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Category:Letter
MONTHYEARL-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections 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 ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project 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 IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report IR 05000250/20240102024-05-0101 May 2024 Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 ML24087A1992024-04-0505 April 2024 Achp Section 106 Letter Re Notice of Availability of the Final Environmental Impact Statement for Turkey Point Units 3 & 4 Subsequent License Renewal Application ML24096A2142024-04-0505 April 2024 Ltr. to David Hill, Principal Chief, the Muscogee (Creek) Nation, Re., Section 106 Letters for Turkey Point ML24096A2162024-04-0505 April 2024 Ltr. to Marcellus Osceola, Chairman, Seminole Tribe of Florida, Re., Section 106 Letters for Turkey Point ML24087A1982024-04-0505 April 2024 Notice of Availability of the Final Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML24096A2152024-04-0505 April 2024 Ltr. to Lewis Johnson, Principal Chief, Seminole Nation of Oklahoma, Re., Section 106 Letters for Turkey Point ML24096A2182024-04-0505 April 2024 Ltr. to Stephanie Bryan, Tribal Chair, Poarch Band of Creek Indians, Re., Section 106 Letters for Turkey Point ML24087A2002024-04-0505 April 2024 Letter to Miami-Dade County Office of Historic Preservation Re Section 106 on Turkey Point Units 3 & 4 EIS ML24087A2012024-04-0505 April 2024 Letter to Talbert Cypress, Miccosukee Tribe of Indians of Florida; Re., Section 106 Letters for Turkey Point ML24072A2832024-04-0101 April 2024 Ltr to Dianne Strand-Notice of Avail.-Final Site-Specific Supp. 5a, 2nd Renewal to the GEIS for License Renewal L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections 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 ML24073A1712024-03-26026 March 2024 Correction of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML24072A2382024-03-20020 March 2024 Review of the Fall 2023 Steam Generator Tube Inspections During Refueling Outage No. 33 L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports 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 ML24064A1642024-03-11011 March 2024 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 IR 05000250/20244202024-03-11011 March 2024 – Security Baseline Inspection Report 05000250/2024420 and 05000251/2024420 - Final ML24058A1182024-03-0101 March 2024 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 L-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report IR 05000250/20230062024-02-28028 February 2024 Annual Assessment Letter for Turkey Point Units 3 & 4 - Report 05000250/2023006 and 05000251/2023006 L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation ML24051A1442024-02-20020 February 2024 NRC Response to Turkey Point Appeal of Initial Disputed Item 05000250,251-2024-01 2024-08-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 3, 2016 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P. 0. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
TURKEY POINT NUCLEAR GENERATING, UNITS 3 AND 4 - RESPONSE REGARDING PHASE 2 STAFFING SUBMITTALS ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 9.3 RELATED TO THE FUKUSHIMA DAl-ICHI NUCLEAR POWER PLANT ACCIDENT (CAC NOS.
MF7041 AND MF7042)
Dear Mr. Nazar:
By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 1O of the Code of Federal Regulations ( 10 CFR) Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter) regarding Recommendations 2.1 (seismic and flooding evaluations), 2.3 (seismic and flooding walkdowns), and 9.3 (emergency preparedness communication and staffing) of the Near-Term Task Force (NTTF) review of insights from the Fukushima Dai-ichi accident. With respect to Recommendation 9.3, Enclosure 5 to the NRC's letter requested licensees and holders of construction permits to assess their means to power communications equipment onsite and offsite during a prolonged station blackout (SBO) event and to perform a staffing assessment to determine the staff required to fill all necessary positions in response to a multi-unit event.
The 50.54(f) letter, in part, requested licensee responses pursuant to the provisions of 10 CFR 50.54(f) pertaining to onsite and augmented staff availability to implement the strategies discussed in the emergency plan and plant operating procedures, including new staff or functions resulting from the assessment, identified collateral du~ies, an implementation schedule to perform the assessments, identified modifications, and any changes that have been made or will be made to the emergency plan regarding on-shift or augmented staffing.
In addition, NTTF Recommendation 9.3 has a dependency on the implementation of NTTF Recommendation 4.2 (mitigating strategies). As a result of this dependency, licensees responded to the 50.54(f) letter in phases The Phase 1 staffing assessment requested licensees to evaluate their ability to respond to a multi-unit extended loss of alternating current (ac) power (ELAP) event utilizing existing processes and procedures. The licensee responses to the 50.54(f) letter for Phase 1 staffing assessments for multi-unit sites were received and evaluated by the NRC staff. The NRC staff issued acknowledgement letters to all licensees with multi-unit sites, with the exception of San Onofre Nuclear Generating Station, by April 28, 2014.
M. Nazar Licensees were also requested to submit a Phase 2 staffing assessment for NRG staff review, which provides an assessment of the staffing necessary to perform the functions related to the strategies developed in response to NTTF Recommendation 4.2 and the resulting NRG Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events [BDBEE]" (ADAMS Accession No. ML12054A736).
Licensees were requested to provide their Phase 2 staffing assessments to the NRG no later than four months prior to the beginning of their second refueling outage (as used in the context of NRG Order EA-12-049). By letter dated September 28, 2015 (ADAMS Accession No. ML15301A838), Florida Power & Light Company (the licensee) submitted its Phase 2 staffing assessment for Turkey Point Nuclear Generating Unit Nos. 3 and 4. This submittal also references a non-public (Safeguards Information) attachment submitted by separate letter on the same date (ADAMS Accession No. ML15280A010). The NRG staff requested clarification regarding the Safeguards portion of the Phase 2 staffing assessment. By letter dated January 20, 2016 (ADAMS Accession No. ML16028A105), the licensee submitted additional information as a supplement to the Safeguards submittal.
The NRG staff reviewed the licensee's Phase 2 staffing assessment and supplemental information in accordance with the assumptions and guidelines of Sections 2.2, 2.3, and 3 of the Nuclear Energy Institute (NEI) guidance document NEI 12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities" (ADAMS Accession No. ML12125A412), which was endorsed by the NRG staff by letter dated May 15, 2012 (ADAMS Accession No. ML12131A043). The NRG staff noted that the licensee assessed its current onsite minimum staffing levels to identify any enhancements needed to respond following a beyond-design-basis large-scale natural event, and to ensure that the strategies contained in the existing emergency plan and plant operating procedures, such as those used in response to a SBO, can be performed by the site staff. The licensee's assessment assumed that a large-scale natural event causes: (1) an ELAP, (2) all units on the site to be affected, and (3) access to the site to be impeded for a minimum of six hours. The licensee also assessed its capability to perform the site-specific functions related to the strategies developed in response to the resulting Order EA-12-049. The licensee conducted independent reviews and concluded, based on its staffing assessment, that the existing on-shift minimum staff is sufficient to implement the loss of all ac power, multi-unit event response strategies, including those strategies developed to support the requirements of Order EA-12-049, while supporting performance of the required emergency planning duties without unacceptable collateral duties.
The NRG staff reviewed the licensee's Phase 2 staffing submittal and confirmed that the licensee's existing emergency response resources, as described in its emergency plan, are sufficient to perform the required plant actions and emergency plan functions, and implement the multi-unit event response strategies that were developed in response to Order EA-12-049 without the assignment of collateral duties that would impact the performance of assigned emergency plan functions.
As a result, the NRG staff concludes that the licen?ee's Phase 2 staffing submittal adequately addresses the response strategies needed to respond to a BDBEE using its procedures and guidelines. The NRG staff will verify the implementation of the licensee's staffing capabilities through the inspection program.
M. Nazar If you have any questions regarding this letter, please contact Stephen Philpott at (301) 415-2365 or via email at Stephen.Philpott@nrc.gov.
Sincerely,
~. £t.:::
Orders Management Branch Branch Chief Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251 cc: Distribution via Listserv
ML16054A708 *via email OFFICE NRR/JLD/JOMB/PM NRR/JLD/LA NSIR/DPR/NRLB/BC* NRR/JLD/JOMB/BC NAME SPhilpott SLent ARivera MBrown DATE 2/26/16 2/24/16 2/29/16 3/3/2016