View Information Collection Request (ICR) Package

OMB Control No: 3150-0011	ICR Reference No: 201002-3150-002
Status: Historical Active	Previous ICR Reference No: 200906-3150-005
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: Approved without change	Conclusion Date: 02/25/2010
Retrieve Notice of Action (NOA)	Date Received in OIRA: 02/25/2010
Terms of Clearance: In accordance with 5 CFR 1320, the information collection is approved for 3 years. Upon resubmission, the agency has committed to a rigorous reevaluation of their burden estimate, including reevaluating estimation through direct feedback from respondents. In particular, in relation to comments received, NRC has committed to evaluating the burden increase and any issues with duplication in information collection due to the requirement for embedded flaws violating the sizing criteria.

	Inventory as of this Action	Requested	Previously Approved
Expiration Date	12/31/2012	06/30/2012	06/30/2012
Responses	45,521	0	45,520
Time Burden (Hours)	5,218,590	0	5,218,227
Cost Burden (Dollars)	1,816,726	0	1,816,726

Abstract: 10 CFR 50,

Authorizing Statute(s): PL: Pub.L. 109 - 58 119 Stat 594 Name of Law: Energy Policy Act of 2005
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	Final or interim final rulemaking	75 FR 13	01/04/2010

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

ICR Summary of Burden

	Total Approved	Previously Approved	Change Due to Agency Discretion
Annual Number of Responses	45,521	45,520	1
Annual Time Burden (Hours)	5,218,590	5,218,227	363
Annual Cost Burden (Dollars)	1,816,726	1,816,726	0

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 mew 10 CFR 50.61a. The final 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 50.61a 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 PWR's, the staff projects that eight reactor vessels could exceed the screening criteria specified in 10 CFR 50.61 during their extended (60 year) lifetime. 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). Because it could take approximately up to 3 years to prepare the package for initial submittal to the NRC, the NRC estimates that only one licensee is expected to apply during the initial 3 year clearance period. The NRC assumes that, 3 years 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, one operating reactor would be affected by the RT max-x assessment and inservice testing and none would perform the flux reduction analyses nor the reactor vessel thermal annealing. Therefore, the estimated number of annual respondents is expected to be 0.333 per year and each respondent would provide two responses (i.e., one for the RT max-x assessment and one for the analysis of ASME Code inservice ultrasonic testing results).

Annual Cost to Federal Government: $498,610

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)? No

Is this ICR related to the Pandemic Response? Uncollected

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

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