ML21330A019

From kanterella
Jump to navigation Jump to search
Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 2
ML21330A019
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 11/23/2021
From: Angela Wu
NRC/NRR/DNRL/NLRP
To: Snider S
Duke Energy, Duke Energy Carolinas
Wu A
Shared Package
ML21330A017 List:
References
Download: ML21330A019 (2)


Text

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (ONS)

SUBSEQUENT LICENSE RENEWAL APPLICATION (SLRA)

SAFETY REVIEW REQUESTS FOR CONFIRMATION OF INFORMATION SET #2 Regulatory Basis:

Part 54 of Title 10 of the Code of Federal Regulations (10 CFR), Requirements for Renewal of Operating Licenses for Nuclear Power Plants, is designed to elicit application information that will enable the U.S. Nuclear Regulatory Commission (NRC) staff to perform an adequate safety review and the Commission to make the necessary findings. Reliability of application information is important and advanced by requirements that license applications be submitted in writing under oath or affirmation and that information provided to the NRC by a license renewal applicant or required to be maintained by NRC regulations be complete and accurate in all material respects. Information that must be submitted in writing under oath or affirmation includes the technical information required under 10 CFR 54.21(a) related to assessment of the aging effects on structures, systems, and components subject to an aging management review.

Thus, both the general submission requirements for license renewal applications and the specific technical application information requirements require that submission of information material to NRCs safety findings (see 10 CFR 54.29 standards for issuance of a renewed license) be submitted by an applicant as part of the application.

Background:

By letter dated June 7, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21158A193), as supplemented by letters dated October 22, 2021 (ADAMS Accession No. ML21295A035), October 28, 2021 (ADAMS Accession No. ML21302A208), and November 11, 2021 (ADAMS Accession No. ML21315A012), Duke Energy Carolinas, LLC (Duke Energy) submitted to the U.S. Nuclear Regulatory Commission (NRC or staff) an application to renew the Renewed Facility Operating License Nos. DPR-38, DPR-47, and DPR-55 for Oconee Nuclear Station (ONS), Units 1, 2, and 3. Duke Energy submitted the application pursuant to 10 CFR Parts 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, for subsequent license renewal.

Between July 26 and October 8, 2021, the NRC staff conducted audits of Duke Energys records to confirm information submitted in the ONS subsequent license renewal applicaiotn.

Request:

During the audit, the staff reviewed several documents that contain information which will likely be used in conclusions documented in the Safety Evaluation Report (SER). To the best of the staff's knowledge, this information is not on the docket. Any information used to reach a conclusion in the SER must be included on the docket by the applicant. We request that you submit confirmation that the information gathered from the documents and listed below is correct or provide the associated corrected information.

1

Requests for Confirmation of Information (RCIs)

RCI No. Description Duke Energys

Response

B2.1.30-A Based on the audit review of SLR-ONS-AMPR-XI.S3, ASME Section XI, Subsection IWF AMP Evaluation Report, ONS Units 1, 2, and 3, Revision 2, the staff noted from Section 3.2 that Oconee Nuclear Station (ONS) does not contain any Class MC component supports.

Confirm that ONS Units 1, 2, and 3 do not contain Class MC component supports.

B2.1.30-B Based on the audit review of SLR-ONS-AMPR-XI.S3, ASME Section XI, Subsection IWF AMP Evaluation Report, ONS Units 1, 2 and 3, Revision 2, the staff noted from Section 4.3 that plant-specific operating experience has not identified cracking or SCC for high strength bolting used at ONS.

Confirm that plant-specific operating experience to date has not identified cracking due to SCC for high strength bolting greater than 1 inch diameter within the scope of SLRA B2.1.30 AMP at ONS.

2