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OMB Control No: 3150-0011	ICR Reference No: 201403-3150-004
Status: Historical Inactive	Previous ICR Reference No: 201208-3150-003
Agency/Subagency: NRC	Agency Tracking No:
Title: 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities
Type of Information Collection: Revision of a currently approved collection	Common Form ICR: No
Type of Review Request: Regular
OIRA Conclusion Action: Comment filed on proposed rule and continue	Conclusion Date: 06/13/2014
Retrieve Notice of Action (NOA)	Date Received in OIRA: 03/28/2014
Terms of Clearance: OMB files this comment in accordance with 5 CFR 1320.11(c). This OMB action is not an approval to conduct or sponsor an information collection under the Paperwork Reduction Act of 1995. If OMB has assigned this ICR a new OMB Control Number, the OMB Control Number will not appear in the active inventory. For future submissions of this information collection, reference the OMB Control Number provided. OMB is withholding approval at this time. Prior to publication of the final rule, the agency should provide a summary of any comments related to the information collection and their response, including any changes made to the ICR as a result of comments. In addition, the agency must enter the correct burden estimates. This action has no effect on any current approvals.

	Inventory as of this Action	Requested	Previously Approved
Expiration Date	10/31/2014	36 Months From Approved	10/31/2014
Responses	46,176	0	46,176
Time Burden (Hours)	4,488,602	0	4,488,602
Cost Burden (Dollars)	1,810,380	0	1,810,380

Abstract: PROPOSED RULE: Performance-Based Emergency Core Cooling Systems Cladding Acceptance Criteria. The NRC is proposing to amend its regulations to revise the acceptance criteria for the emergency core cooling system for light-water nuclear power reactors as currently required by 10 CFR part 50. The rule would establish a 5-year staged implementation approach to improve the efficiency and effectiveness of the migration to the new ECCS requirements. The vendors would also propose post-quench ductility limits by either selecting analytical limits provided in Figure 2 of draft regulatory guide DG-1263, "Establishing Analytical Limits for Zirconium-Based Alloy Cladding," using an NRC-approved experimental approach to obtain the post-quench ductility limits, or using an experimental approach developed by the vendor to obtain the post-quench ductility limits. Those ductility limits which are developed via an experimental method would be submitted to the NRC via a topical report for NRC approval. The DG-1262, "Testing for Post Quench Ductility," provides guidance on an acceptable testing approach for developing post-quench ductility. The DG-1263 provides a methodology for using test results, generated from DG-1262 or an alternate NRC-approved experimental approach, to establish and support a new cladding-specific analytical limit. The vendors would also obtain post-quench ductility analytical methods by either selecting analytical limits provided in a regulatory guide, using an NRC-approved experimental approach, or using an experimental approach developed by the vendor. Those PQD limits developed via an experimental method would be submitted to the NRC via a topical report. The vendors would also perform long-term cooling tests to determine the long-term cooling limits for each of the nine cladding alloys. In addition, vendors would perform initial breakaway testing. The licensees would report the initial breakaway results to the NRC via their license amendment request. Those licensees that meet the new requirements without new analyses or model revisions would complete any necessary engineering calculations, update their plant UFSAR, and provide a letter report to the NRC documenting compliance. Those licensees that would require new analyses or model revisions to demonstrate compliance would be required to submit a new LOCA analysis of record. The rule would also require licensees to conduct periodic breakaway testing, and include those results in the yearly ECCS report. Lastly, the rule would add a requirement to report errors in ECR to the NRC. This would be submitted within the same yearly ECCS report. The rule would include a provision allowing entities to use an alternative risk-informed approach to evaluate the effects of debris for long-term cooling. If an entity voluntarily chooses to use this approach, they would need to submit an application for NRC review and approval, report all errors and changes in their plant-specific PRA, and conduct periodic updates to their PRA.

Burden increases because of Program Change due to Agency Discretion: Yes

Burden Increase Due to: Changing Regulations

Burden decreases because of Program Change due to Agency Discretion: No

Burden Reduction Due to:

Short Statement: The current Part 50 burden is 46,176 responses and 4,488,602 hours. The proposed rule would increase this burden by a total of 290.33 responses and 61,130.95 hours (rounded to 290 responses and 61,131 hours), making the new Part 50 total 4,549,733 hours and 46,466 hours The proposed rule would revise ECCS acceptance criteria to reflect recent research findings which identified new embrittlement mechanisms for fuel rods with zirconium alloy cladding under loss-of-coolant accident (LOCA) conditions. This action is necessary to ensure an acceptable level of fuel rod cladding post-quench ductility (PQD) following a postulated loss-of-coolant accident, and thus to ensure the adequate protection of public health and safety. This burden is associated with one-time and recurring costs to include results of periodic breakaway testing in the yearly ECCS submittals required under the proposed rule's § 50.46c(m)(1) (current rule's § 50.46(a)(3)(ii)). This burden is justified in light of the safety importance of the proposed rule. The proposed rule adds a recordkeeping requirement to update the risk informed alternative. However, licensees will not begin to perform those updates until Year 6. As such, they are not calculated in this clearance period. Additionally, the proposed rule reduces the number of exemption requests filed under § 50.12. This results in an annual recordkeeping burden reduction). Overall, the proposed rule would result in a one-time annualized burden of 64,067 hours in the first three years to implement the changes that would revise the acceptance criteria for the emergency core cooling system for light-water nuclear power reactors. Due to the phased implementation schedule for the proposed rule, one-time burdens would continue to be incurred until year 6. The annual, recurring changes resulting from the proposed rule represent an overall reduction in burden of 2,936 hours annually. Following the implementation phase, the industry will see a reduced burden for ECCS requirements in 10 CFR 50.46c compared to the current requirements under 10 CFR 50.46.

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