Similar Documents at Salem |
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Category:Letter
MONTHYEARIR 05000272/20240022024-07-30030 July 2024 Integrated Inspection Report 05000272/2024002 and 05000311/2024002 LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding2024-07-24024 July 2024 Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding ML24145A1772024-07-15015 July 2024 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary IR 05000272/20245012024-06-12012 June 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24099A1572024-05-29029 May 2024 Issuance of Amendment Nos. 348 and 330 Permanent Extension of Type a and Type C Containment Leak Rate Test Frequencies ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response IR 05000272/20240102024-05-16016 May 2024 Fire Protection Team Inspection Report 05000272/2024010 and 05000311/2024010 IR 05000272/20240012024-05-0707 May 2024 Integrated Inspection Report 05000272/2024001 and 05000311/2024001 LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage2024-05-0606 May 2024 Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - 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Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership 2024-07-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Robert Braun President and Chief Nuclear Officer PSEG Nuclear LLC -N09 P.O. Box 236 Hancocks Bridge, NJ 08038 July 13, 2015
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR THE SPRING 2014 REFUELING OUTAGE 20 (TAC NO. MF5117)
Dear Mr. Braun:
By letters dated October 30, 2014, and May 21, 2015 (Agencywide Documents Access and Management System Accession Nos. ML 14303A032 and ML 15141A 117, respectively), PSEG Nuclear LLC (PSEG), submitted information summarizing the results of the spring 2014 steam generator tube inspections performed at Salem Nuclear Generating Station (Salem), Unit No. 2. These inspections were performed during Refueling Outage 20. This information was submitted in accordance with Salem, Unit No. 2, Technical Specification (TS) 6.9.1.10, "Steam Generator Tube Inspection Report." The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of your submittals, as documented in the enclosed evaluation.
The NRC staff concludes that PSEG has provided the information required by the TSs and that no additional followup is required at this time. This completes the NRC staff's efforts for TAC No. MF5117. If you have any questions, please contact me at 301-415-1603 or Carleen.Parker@nrc.gov.
Docket No. 50-311
Enclosure:
Review of Report cc w/enclosure:
Distribution via Listserv Sin,rely, (;J--\ Carleen J.
reject Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSPECTION REPORT PERFORMED DURING REFUELING OUTAGE TWENTY PSEG NUCLEAR LLC SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 DOCKET NO. 50-311
1.0 INTRODUCTION
By letters dated October 30, 2014, and May 21, 2015 (Agencywide Documents Access and Management System Accession Nos. ML 14303A032 and ML 15141A117, respectively), PSEG Nuclear, LLC (the licensee) submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Salem Nuclear Generating Station (Salem), Unit No. 2. These inspections were performed during Refueling Outage (RFO) 20.
2.0 BACKGROUND
Salem, Unit No. 2, has four AREVA Model 61/19T replacement SGs, which were installed in May of 2008. Each SG contains 5,048 U-bend thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of 0.750 inches and a nominal wall thickness of 0.043 inches. During SG fabrication, the tubes were hydraulically expanded at both ends over the full depth of the tubesheet.
The tubesheet was drilled on a triangular pitch. The U-bends in rows 1 through 16 were stress-relieved after bending. Eight stainless steel (Type 410) support plates, which have broached trefoil holes, provide lateral tube support to the vertical section of the tubes, and three sets of stainless steel (Type 405M) anti-vibration bars support the U-bend section of the tubes. 3.0 EVALUATION The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.
After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comments and observations:
The nuts that were previously found loose and retightened during RFO 17 and the nuts that were inaccessible and left as-is were not inspected during RFO 20. According to the licensee, the nuts that were retightened in RFO 17 were not found to be loose in RFO 18; the nuts that Enclosure were left as-is remain bounded by the evaluations performed in RFO 17 and RFO 18, which determined that the conditions within the upper internals did not require re-examination as of RFO 20. Wear at the tube support plates was observed in the tube located in row 1, column 63, in three of the four SGs. All three of these tubes were stabilized and plugged. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications.
In addition, the NRC staff concludes that there are no technical issues that warrant followup action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Principal Contributor:
Andrew B. Johnson Date: July 13, 2015 Mr. Robert Braun President and Chief Nuclear Officer PSEG Nuclear LLC -N09 P.O. Box 236, N09 Hancocks Bridge, NJ 08038 July 13, 2015
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR THE SPRING 2014 REFUELING OUTAGE 20 (TAC NO. MF5117)
Dear Mr. Braun:
By letters dated October 30, 2014, and May 21, 2015 (Agencywide Documents Access and Management System Accession Nos. ML 14303A032 and ML 15141A117, respectively), PSEG Nuclear LLC (PSEG), submitted information summarizing the results of the spring 2014 steam generator tube inspections performed at Salem Nuclear Generating Station (Salem), Unit No. 2. These inspections were performed during Refueling Outage 20. This information was submitted in accordance with Salem, Unit No. 2, Technical Specification (TS) 6.9.1.10, "Steam Generator Tube Inspection Report." The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of your submittals, as documented in the enclosed evaluation.
The NRC staff concludes that PSEG has provided the information required by the TSs and that no additional followup is required at this time. This completes the NRC staff's efforts for TAC No. MF5117. If you have any questions, please contact me at 301-415-1603 or Carleen.Parker@nrc.gov.
Docket No. 50-311
Enclosure:
Review of Report Sincerely, IRA/ Carleen J. Parker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/enclosure:
Distribution via Listserv DISTRIBUTION:
PUBLIC LPL 1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrLALRonewicz Resource RidsNrrPMSalem Resource AJohnson, NRR RidsRgn1 Mail Center Resource RidsACRS_MailCTR Resource RidsNrrDeEsgb Resource ADAMS A ccess1on N ML15173A186 o.: *b >Y memo OFFICE LPL 1-2/PM LPL 1-2/LA ESGB/BC* NAME CParker LRonewicz GKulesa DATE 6/22/15 6/23/15 6/4/15 OFFICIAL RECORD COPY AHuynh, NRR KKarwoski, NRR GKulesa, NRR RidsNrrDorlDpr Resource LPL 1-2/BC LPL 1-2/PM DBroaddus CParker 7/10/15 7/13/15