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Category:Letter
MONTHYEARL-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report ML24291A2882024-10-24024 October 2024 Westinghouse Topical Report - Request for Withholding Information from Public Disclosure L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24276A2302024-10-16016 October 2024 Westinghouse Topical Report – Request for Withholding Information from Public Disclosure ML24289A2372024-10-15015 October 2024 Transmittal of Revision 1 Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles IR 05000250/20243012024-10-0303 October 2024 NRC Operator License Examination Report 05000250/2024301 and 05000251/2024301 L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24269A1292024-09-24024 September 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24260A2262024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-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 IR 05000250/20240112024-08-0606 August 2024 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011 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 05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications 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-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update 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 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 ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure 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 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 05000250/LER-2024-002, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications ML24096A2142024-04-0505 April 2024 Ltr. to David Hill, Principal Chief, the Muscogee (Creek) Nation, Re., Section 106 Letters for Turkey Point 2024-09-25
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 4,2012 Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 SUB..IECT: TURKEY POINT UNITS 3 AND 4 - NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 LICENSE AMENDMENT APPLICATION ONLINE REFERENCE PORTAL
Dear Mr. Nazar:
By letter dated June 23, 2011, Florida Power & Light Company (the licensee) provided submittal dates for license amendment application incorporating National Fire Protection Association Standard (NFPA) 805 for Turkey Point, Units 3 and 4.
To improve the efficiency of the U.S. Nuclear Regulatory Commission (NRC) reviews, the licensees' representatives and the NRC staff have discussed the use of an online reference portal that would allow the NRC staff and contractors limited read-only access to the basis documents and other reference materials cited in the applications. The online reference portal would allow the NRC staff to audit basis documents to determine whether the information included in the documents support the application. Documents identified as necessary for analysis of the application will be identified by the NRC staff. The licensee will be formally requested to submit those documents on the NRC docket. Use of the online reference portal is acceptable as long as the following conditions are met:
- The online reference portal will be password-protected and passwords will be assigned to those directly involved in the review on a need-to-know basis;
- The online reference portal will be sufficiently secure to prevent staff from printing, saving, or downloading any documents; and
- Conditions of use of the online reference portal will be displayed on the log-in screen and will require concurrence by each user.
The NRC staff would like to request that the portal be populated with the documents listed in the enclosure to this letter when the NFPA 805 license amendment request (LAR) is submitted to the NRC. This will help with the preparation for the site audits and increase effectiveness of the review prior to the audit. Once the NRC accepts the LAR for review, it would be helpful if the portal is ready for immediate access to the NRC staff. Therefore, we request that you send the information to access the portal, such as username and password, immediately after the LAR has been accepted by the NRC.
M. Nazar -2 The conditions associated with the online reference portal must be maintained throughout the duration of the review process. Please provide written confirmation that the licensee agrees to the terms and conditions set forth in this letter.
Please send the information requested in this letter to me. Should you have any questions regarding NFPA 805 portal, please contact Ms. Leslie Fields, Senior Project Engineer, at 301-415-1186, or via email at leslie.fields@nrc.gov.
ason C. Paige, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251 cc w/encl: Distribution via ListServ
GENERIC LIST OF SHAREPOINT PORTAL REQUESTED DOCUMENTS FOR NFPA 805
- 1. National Fire Protection Association (NFPA) Code Deviations and Justifications
- 2. All applicable Probabilistic Risk Assessment (PRA) Peer Review Reports
- 3. All site calculations reference in the License Amendment Request (LAR)
- 4. Credited Fire Protection (FP) System and Feature Drawings
- a. Layout Drawings: fire barriers, installed fire detection and suppression systems, fire areas, fire zones, stairwells, fire doors, fire dampers, etc.
- b. Piping and Instrumentation Diagrams (P&IDs): FP Water System
- c. System Descriptions for Fire Suppression, Water Supply, and Detection (including incipient or very early warning fire detection (VEWFD))
- d. Hydraulic Calculations for Fire Service and Fire Suppression System Water Demand (if used to support non-fire water use in Title 10 of the Code of Federal Regulations, Section S0.48(c)(2)(vii))
- 5. Drawings related to systems credited in the Nuclear Safety Capability Assessment (NSCA) as well as those required to fully understand plant response:
- a. P&IDs: Reactor Coolant System, Main Steam, Main Feedwater, Circulating Water, Service Water, etc.
- b. Safe Shutdown/NSCA Logic Diagrams (if used)
- c. Electrical Distribution System One-Lines (alternating current (AC) and direct current (DC))
- 6. Those documents that fulfill the NFPA 805 requirement for "Design Basis Document (DBD)"
- a. Fire Area Calculations (e.g. Fire Safety Analyses, Fire Risk Analyses, Plant Change Evaluations, Fire Risk Evaluations, etc.)
- b. NSCA Calculation (Safe Shutdown/Circuit Analysis)
- c. Multiple Spurious Operation (MSO) Expert Panel Report
- d. Thermo-Hydraulic Analysis serving as the basis for Variance from Deterministic Requirements (VFDR) and recovery action (RA) timing
- e. Evaluation of Recovery Actions for feasibility
- f. Fire Hazards Analysis (FHA) (if separate from the fire area calculations)
- g. Non-Power Operation (NPO) Calculation(s)
- h. Radioactive Release Calculation(s)
- i. Pre-Fire Plans
- 7. Fire PRA Calculations
- a. Plant Boundary/Partitioning Methods and Results (TASK 1)
- b. Component Selection Calculation (TASK 2)
- c. Cable Selection and Circuit Analysis (TASKS 3, 9, and 10)
- d. Ignition Frequency Calculation (TASK 6)
Enclosure
-2
- e. Fire PRA Quantification Calculations (TASK S) including:
- i. Seismic Fire Interactions (TASK 13) Methodologies and results (including assumptions) ii. Screening Methodologies and Results (TASKS 4 and 7) (including assumptions) iii. Fire Risk Quantifications (TASK 14) Methodologies and Results (including assumptions) iv. Multi-Compartment Screening and Analysis
- v. Post-Fire Human Reliability Analysis (HRA) Methodologies and Results (including assumptions) (TASK 12) vi. Detailed proposed modification descriptions (Engineering Change Requests/Records) sufficient to comprehend potential impact/improvement to Fire PRA
- f. NFPA 80S Application Calculation (provides all the delta risk calculations for VFDRs)
- g. Control Room Risk Calculation
- h. Uncertainty and Sensitivity Calculations (TASK 1S)
- i. Fire Modeling Calculations used to support the Fire PRA (zone of influence (lOI), hot gas layer, bounding, detailed fire modeling, etc.)
ii Plant Specific Verification and Validation (V&V) Analysis iii. Non-Public V&V References (e.g.; Electric Power Research Institute (EPRI) Fire Modeling, Generic Treatment) iv. Fire Modeling Assumptions and Calculations performed to support target selection (e.g.; lOI, secondary fires, transient combustible/ignition sources) including those that deviate from NUREG/CR-68S0. (TASKS 8 and 11)
- 8. Fire Modeling used in the Fire Modeling Performance-Based Approach
- a. Plant Specific V&V Analysis performed
- b. Non-Public V&V References (e.g.; EPRI Fire Modeling, Generic Treatments ... )
- c. Fire Modeling Assumptions and Calculations performed to support Performance Based Evaluations (e.g.; lOI, secondary fires, transient combustible/ignition sources ... ) considered outside NUREG/CR 68S0 Assumptions and Parameters (TASKS 8 and 11)
- d. Hot Gas Layer (HGL) Determination Calculations (including Assumptions)
- 9. Fire Protection Program Manual
- 10. Fire Protection Quality Assurance (QA) Program (including FP Structure System Components (SSCs) and FP Features)
- 11. NFPA 80S Monitoring Program Calculations and Procedures
- 12. Technical Requirements Manual (TRM)
- 13. Updated Final Safety Analysis Report (UFSAR) Changes (including current UFSAR 9.S.1 Fire Protection and Section 7.4 Alternate Shutdownllnstrumentation)
M. Nazar -2 The conditions associated with the online reference portal must be maintained throughout the duration of the review process. Please provide written confirmation that the licensee agrees to the terms and conditions set forth in this letter.
Please send the information requested in this letter to me. Should you have any questions regarding NFPA 805 portal, please contact Ms. Leslie Fields, Senior Project Engineer, at 301-415-1186, or via email at leslie.fields@nrc.gov.
Sincerely, IRA!
Jason C. Paige, Project Manager Plant Licensing Branch 1/-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251 cc w/encl: Distribution via ListServ DISTRIBUTION:
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