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OMB Control No: 3150-0011	ICR Reference No: 200806-3150-005
Status: Historical Inactive	Previous ICR Reference No: 200708-3150-021
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: 09/03/2008
Retrieve Notice of Action (NOA)	Date Received in OIRA: 06/30/2008
Terms of Clearance: In accordance with 5 CFR 1320, OMB is withholding approval at this time. Prior to publication of the final rule, the agency must submit to OMB a summary of all comments related to the information collection contained in the proposed rule and the agency response. The agency should clearly indicate any changes made to the information collection as a result of these comments.

	Inventory as of this Action	Requested	Previously Approved
Expiration Date	06/30/2010	06/30/2010	06/30/2010
Responses	45,517	0	45,517
Time Burden (Hours)	5,211,667	0	5,211,667
Cost Burden (Dollars)	255,446	0	255,446

Abstract: 10 CFR 50, "Alernate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events (10 CFR 50.61 and 50.61a)," Proposed Rule The NRC is proposing to amend its regulations to provide updated fracture toughness requirements for protection against pressurized thermal shock (PTS) events for pressurized water reactor (PWR) pressure vessels. The proposed rule would provide new PTS requirements based on updated analysis methods. This action is necessary because the existing requirements are based on unnecessarily conservative probablistic fracture mechanics analyses. This action would reduce regulatory burden for licensees, specifically those licensees that expect to exceed the existing requirements befor the expiration of their licenses. These new requirements would be voluntarily utilized by any PWR licensee as an alternative to complying with the existing requirements. The collections would be initially required for PWR licensees utilizing the requirements of 10 CFR 50.61a as a voluntary alternative to the requirements of 10 CFR 50.61. The collections would also be required, after voluntary implementation of the new 50,61a, when any change is made to the design or operation of the facility that effects the calculated RTmax-x value. The collections would also be required during the scheduled periodic ultrasonic examination of beltline welds.

Authorizing Statute(s): PL: Pub.L. 83 - 703 68 Stat. 919 Name of Law: Atomic Energy Act of 1954

Citations for New Statutory Requirements: None

Associated Rulemaking Information
RIN:	Stage of Rulemaking:	Federal Register Citation:	Date:
3150-AI01	Proposed rulemaking	72 FR 56275	10/03/2007

Federal Register Notices & Comments
Did the Agency receive public comments on this ICR? No

Number of Information Collection (IC) in this ICR: 1

IC Title	Form No.	Form Name
10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities

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 NRC is proposing to amend its regulations in 10 CFR Part 50.61, to provide updated fracture toughness requirements for protection against pressurized thermal shock (PTS) events for pressurized water reactor (PWR) pressure vessels. These amended regulations will be captured in the new 10 CFR 50.61a. The proposed rule would require new PTS requirements based on updated analysis methods. This action is being taken because the existing requirements are based on unnecessarily conservative probabilistic fracture mechanics analyses. This action would reduce a regulatory burden for licensees, specifically those licensees that expect to exceed the existing requirements before the expiration of their licenses. These new requirements would be voluntarily utilized by any PWR licensees as an alternative to complying with the existing requirements. The requirements in 10 CFR 50.16a will only apply to those licensees that voluntarily choose compliance with this section as an alternative to compliance with the requirements specified in 10 CFR 50.61. Of the 69 currently operating PWRs, the staff projects that eight reactor vessels could exceed the screening criteria specified in 10 CFR 50.61 during their extended (60 year) lifetimes. The NRC expects that each of these licensees will elect to apply the less stringent embrittlement correlations and screening criteria in 10 CFR 50.61a rather than applying the compensatory measures of 10 CFR 50.61(b)(3) through (b)(7). The NRC assumes that, subsequent to the effective date of the final rule, one operating reactor licensee per year will choose to comply with 10 CFR 50.61a for the following eight years. Thus, in the three years following the effective date of this rule, three operating reactors would be affected by the RT MAX-X assessment; none would perform the flux reduction analyses, and none would perform the reactor vessel thermal annealing. The estimated number of annual respondents is expected to be one and the number of annual responses to the NRC is expected to be two (one response for the RT MAX-X assessment and one response for the analysis of ASME BPV inservice ultrasonic testing results).

Annual Cost to Federal Government: $8,680

Does this IC contain surveys, censuses, or employ statistical methods? No

Is the Supporting Statement intended to be a Privacy Impact Assessment required by the E-Government Act of 2002? No

Is this ICR related to the Affordable Care Act [Pub. L. 111-148 & 111-152]? Uncollected

Is this ICR related to the Dodd-Frank Wall Street Reform and Consumer Protection Act, [Pub. L. 111-203]? Uncollected

Is this ICR related to the American Recovery and Reinvestment Act of 2009 (ARRA)? Uncollected

Is this ICR related to the Pandemic Response? Uncollected

Agency Contact: Veronica Rodriguez 301 415-3703 vmr1@nrc.gov

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