ML25255A067
| ML25255A067 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/12/2025 |
| From: | Audrey Klett NRC/NRR/DORL/LPL1 |
| To: | Jurak S Public Service Enterprise Group |
| Williams, S | |
| References | |
| EPID L-2025-LRO-0032 2R27 SGTIR | |
| Download: ML25255A067 (1) | |
Text
From:
Audrey Klett To:
Jurek, Shane
Subject:
NRC Request for Additional Information for Salem 2R27 SGTIR (L-2025-LRO-0032)
Date:
Friday, September 12, 2025 8:33:00 AM Attachments:
Salem 2R27 SGTIR RAI (L-2025-LRO-0032).docx Licensee: PSEG Nuclear LLC Plant: Salem Generating Station, Unit 2 License: DPR-75 Docket: 50-311
- Shane, Please the attached for the subject RAI. Please let me know if you have any questions.
- Thanks,
Audrey Klett, Senior Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Plant Licensing Branch 1 301-415-0489
REQUEST FOR ADDITIONAL INFORMATION SALEM, UNIT 2 (2R27) STEAM GENERATOR TUBE INSPECTION REPORT PSEG NUCLEAR LLC SALEM, UNIT 2 DOCKET NO. 50-311
Background
By letter dated May 15, 2025 (Agencywide Documents Access and Management System Accession No. ML25135A078), PSEG Nuclear LLC (the licensee) submitted letter LR-N25-0048, Steam Generator Tube Inspection Report - Twenty-seventh Refueling Outage, which summarized the results of the steam generator inspections performed at Salem Generating Station (Salem), Unit 2 during the twenty-seventh refueling outage (2R27) in fall 2024.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee in its letter and has determined that the staff needs the following additional information to complete its review. As discussed with licensee staff via emails on September 10 and 11, 2025, the NRC staff is requesting the licensee to respond to the request for additional information on or by October 15, 2025.
Regulatory Basis All pressurized water reactors have technical specifications (TS) according to § 50.36 of Title 10 of the Code of Federal Regulations that include a steam generator program with specific criteria for the structural and leakage integrity, repair, and inspection of steam generator tubes. Salem, Unit 2, TS 6.9.1.10, Steam Generator Tube Inspection Report, requires that a report be submitted within 180 days after the initial entry into hot shutdown (MODE 4) following completion of an inspection of the steam generators performed in accordance with TS 6.8.4.i, Steam Generator (SG) Program, which requires that a steam generator program be established and implemented to ensure steam generator tube integrity is maintained.
Question 1 Table 3 of attachment 1 to LR-N25-0048 provides the Salem, Unit 2 condition monitoring summary. For tube wear at the tube support plates (TSPs), the 2R22 to 2R27 operational assessment projected depth was 51.1 percent through-wall. The staff notes the maximum depth of tube wear at TSPs measured during 2R27 was 13 percent through-wall. The condition monitoring limit for TSP wear in Table 3 is shown as 47.5 percent through-wall, which is less than the conservative 2R22 operational assessment projected depth. The updated steam generator inspection report from 2R22 (ML21305A003) stated that a conservative structural depth for wear at TSPs was 52 percent through-wall. Discuss if the 47.5 percent through-wall condition monitoring limit shown in Table 3 is correct.
Question 2, section f of LR-N25-0048 provided the results of any steam generator secondary side inspections. Secondary side visual inspections included all steam drum components in all four steam generators. Discuss if any degradation was detected in the inspection of the feed ring, J-nozzles, moisture separator equipment, flow restrictor outlet nozzles, and other internal supports.
Question 3, section f of LR-N25-0048, provides a discussion of the secondary side foreign object search and retrieval (FOSAR) and indicates that no eddy current loose parts were
2 reported in 2R27 and that no loose part wear was identified on any tube. In addition, all foreign material remaining in the steam generators has been evaluated and determined to be acceptable for the next five cycles. This section also states, Appendix F contains a summary of the SSI [secondary-side inspection] findings (FOSAR). There is no Appendix F in the submittal.
Therefore, the NRC requests the licensee to indicate if this sentence was inadvertently included; otherwise, the NRC staff requests the licensee to submit Appendix F.
Question 4 Confirm whether the title of the graphic in Attachment 3 of LR-N25-0048 contains a typographical error and should state Model 61/19T instead of Model F.