ML25280A013
| ML25280A013 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/03/2025 |
| From: | Marlayna Vaaler Doell Plant Licensing Branch III |
| To: | Schultheis M Holtec Palisades |
| References | |
| EPID L-2025-LLR-0073 | |
| Download: ML25280A013 (1) | |
Text
From:
Marlayna Doell To:
Michael Schultheis Cc:
k.steffic@holtec.com; k.miller1@holtec.com
Subject:
Request for Additional Information Re: Relief Request Number RR 5 RPV Vent Line Penetration Modifications
- L-2025-LLR-0073 Date:
Friday, October 3, 2025 1:46:00 PM Attachments:
- Mike,
By letter dated July 31, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession ML25212A032), Holtec Palisades, LLC requested alternative RR 5-10 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) requirements for a 100% surface examination coverage of the modified reactor vessel closure head vent line penetration weld due to hardship under Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2).
On September 9, 2025, the NRC staff sent the licensee DRAFT RAIs to ensure that the questions are understandable, the regulatory basis is clear, there is no proprietary information contained in the RAIs, and to determine if the information was previously docketed. On September 11, 2025, the NRC and the licensee held a clarification call to discuss the DRAFT RAIs.During the call, 30 days from the date of the call to respond to the RAIs was agreed upon.The attached is the final version of the RAIs. These RAIs will be put in ADAMS as a publicly available document.
- Thanks, Marlayna
~~~~~~~~~~~~~~~~~~~~~~~~~~~~
Decommissioning Project Manager U.S. Nuclear Regulatory Commission NRR/DORL/LPL3
Phone: 301.415.3178 Mobile: 440.668.7399 E-mail: marlayna.doell@nrc.gov Office Location: Fulltime Telework from Kingsport, Tennessee!
Mail Stop: T-5A10
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PALISADES - RELIEF REQUEST NUMBER RR 5-10 HOLTEC PALISADES, LLC PALISADES NUCLEAR PLANT DOCKET NO. 50-255
=
Background===
By letter dated July 31, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession ML25212A032), Holtec Palisades (the licensee) requested alternative RR 5-10 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) requirements of a 100% surface examination coverage of the modified reactor vessel closure head vent line penetration weld due to hardship under Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2). To complete its review, the NRC staff requests the following additional information.
Regulatory Basis 10 CFR 50.55a(z) Alternatives to codes and standards requirements 10 CFR 50.55a(g)(6)(ii)(D) Augmented ISI requirements for reactor vessel head Question 1 Confirm that the licensees proposed alternative RR 5-10 is only for the preservice and inservice surface examination coverage requirements to be changed from being, required to examine 1/4-inch beyond the Alloy 52M/152 weld-to-cladding interface shown in Figure 2 of ASME Code Case N-729-6, to instead only extend to point c of Figure 2 of RR 5-10.
- a. Verify the proposed alternative preservice and inservice surface examination coverage to point c of Figure 2 of RR 5-10 would bound the original Alloy 182/82 weld-to-cladding GF dimension of Figure 2 of ASME Code Case N7296.
Question 2 Figures 1 and 2 of RR 5-10 lack detailed dimensions of the modification. Provide a drawing of the modification including Alloy 52 weld metal deposit thickness ranges and coverage lengths over the Alloy 600 tube, Alloy 182/82 weld metal, and stainless steel cladding.
Question 3 Provide the following information regarding the non-destructive examinations performed on the weld and nozzle.
- a. In accordance with the requirements of the 2019 Edition of the ASME Code,Section III, NB-5140, was the adjacent base material for at least 1/2 inch (13 mm) on each side of the weld included in the examination?
- b. Did the Section III acceptance examination cover the 1/4-inch surface area beyond the Alloy 52M/152 weld-to-cladding interface?
- c. What is the current access restriction for performing a liquid dye penetrant examination to cover the surface from point c of Figure 2 of RR 5-10 through the 1/4-inch surface area beyond the Alloy 52M/152 weld-to-cladding interface (i.e., the "G-F" dimension provided in the Legend of Figure 2 of ASME Code Case N-729-6)?