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Category:Letter
MONTHYEARIR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report ML24108A0632024-04-18018 April 2024 – Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report ML24093A2612024-04-0202 April 2024 – Investigation Summary, Office of Investigations Case Number 2-2023-005 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes ML24078A2622024-03-26026 March 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML24058A1572024-03-19019 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report IR 05000335/20230062024-02-28028 February 2024 Annual Assessment Letter for St Lucie Units 1 & 2 - Report 05000335/2023006 and 05000389/2023006 L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules IR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) IR 05000335/20230042024-01-24024 January 2024 – Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 2024-08-07
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Text
rch 18, 2014
SUBJECT:
ST. LUCIE PLANT, UNITS 1 AND 2; TARGET SET INSPECTION 05000335/2013201, 05000389/2013201
Dear Mr. Nazar:
On December 19, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your St. Lucie Plant, Units 1 and 2. On February 3, 2014, the NRC inspector discussed the results of this inspection with Charles Workman, Security Manager and other members of your staff. The inspector documented the results of this inspection in the enclosed inspection report.
The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.
Three NRC-identified findings of very low significance (i.e., Green as determined by the Baseline Security Significance Determination Process) were identified during this inspection.
These findings were determined to involve a violation of NRC requirements. The deficiencies were promptly corrected or compensated for and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspector left the site.
If you contest any non-cited violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Director, Office of Nuclear Security and Incident Response (NSIR); the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; the Branch Chief, Security Training and Support Branch, NSIR; and the NRC Resident Inspectors at St Lucie Plant, Units 1 and 2. If you disagree with the cross-cutting aspects assigned to the findings in this report, you should provide a response within 30 days of the date of this inspection report with the basis for your disagreement to the Director, NSIR, and the Branch Chief, Security Training and Support Branch, NSIR.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains security-related information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and security-related information is necessary to provide an acceptable response, please mark your entire response Security-Related Information-Withhold from Public Disclosure Under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA/
Michael Buckley, Acting Chief Security Training and Support Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos. 50-335, 50-389 License Nos. DPR-67, NPF-16 Enclosure: Inspection Report 05000335/2013201, 05000389/2013201 w/Attachments: Supplemental Information