ML24326A148
| ML24326A148 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/21/2024 |
| From: | Blake Purnell NRC/NRR/DORL/LPL2-2 |
| To: | Wiwel M Public Service Enterprise Group |
| References | |
| L-2024-LLA-0100 | |
| Download: ML24326A148 (4) | |
Text
From:
Blake Purnell Sent:
Thursday, November 21, 2024 9:53 AM To:
Wiwel, Michael Cc:
Audrey Klett; Hipo Gonzalez; Jurek, Shane; Licensing@pseg.com
Subject:
Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Use Optimized ZIRLO Fuel Rod Cladding Attachments:
RAI Salem ZIRLO LAR.pdf Michael Wiwel, By letter dated July 24, 2024 (Agencywide Documents Access and Management System Accession No. ML24206A100), PSEG Nuclear LLC submitted a license amendment request (LAR) for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. The proposed amendments would modify the Salem technical specifications to allow for the use of Optimized ZIRLO' fuel rod cladding material.
The NRC staff is reviewing the LAR and has determined that additional information is needed to complete the review. A response to the attached request for additional information is requested to be provided within 45 days of the date of this email. Please contact me if you have any questions.
Sincerely, Blake Purnell, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Docket Nos. 50-272 and 50-311 EPID L-2024-LLA-0100 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL1/BC NRR/DSS/STSB/BC NAME BPurnell HGonzalez SMehta DATE 11/21/2024 11/14/2024 11/14/2024
Hearing Identifier:
NRR_DRMA Email Number:
2646 Mail Envelope Properties (BLAPR09MB649717BEAD55C35D2941E761E6222)
Subject:
Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Use Optimized ZIRLO Fuel Rod Cladding Sent Date:
11/21/2024 9:53:07 AM Received Date:
11/21/2024 9:53:00 AM From:
Blake Purnell Created By:
Blake.Purnell@nrc.gov Recipients:
"Audrey Klett" <Audrey.Klett@nrc.gov>
Tracking Status: None "Hipo Gonzalez" <Hipolito.Gonzalez@nrc.gov>
Tracking Status: None "Jurek, Shane" <Shane.Jurek@pseg.com>
Tracking Status: None "Licensing@pseg.com" <Licensing@pseg.com>
Tracking Status: None "Wiwel, Michael" <Michael.Wiwel@pseg.com>
Tracking Status: None Post Office:
BLAPR09MB6497.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1120 11/21/2024 9:53:00 AM RAI Salem ZIRLO LAR.pdf 105580 Options Priority:
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REQUEST FOR ADDITIONAL INFORMATION PROPOSED AMENDMENT TO IMPLEMENT OPTIMIZED ZIRLO' FUEL ROD CLADDING PSEG NUCLEAR LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letter dated July 24, 2024 (Agencywide Documents Access and Management System Accession No. ML24206A100), PSEG Nuclear LLC (PSEG) submitted a license amendment request (LAR) for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. The proposed amendments would modify the Salem technical specifications (TSs) to allow for the use of Optimized ZIRLO' fuel rod cladding material.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing the application and has determined that the additional information below is needed for the staff to complete its review.
=
Background===
Optimized ZIRLO' is described in Westinghouse Topical Report WCAP-12610-P-A &
CENPD-404-P-A, Addendum 1-A, Optimized ZIRLO' (Addendum 1-A).1 Addendum 1-A includes the NRC staff conditions on the approval of Addendum 1. The LAR addresses the NRC staff conditions in Addendum 1-A, and states in several places that specific NRC staff conditions will be confirmed as part of the normal reload design process. The LAR implies that Addendum 1-A would need to be used when establishing core operating limits if Optimized ZIRLO' will be used in the reload core.
Technical Specification 6.9.1.9, Core Operating Limits Report (COLR), for Salem, Unit Nos. 1 and 2, specifies administrative controls for establishing core operating limits prior to each reload cycle, or prior to any remaining portion of a reload cycle. Technical Specification 6.9.1.9 requires the licensee to use the specific analytical methods listed in TS 6.9.1.9.b to determine the core operating limits. However, the LAR for Salem does not propose to add Addendum 1-A to the list of analytical methods for determining core operating limits in TS 6.9.1.9.
The LAR cites license amendments the NRC staff issued for three facilities as precedents to support the use of Optimized ZIRLO' at Salem. These facilities have TSs for the COLR that are similar to Salem TS 6.9.1.9. Among other changes, the cited license amendments for these facilities amended the TSs for the COLR to added Addendum 1-A to the list of analytical methods used to determine the core operating limits.
Request for Additional Information Identify whether a supplement to this LAR or a separate LAR will be submitted to revise TS 6.9.1.9 to add Addendum 1-A to the list of analytical methods used for determining core operating limits prior to the initial loading of fuel with Optimized ZIRLO' at the Salem units.
1 Transmittal letter and non-proprietary version are available under ADAMS Accession Nos. ML062080563 and ML062080569, respectively.
Alternatively, explain how the existing analytic methods in TS 6.9.1.9 can be used without modification to determine core operating limits for a reload that includes fuel with Optimized ZIRLO'. This explanation should include a discussion of why the NRC conditions in Addendum 1-A would not impact the establishment of the core operating limits for the Salem units.