BW210048, Submittal of Analytical Evaluation in Accordance with ASME Code Section XI
| ML21194A025 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/07/2021 |
| From: | Keenan J Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21194A024 | List: |
| References | |
| BW210048 | |
| Download: ML21194A025 (2) | |
Text
Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 1, this document is decontrolled.
Exelon Generation Company, LLC Braidwood Station 35100 South Route 53, Suite 84 Braceville, IL 60407-9619 www.exeloncorp.com July 7, 2021 BW210048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Renewed Facility Operating License No. NPF-72 NRC Docket No. STN 50-456
Subject:
Submittal of Analytical Evaluation in Accordance with ASME Code Section XI
References:
- 1. Letter BW180116 from Marri Marchionda-Palmer (Exelon Generation Company, LLC) to U. S. NRC, Submittal of Analytical Evaluation in Accordance with ASME Code Section XI, dated December 12, 2018 On December 12, 2018, in accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2001 Edition through 2003 Addenda, IWB-3134, "Review by Authorities paragraph (b) Braidwood Station submitted an analytical evaluation associated with indications recorded in the reactor vessel head dome closure head ring weld inspection (Reference 1).
The Reference 1 letter transmitted the Westinghouse Electric Company LLC ("Westinghouse")
evaluation of the weld indications. The evaluation, based on ASME Section XI IWB-3600 requirements, demonstrated the structural integrity of the closure head for at least two fuel cycles of operation.
The reactor vessel head dome closure head ring weld was inspected, as required by the ASME Section XI Code, in the Spring 2021 Refueling Outage for Braidwood Unit 1. No changes were recorded from the 2018 inspection.
An additional evaluation of the recorded indications has been completed and is provided in to this transmittal. The evaluation has determined that the recorded indications are acceptable per IWB-3600 for at least 60 years of plant operation, which will cover the remaining design life of the plant.
July 7, 2021 U.S. Nuclear Regulatory Commission Page 2 contains Proprietary Information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 1, this document is decontrolled. contains information proprietary to Westinghouse. It is supported by an affidavit (Attachment 3) signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Nuclear Regulatory Commission and addresses with specificity the considerations listed in 10 CFR 2.390(a)(4).
Westinghouse and Exelon Generation Company, LLC (EGC) request that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390, "Public inspection, exemption, requests for withholding." Attachment 2 contains a nonproprietary version of Attachment 1 with brackets showing where the proprietary information has been deleted.
There are no regulatory commitments contained in this letter.
Please direct any questions you may have regarding this submittal to Mr. Kevin Lueshen, Regulatory Assurance Manager, at (815) 417-2800.
John Keenan Site Vice President Braidwood Station Attachments:
1.
Westinghouse WCAP-18596-P Revision 0, Braidwood Unit 1 Reactor Vessel Closure Head Dome-to-Ring Weld ASME Section XI Evaluation of As-Found Indications (Proprietary) 2.
Westinghouse WCAP-18596-NP Revision 0, Braidwood Unit 1 Reactor Vessel Closure Head Dome-to-Ring Weld ASME Section XI Evaluation of As-Found Indications (Non-Proprietary) 3.
Westinghouse Affidavit for Withholding Proprietary Information from Public Disclosure, CAW-20-5133 cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Braidwood Station NRR Project Manager - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety Keenan, John P.
Digitally signed by Keenan, John P.
DN: cn=Keenan, John P.
Date: 2021.07.06 12:41:14 -05'00'