10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities

Forms and Documents

Document Name	Status
10CFR50FractureToughnesSPRreganal070808.pdf Supplementary Document	2008-09-08
19CFR50FractureToughnessSPRss071608.doc Supporting Statement A	2008-09-08

IC Document Collections

IC ID	Document Title	Status
42740	10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities	Modified

ICR Details

OMB Control No: 3150-0011	ICR Reference No: 200809-3150-001
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: 11/03/2008
	Date Received in OIRA: 09/08/2008
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

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Abstract: 10 CFR 50, Alternate Fracture Toughness Requirements for Protection Against Thermal Shock Events, Supplemental Proposed Rule 10 CFR 50.61 and 50.61a) The NRC is proposing to amend its regulations to provide updated fracture toughness requirements for protection against PTS events for PWR pressure vessels. The supplemental 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 probabilistic fracture mechanics analyses. This action would reduce 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 utilized by licensees of currently operating PWRs as an alternative to complying with the existing requirements. The pressurized thermal shock (PTS) proposed rule was published in the Federal Register on October 3, 2007 (72 FR 56275). The NRC is issuing a supplemental proposed rule because it is considering the adoption of new provisions as an alternative to the provisions previously noticed in the Federal Register. This supplemental proposed rule is being issued to request stakeholders’ feedback on the modifications made to the rule language as a result of public comments received on the October 2007 publication. The information collection requirements previously issued have been updated with the information contained in this supporting statement. The NRC published the alternate PTS proposed rulemaking for public comment in the Federal Register on October 3, 2007 (72 FR 56275). The proposed rule provided an alternative to the current rule in 10 CFR 50.61, which further prompted the NRC to keep the current, mandatory requirements separate from the new requirements. As a result, the proposed rule retained the current requirements in 10 CFR 50.61 for PWR licensees choosing not to implement the less restrictive screening limits, and presented new requirements in 10 CFR 50.61a as a relaxation for PWR licensees. During the development of the PTS final rule, the NRC determined that several significant changes to the proposed rule language would be needed to adequately address stakeholders’ comments, including concerns related to the applicability of the rule. The NRC is considering the adoption of these provisions as an alternative to the provisions previously noticed in the Federal Register and wishes to notice these provisions for public comment. Because these modifications are significant changes to the proposed rule language on which external stakeholders did not have an opportunity to comment, the NRC concluded that obtaining stakeholder feedback on these provisions through the use of a supplemental proposed rule is appropriate. Consequently, the information collection requirements from the proposed rule have been updated in its entirety with the information collection requirements provided in this supporting statement.

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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

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Associated Rulemaking Information
RIN:	Stage of Rulemaking:	Federal Register Citation:	Date:
3150-AI01	Proposed rulemaking	73 FR 46557	08/11/2008

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Federal Register Notices & Comments

Did the Agency receive public comments on this ICR? No

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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

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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: 10 CFR 50, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events, Supplemental Proposed Rule 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).

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Annual Cost to Federal Government: $3,870

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

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Common Form ICR:  No

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On behalf of this Federal agency, I certify that the collection of information encompassed by this request complies with 5 CFR 1320.9 and the related provisions of 5 CFR 1320.8(b)(3).

The following is a summary of the topics, regarding the proposed collection of information, that the certification covers:

(a) It is necessary for the proper performance of agency functions;

(b) It avoids unnecessary duplication;

(c) It reduces burden on small entities;

(d) It uses plain, coherent, and unambiguous language that is understandable to respondents;

(e) Its implementation will be consistent and compatible with current reporting and recordkeeping practices;

(f) It indicates the retention periods for recordkeeping requirements;

(g) It informs respondents of the information called for under 5 CFR 1320.8 (b)(3) about:

(i) Why the information is being collected;

(ii) Use of information;

(iii) Burden estimate;

(iv) Nature of response (voluntary, required for a benefit, or mandatory);

(v) Nature and extent of confidentiality; and

(vi) Need to display currently valid OMB control number;

(h) It was developed by an office that has planned and allocated resources for the efficient and effective management and use of the information to be collected.

(i) It uses effective and efficient statistical survey methodology (if applicable); and

(j) It makes appropriate use of information technology.

If you are unable to certify compliance with any of these provisions, identify the item by leaving the box unchecked and explain the reason in the Supporting Statement.

Certification Date: 09/08/2008

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