In accordance with 5 CFR 1320, the information collection is approved. Because the agency sought comments only on the changes associated with the regulation, the existing expiration date remains the same for this collection.
table that charts list comparision
Inventory as of this Action
Requested
Previously Approved
05/31/2022
05/31/2022
05/31/2022
43,617
0
43,618
3,710,882
0
3,710,960
272,062
0
272,062
THE APPENDIX H TO 10 CFR PART 50 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - FINAL RULE. The requirements for a reactor vessel material surveillance program are specified under appendix H to 10 CFR part 50. The NRC requires light-water nuclear power reactor licensees to implement this program when it cannot be shown that the end of design life neutron fluence for the reactor vessel is below certain criteria. This program monitors changes in the fracture toughness properties of the reactor vessel materials adjacent to the reactor core. It involves the testing of irradiated material specimens that are located in surveillance capsules in the reactor vessel. The surveillance test results are used to evaluate the changes in material fracture toughness and thereby assesses the integrity of the reactor vessel. Appendix H to 10 CFR part 50 requires that within one year of the date of the surveillance capsule withdrawal, a summary technical report be submitted to the NRC that contains the data required by ASTM E 185, and the results of all fracture toughness tests conducted on the beltline materials in the irradiated and unirradiated conditions, unless an extension is granted by the Director, Office of Nuclear Reactor Regulation. At that time this requirement became effective (48 FR 24008; July 26, 1983), there was still a limited amount of data from irradiated materials from which to estimate embrittlement trends of reactor vessels at nuclear power plants; thus, making it crucial for timely reporting of test results.' Licensees that participate in an integrated surveillance program have found it burdensome to meet this one-year requirement, due to the time needed for coordination among the multiple licensees participating in the program. A significant number of test specimens have been analyzed since 1983, the results of which support the reduced need for prompt reporting of the test results Based on this finding, the NRC determined that the reporting requirement in appendix H to 10 CFR part 50 should be revised. The final rule reduces this regulatory burden by extending the reporting period from 1 year to 18 months, with the objectives of eliminating the need for licensees to prepare and submit extension requests, and the use of NRC resources to review the requests. This revision has no effect on public health and safety. Licensees must maintain records and prepare reports to demonstrate their fulfillment of the regulatory requirements related to a reactor vessel material surveillance program. The information collection requirements under this program include: ⢠Maintenance of records of the test results from this program throughout the life of the reactor vessel. ⢠Reports of the information specified in ASTM E 185 82.
The final rule decreases the burden for 10 CFR Part 50 from 3,710,960 to 3,710,882 hours and decreases the responses from 43,618 to 43,617, a reduction of 78 hours and 1 response. The rule reduces burden by extending the periodicity for submitting the summary technical report under Appendix H, Section IV.A, to 10 CFR Part 50, from 1 year to 18 months. The objective of this action is to eliminate the need for licensees to prepare and submit extension requests, and the use of NRC resources to review these requests.
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:
(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;
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.
Reactor Vessel Materials Surveillance Program Final Rule OMB SS 12-4-2020.docx
10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities