10 CFR 52.99, Inspection During Construction

Inspection during construction

a

(a) Licensee schedule for completing inspections, tests, or analyses. The licensee shall submit to the NRC, no later than 1 year after issuance of the combined license or at the start of construction as defined at 10 CFR 50.10(a), whichever is later, its schedule for completing the inspections, tests, or analyses in the ITAAC. The licensee shall submit updates to the ITAAC schedules every 6 months thereafter and, within 1 year of its scheduled date for initial loading of fuel, the licensee shall submit updates to the ITAAC schedule every 30 days until the final notification is provided to the NRC under paragraph (c)(1) of this section.

b

(b) Licensee and applicant conduct of activities subject to ITAAC. With respect to activities subject to an ITAAC, an applicant for a combined license may proceed at its own risk with design and procurement activities, and a licensee may proceed at its own risk with design, procurement, construction, and preoperational activities, even though the NRC may not have found that any one of the prescribed acceptance criteria are met.

c

(c) Licensee notifications-(1) ITAAC closure notification. The licensee shall notify the NRC that prescribed inspections, tests, and analyses have been performed and that the prescribed acceptance criteria are met. The notification must contain sufficient information to demonstrate that the prescribed inspections, tests, and analyses have been performed and that the prescribed acceptance criteria are met.

(2) ITAAC post-closure notifications. Following the licensee’s ITAAC closure notifications under paragraph (c)(1) of this section until the Commission makes the finding under 10 CFR 52.103(g), the licensee shall notify the NRC, in a timely manner, of new information that materially alters the basis for determining that either inspections, tests, or analyses were performed as required, or that acceptance criteria are met. The notification must contain sufficient information to demonstrate that, notwithstanding the new information, the prescribed inspections, tests, or analyses have been performed as required, and the prescribed acceptance criteria are met.

(3) Uncompleted ITAAC notification. If the licensee has not provided, by the date 225 days before the scheduled date for initial loading of fuel, the notification required by paragraph (c)(1) of this section for all ITAAC, then the licensee shall notify the NRC that the prescribed inspections, tests, or analyses for all uncompleted ITAAC will be performed and that the prescribed acceptance criteria will be met prior to operation. The notification must be provided no later than the date 225 days before the scheduled date for initial loading of fuel, and must provide sufficient information to demonstrate that the prescribed inspections, tests, or analyses will be performed and the prescribed acceptance criteria for the uncompleted ITAAC will be met, including, but not limited to, a description of the specific procedures and analytical methods to be used for performing the prescribed inspections, tests, and analyses and determining that the prescribed acceptance criteria are met.

(4) All ITAAC complete notification. The licensee shall notify the NRC that all ITAAC are complete.

d

(d) Licensee determination of noncompliance with ITAAC. (1) In the event that an activity is subject to an ITAAC derived from a referenced standard design certification and the licensee has not demonstrated that the prescribed acceptance criteria are met, the licensee may take corrective actions to successfully complete that ITAAC or request an exemption from the standard design certification ITAAC, as applicable. A request for an exemption must also be accompanied by a request for a license amendment under 10 CFR 52.98(f).

(2) In the event that an activity is subject to an ITAAC not derived from a referenced standard design certification and the licensee has not demonstrated that the prescribed acceptance criteria are met, the licensee may take corrective actions to successfully complete that ITAAC or request a license amendment under 10 CFR 52.98(f).

e

(e) NRC inspection, publication of notices, and availability of licensee notifications. The NRC shall ensure that the prescribed inspections, tests, and analyses in the ITAAC are performed.

(1) At appropriate intervals until the last date for submission of requests for hearing under 10 CFR 52.103(a), the NRC shall publish notices in the Federal Register of the NRC staff’s determination of the successful completion of inspections, tests, and analyses.

(2) The NRC shall make publicly available the licensee notifications under paragraph (c) of this section. The NRC shall, no later than the date of publication of the notice of intended operation required by 10 CFR 52.103(a), make publicly available those licensee notifications under paragraph (c) of this section that have been submitted to the NRC at least seven (7) days before that notice.

Federal Register

72 FR 49536, Aug. 28, 2007; 72 FR 57447, Oct. 9, 2007; 77 FR 51892, Aug. 28, 2012]

External Links

NRC website 10 CFR 52.99

v t e Code of Federal Regulations
Title 10 Part 52 - LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS
10 CFR: 1 2 4 5 7 9 10 11 12 13 14 15 16 19 20 21 25 26 30 31 32 33 34 35 36 37 39 40 50 51 52 54 55 60 61 62 63 70 71 72 73 74 75 76 81 95 100 140 150 160 170 171
0, General Provisions, Scope; applicability of 10 CFR Chapter I provisions 1, Definitions 2, 3, Written communications 4, Deliberate misconduct 5, Employee protection 6, Completeness and accuracy of information 7, Specific exemptions 8, Combining licenses; elimination of repetition 9, Jurisdictional limits 10, Attacks and destructive acts 11, Information collection requirements: OMB approval 12, Early Site Permits, Scope of subpart 13, Relationship to other subparts 15, Filing of applications 16, Contents of applications; general information 17, Contents of applications; technical information 18, Standards for review of applications 21, Administrative review of applications; hearings 23, Referral to the Advisory Committee on Reactor Safeguards (ACRS) 24, Issuance of early site permit 25, Extent of activities permitted 26, Duration of permit 27, Limited work authorization after issuance of early site permit 28, Transfer of early site permit 29, Application for renewal 31, Criteria for renewal 33, Duration of renewal 35, Use of site for other purposes 39, Finality of early site permit determinations 41, Standard Design Certifications, Scope of subpart 43, Relationship to other subparts 45, Filing of applications 46, Contents of applications; general information 47, Contents of applications; technical information 48, Standards for review of applications 51, Administrative review of applications 53, Referral to the Advisory Committeeon Reactor Safeguards (ACRS) 54, Issuance of standard design certification 55, Duration of certification 57, Application for renewal 59, Criteria for renewal 61, Duration of renewal 63, Finality of standard design certifications 71, Combined Licenses, Scope of subpart 73, Relationship to other subparts 75, Filing of applications 77, Contents of applications; general information 79, Contents of applications; technical information in final safety analysis report 80, Contents of applications; additional technical information 81, Standards for review of applications 83, Finality of referenced NRC approvals; partial initial decision on site suitability 85, Administrative review of applications; hearings 87, Referral to the Advisory Committee on Reactor Safeguards (ACRS) 89, 91, Authorization to conduct limited work authorization activities 93, Exemptions and variances 97, Issuance of combined licenses 98, Finality of combined licenses; information requests 99, Inspection during construction 103, Operation under a combined license 104, Duration of combined license 105, Transfer of combined license 107, Application for renewal 109, Continuation of combined license 110, Termination of license 131, Standard Design Approvals, Scope of subpart 133, Relationship to other subparts 135, Filing of applications 136, Contents of applications; general information 137, Contents of applications; technical information 139, Standards for review of applications 141, Referral to the Advisory Committee on Reactor Safeguards (ACRS) 143, Staff approval of design 145, Finality of standard design approvals; information requests 147, Duration of design approval 151, Manufacturing Licenses, Scope of subpart 153, Relationship to other subparts 155, Filing of applications 156, Contents of applications; general information 157, Contents of applications; technical information in final safety analysis report 158, Contents of application; additional technical information 159, Standards for review of application 161, Reserved 163, Administrative review of applications; hearings 165, Referral to the Advisory Committee on Reactor Safeguards (ACRS) 167, Issuance of manufacturing license 169, 171, Finality of manufacturing licenses; information requests 173, Duration of manufacturing license 175, Transfer of manufacturing license 177, Application for renewal 179, Criteria for renewal 181, Duration of renewal 301, Enforcement, Violations 303, Criminal penalties Appendices: 10 CFR 52 Appendix B, Appendix B to Part 52-Design Certification Rule for the System 80+ Design 10 CFR 52 Appendix C, Appendix C to Part 52-Design Certification Rule for the Ap600 Design 10 CFR 52 Appendix D, Appendix D to Part 52-Design Certification Rule for the Ap1000 Design 10 CFR 52 Appendix E, Appendix E to Part 52-Design Certification Rule for the Esbwr Design 10 CFR 52 Appendix F, Appendices F Through M to Part 52 Reserved 10 CFR 52 Appendix N, Appendix N to Part 52-Standardization of Nuclear Power Plant Designs: Combined Licenses to Construct and Operate Nuclear Power Reactors of Identical Design At Multiple Sites

10 CFR 52.99, Inspection During Construction

a

b

c

d

e

Federal Register

External Links

Navigation menu

Search