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.
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