert level is no longer required, which is consistent with ISFSI facilities.
                                 Also refer to basis for 10 CFR Part 50, Appendix E, Section IV.1.( print page 65724)10 CFR Part 50, App. E, Section IV C.1
                                 The NRC is granting exemption from portions of the rule language that would otherwise require emergency actions levels based on operating reactor concerns, such as offsite radiation monitoring, pressure in containment, and the response of the emergency core cooling system. In addition, the NRC is striking language that would otherwise require offsite emergency action levels of a site area emergency and a general emergency
Containment parameters do not provide an indication of the conditions at a defueled facility and emergency core cooling systems are no longer required. Other indications, such as SFP level or temperature, can be used at sites where there is spent fuel in the SFPs.
                                 In the SOC for the final rule for EP requirements for ISFSIs and MRS) facilities (60 FR 32430), the Commission responded to comments concerning a general emergency at an ISFSI and an MRS, and concluded that, “. . . an essential element of a General Emergency is that a release can be reasonably expected to exceed EPA Protective Action Guidelines exposure levels off site for more than the immediate site area.”The probability of a condition reaching the level above an emergency classification of alert is very low. In the event of an accident at a defueled facility that meets the conditions for relaxation of EP requirements, there will be available time for event mitigation and, if necessary, implementation of offsite protective actions using a CEMP.NEI 99-01, “Development of Emergency Action levels for Non-Passive Reactors,” (Revision 6) was found to be an acceptable method for development of EALs and was endorsed by the NRC in a letter dated March 28, 2013 (ADAMS Accession No. ML12346A463). No offsite protective actions are anticipated to be necessary, so classification above the alert level is no longer required.10 CFR Part 50, App. E, Section IV C.2
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to assess, classify, and declare an emergency condition within 15 minutes
In the EP rule published in the 
                                **Federal Register**
                                 (76 FR 72560), non-power reactor licensees were not required to assess, classify and declare an emergency condition within 15 minutes. An SFP and an ISFSI are also not nuclear power reactors as defined in the NRC's regulations. A decommissioning power reactor has a low likelihood of a credible accident resulting in radiological releases requiring offsite protective measures. For these reasons, the NRC staff concludes that a decommissioning power reactor should not be required to assess, classify and declare an emergency condition within 15 minutes.10 CFR Part 50, App. E, Section IV D.1
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to reach agreement with local, State, and Federal officials and agencies for prompt notification of protective measures or evacuations and the associated titles of officials to be notified for each agency within the EPZs
Refer to basis for 10 CFR 50.47(b) and 10 CFR 50.47(b)(10).10 CFR Part 50, App. E, Section IV D.2
                                 The NRC is granting exemption from the requirement for the licensee to annually disseminate general information on emergency planning and evacuations within the plume exposure pathway EPZ. The need for signage or other measure to address transient populations is also being struck
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.D.1.10 CFR Part 50, App. E, Section IV D.3
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to have the capability to make notifications to State and local government agencies within 15 minutes of declaring an emergency
While the capability needs to exist for the notification of offsite government agencies within a specified time period, previous exemptions have allowed for extending the State and local government agencies' notification time up to 60 minutes based on the site-specific justification provided.
                                 DEK's exemption request provides that the KPS will make notifications to the State of Wisconsin, to the local county (Kewaunee) and the NRC within 60 minutes of declaration of an event. In the permanently defueled condition of the reactor, the rapidly developing scenarios associated with events initiated during reactor power operation are no longer credible.Also refer to basis for 10 CFR 50.47(b) and 10 CFR 50.47(b)(10).10 CFR Part 50, App. E, Section IV D.4
                                 The NRC is granting exemption from the requirement for the licensee to obtain FEMA approval of its backup alert and notification capability
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.D.3 regarding the alert and notification system requirements.10 CFR Part 50, App. E, Section IV E.8.a.(i)
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to have an onsite technical support center and emergency operations facility.
Due to the low probability of design-basis accidents or other credible events to exceed the EPA PAGs at the site boundary, the available time for event mitigation at a decommissioning reactor and, if needed, to implement offsite protective actions using a CEMP, an emergency operations facility (EOF) would not be required to support offsite agency response. Onsite actions may be directed from the control room or other location, without the requirements imposed on a technical support center (TSC).( print page 65725)10 CFR Part 50, App. E, Section IV E.8.a.(ii)
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to have an onsite operational support center
NUREG-0696, “Functional Criteria for Emergency Response Facilities,” provides that the operational support center (OSC) is an onsite area separate from the control room and the TSC where licensee operations support personnel will assemble in an emergency. For a decommissioning power reactor, an OSC is no longer required to meet its original purpose of an assembly area for plant logistical support during an emergency. The OSC function can be incorporated into another facility.10 CFR Part 50, App. E, Section IV E.8.b. and subpart Sections IV E.8.b.(1)-E.8.b.(5)
Refer to basis for 10 CFR 50.47(b)(3).The NRC is granting exemption from the requirements related to an offsite emergency operations facility location, space and size, communications capability, access to plant data and radiological information, and access to coping and office supplies.10 CFR Part 50, App. E, Section IV E.8.c. and Sections IV E.8.c.(1)-E.8.c.(3)
Refer to basis for 10 CFR 50.47(b)(3).The NRC is granting exemption from the requirements to have an emergency operations facility with the capabilities to obtain and display plant data and radiological information; the capability to analyze technical information and provide briefings; and the capability to support events occurring at more than one site (if the emergency operations center supports more than one site).10 CFR Part 50, App. E, Section IV E.8.d
                                 The NRC is granting exemption from the requirements to have an alternate facility that would be accessible even if the site is under threat of or experiencing hostile action, to function as a staging area for augmentation of emergency response staff
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.1 regarding hostile action.10 CFR Part 50, App. E, Section IV E.8.e
Refer to basis for 10 CFR 50.47(b)(3).The NRC is granting exemption from the requirement regarding the need for the licensee to comply with paragraph 8.b of this section10 CFR Part 50, App. E, Section IV E.9.a
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to have communications with State and local governments that are within the plume exposure pathway EPZ (which is no longer required by the exemption granted to 10 CFR 50.47(b)(10)) but are not contiguous with or bordering on the licensee site boundary
Refer to basis for 10 CFR 50.47(b) and 10 CFR 50.47(b)(10).
                                 Communications with State and local governments that are not contiguous with or bordering the site boundary will no longer be required. However, the contiguous State and the local governments in which the nuclear facility is located will still need to be informed of events and emergencies, so lines of communication must be maintained.10 CFR Part 50, App. E, Section IV E.9.c
                                 The NRC is granting exemption from the requirements for communication and testing provisions between the control room, the onsite technical support center, State/local emergency operations facilities, and field assessment teams
Because of the low probability of design-basis accidents or other credible events that would be expected to exceed the EPA PAGs and the available time for event mitigation and, if needed, implementation of offsite protective actions using a CEMP, there is no need for the TSC, EOF, or offsite field assessment teams.
                                 Also refer to justification for 10 CFR 50.47(b)(3). Communication with State and local emergency operation centers is maintained to coordinate assistance on site if required.10 CFR Part 50, App. E, Section IV E.9.d
                                 The NRC is granting exemption from portions of the rule language that would otherwise require provisions for communications from the control room, onsite technical support center, and emergency operations facility with NRC Headquarters and appropriate Regional Operations Center
The functions of the control room, EOF, TSC, and OSC may be combined into one or more locations due to the smaller facility staff and the greatly reduced required interaction with State and local emergency response facilities.
                                 Also refer to basis for 10 CFR 50.47(b).10 CFR Part 50, App. E, Section IV F.1 and Section IV F.1. v.iii
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to provide training and drills for the licensee's headquarters personnel, Civil Defense personnel, or local news media
Decommissioning power reactor sites typically have a level of emergency response that does not require additional response by the licensee's headquarters personnel, Civil Defense personnel, or local news media. Therefore, the NRC staff considers it reasonable to exempt the licensee from training and drill requirements for these personnel.10 CFR Part 50, App. E, Section IV F.2
                                 The NRC is granting exemption from portions of the rule language that would otherwise require testing of a public alert and notification system
Because of the low probability of design basis accidents or other credible events that would be expected to exceed the limits of EPA PAGs and the available time for event mitigation and offsite protective actions from a CEMP, the public alert and notification system will not be used and, therefore, requires no testing.Also refer to basis for 10 CFR 50.47(b).( print page 65726)10 CFR Part 50, App. E, Section IV F.2.a. and Section IV F.2.a.(i) through IV F.2.a.(iii)
                                 The NRC is granting exemption from the requirements for full participation exercises and the submittal of the associated exercise scenarios to the NRC
Due to the low probability of design basis accidents or other credible events that would be expected to exceed the limits of EPA PAGs, the available time for event mitigation and, if necessary, implementation of offsite protective actions using a CEMP, no formal offsite radiological emergency plans are required.
                                 The intent of submitting exercise scenarios at an operating power reactor site is to ensure that licensees utilize different scenarios in order to prevent the preconditioning of responders at power reactors. For decommissioning power reactor sites, there are limited events that could occur, and as such, the previously routine progression to general emergency in an operating power reactor site scenario is not applicable.The licensee would be exempt from 10 CFR. 
                                 Part 50, Appendix E, Section IV.F.2.a.(i)-(iii) because the licensee would be exempt from the umbrella provision of 10 CFR Part 50, Appendix E, Section IV.F.2.a.10 CFR Part 50, App. E, Section IV F.2.b
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to submit scenarios for its biennial exercises of its onsite emergency plan. In addition, the NRC is granting exemption from portions of the rule language that requires assessment of offsite releases, protective action decision making, and reference to the Technical Support Center, Operations Support Center, and the Emergency Operations Facility
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.F.2.a.
                                 The low probability of design basis accidents or other credible events that would exceed the EPA PAGs, the available time for event mitigation and, if necessary, implementation of offsite protective actions using a CEMP, render a TSC, OSC and EOF unnecessary. The principal functions required by regulation can be performed at an onsite location that does not meet the requirements of the TSC, OSC or EOF.10 CFR Part 50, App. E, Section IV F.2.c. and Sections IV F.2.c.(1) through F.2.c.(5)
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.F.2.a.The NRC is granting exemption from the requirements regarding the need for the licensee to exercise offsite plans biennially with full participation by each offsite authority having a role under the radiological response plan. The NRC is also granting exemptions from the conditions for conducting these exercises (including hostile action exercises) if two different licensees have facilities on the same site or on adjacent, contiguous sites, or share most of the elements defining co-located licensees.10 CFR Part 50, App. E, Section IV F.2.d
                                 The NRC is granting exemption from the requirements to obtain State participation in an ingestion pathway exercise and a hostile action exercise, with each State that has responsibilities, at least once per exercise cycle
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.2.10 CFR Part 50, App. E, Section IV F.2.e
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to allow participation exercise in licensee drills by any State and local Government in the plume exposure pathway EPZ when requested
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.2.10 CFR Part 50, App. E, Section IV F.2.f
                                 The NRC is granting exemption from portions of the rule language that would otherwise require FEMA to consult with the NRC on remedial exercises. The NRC is granting exemption from portions of the rule language that discuss the extent of State and local participation in remedial exercises
The U.S. Federal Emergency Management Agency is responsible for evaluating the adequacy of offsite response during an exercise. No action is expected from State or local government organizations in response to an event at a decommissioning power reactor site other than onsite firefighting, law enforcement and ambulance/medical services support. A memorandum of understanding should be in place for those services. Offsite response organizations will continue to take actions on a comprehensive emergency planning basis to protect the health and safety of the public as they would at any other industrial site.10 CFR Part 50, App. E, Section IV F.2.i
                                 The NRC is granting exemption from portions of the rule language that would otherwise require the licensee to drill and exercise scenarios that include a wide spectrum of radiological release events and hostile action
Due to the low probability of design basis accidents or other credible events to exceed the EPA PAGs, the available time for event mitigation and, if needed, implementation of offsite protective actions using a CEMP, the previously routine progression to general emergency in power reactor site scenarios is not applicable to a decommissioning site. Therefore, the licensee is not expected to demonstrate response to a wide spectrum of events.Also refer to basis for 10 CFR Part 50, Appendix E, Section IV.1 regarding hostile action.10 CFR Part 50, App. E, Section IV F.2.j
                                 The NRC is granting exemption from the requirements regarding the need for the licensee's emergency response organization to demonstrate proficiency in key skills in the principal functional areas of emergency response. Additionally, the NRC is granting exemption during an eight calendar year exercise cycle, from demonstrating proficiency in the key skills necessary to respond to such scenarios as hostile actions, unplanned minimal radiological release, § 50.54(hh)(2) implementation strategies, and scenarios involving rapid escalation to a Site Area Emergency or General Emergency
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.F.2.( print page 65727)10 CFR Part 50, App. E, Section IV I
                                 The NRC is granting exemption from the requirements regarding the need for the licensee to develop a range of protective action for onsite personnel during hostile actions
Refer to basis for 10 CFR Part 50, Appendix E, Section IV.E.8.d.


[FR Doc. 2014-26292 Filed 11-4-14; 8:45 am] BILLING CODE 7590-01-P