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| NRC | RIN: 3150-AH29 | Publication ID: Fall 2011 |
| Title: Risk-Informed Changes to Loss-of-Coolant Accident Technical Requirements [NRC-2004-0006] | |
| Abstract: The proposed rule would amend the Commission's regulations to allow for a risk-informed alternative to the present loss-of-coolant accident break size. This rulemaking would address a petition for rulemaking submitted by the Nuclear Energy Institute (NEI) (PRM-50-75). The final rule was provided to the Commission on December 10, 2010, in SECY-10-0161. The NRC staff provided an initial draft final rule to the Advisory Committee on Reactor Safeguards (ACRS) on October 16, 2006. After reviewing the draft rule, the ACRS informed the Commission of numerous technical and policy concerns and recommended that the rule not be issued. The staff prepared a Commission paper (SECY-07-0082; May 16, 2007) to inform the Commission of the impact of the ACRS recommendations and to request guidance before proceeding with the rule. The Commission provided its guidance in a Staff Requirements Memorandum on August 10, 2007. On April 1, 2008, the staff provided an updated rule schedule to the Commission. In a meeting on August 6, 2008, selected NRC managers approved the staff's recommended resolution of the open issues related to the final rule. The staff prepared draft rule language incorporating the new positions into the rule and adding additional requirements for defense-in depth for pipe breaks larger than the transition break size. The OGC reviewed the revised rule language and recommended that portions of the rule be re-noticed to provide an opportunity for public comments on some of the new rule requirements. In a meeting on October 8, 2008, NRC managers decided to repropose the entire rule. On December 18, 2008, the EDO signed a memorandum informing the Commission that the staff will re-notice the section 50.46a rule for additional public comments in August 2009. The staff discussed the revised proposed rule with the ACRS on May 6-7, 2009, and then published the rule on August 10, 2009 (74 FR 40006). On September 24, 2009, in response to a request from NEI, the NRC extended the public comment period by 120 days to close on January 22, 2010 (74 FR 48667). The NRC evaluated the public comments and prepared draft final rule language, which was posted on Regulations.gov on May 12, 2010. A public meeting was held on June 4, 2010, to discuss resolution of public comments and the draft rule language. The staff discussed the rule with the ACRS in September and October of 2010. In its letter of October 20, 2010, the ACRS concluded that the rule was an acceptable alternative for operating reactors. The final rule was provided to the Commission on December 10, 2010 (SECY-10-0161). | |
| Agency: Nuclear Regulatory Commission(NRC) | Priority: Other Significant |
| RIN Status: Previously published in the Unified Agenda | Agenda Stage of Rulemaking: Final Rule Stage |
| Major: No | Unfunded Mandates: No |
| CFR Citation: 10 CFR 50 10 CFR 52 | |
| Legal Authority: 42 USC 2201 42 USC 5841 | |
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Legal Deadline:
None |
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Statement of Need: This rulemaking would codify alternative requirements for ECCS at nuclear power reactors by using risk information to refine ECCS requirements based on the likelihood of pipe breaks of various sizes. The rule would divide all coolant piping breaks currently considered in emergency core cooling requirements into two size groups: Breaks up to and including a "transition" size, and breaks larger than the transition size up to the largest pipe in the reactor coolant system. Selection of the transition size was based upon pipe break frequency estimates and associated uncertainties. Because pipe breaks in the smaller size group are considered more likely, they would be analyzed using existing criteria for ensuring that the reactor core stays cool during and after an accident. Larger breaks are considered less likely and would be analyzed with less conservative methods. Plants would still have to mitigate the effects of breaking the largest pipe and maintain core cooling. Under the draft final rule, power plant operators could make plant design changes that could enhance safety and/or provide operational benefits. The rule includes risk acceptance criteria to ensure that modified designs would continue to provide adequate protection of public health and safety. |
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Alternatives: The alternative is for the NRC not to issue these requirements. The alternative would not allow operators of nuclear power plants to have the increased design and operational flexibility that would be allowed by these risk-informed requirements. |
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Anticipated Costs and Benefits: There are no costs or benefits associated with this alternative rule for licensees who choose not to implement it. For the licensees who do choose to comply with the alternative requirements, if they request to increase power generation at their facilities and eliminate the need for fast-starting of emergency diesel generators, they would need to invest an estimated overall total of approximately $445 to $1,221 million (in 2008$ @ 3 percent discount rate) for plant modifications and staff support. Total estimated NRC cost associated with implementing the alternative requirements and reviewing licensees' design change requests at these facilities would be approximately $22 to $24 million (in 2008$ @ 3 percent discount rate). Substantial net benefits would result after subtracting both licensee and NRC costs from the benefits that licensees would obtain from making these plant modifications. The total cumulative net benefits are estimated to range from $279 to $2,876 million (in 2008$ @ 3 percent discount rate). |
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Risks: The rule would allow plant design and operational changes which could result in small but acceptable increases in risk. Specific acceptance criteria for risk increases are contained in the rule which limit overall risk increases to very small amounts. Allowable risk increases under this rule are consistent with the current risk increase guidelines specified in Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-informed Decisions on Plant-Specific Changes to the Licensing Basis." |
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Timetable:
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| Regulatory Flexibility Analysis Required: No | Government Levels Affected: None |
| Small Entities Affected: No | Federalism: No |
| Included in the Regulatory Plan: Yes | |
| RIN Data Printed in the FR: No | |
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Agency Contact: Richard F. Dudley Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone:301 415-1116 Email: richard.dudley@nrc.gov |
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