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Category:Letter
MONTHYEARML24255A3092024-09-30030 September 2024 SLRA - Revised SE Letter 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 IR 05000335/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000335/2024011 and 05000389/2024011 IR 05000250/20243012024-09-18018 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 ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter 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 L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 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 IR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal 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-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report 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-2024-129, 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 IR 05000250/20240112024-08-0606 August 2024 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011 05000389/LER-2024-003, Unplanned Reactor Scram2024-08-0505 August 2024 Unplanned Reactor Scram 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-2024-089, 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-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage 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-2024-112, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request 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 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-2024-097, 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 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-2024-090, 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 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 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation 2024-09-09
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September 2, 2004 Mr. Ching Guey Florida Power & Light Co.
Mail Code ENG/JB 700 Universe Boulevard Juno Beach, FL 33408
SUBJECT:
TRANSMITTAL OF REVISION 1 SIGNIFICANCE DETERMINATION PROCESS RISK-INFORMED INSPECTION NOTEBOOK AND INFORMATION REQUEST FOR NEXT REVISION
Dear Mr. Guey:
On September 30, 2003, the NRC completed a two-year benchmarking activity for 71 Significance Determination Process (SDP) risk-informed inspection notebooks. All 71 notebooks were issued as revision 1, incorporating information obtained during the initial benchmarking visits. The NRC appreciates the support of each licensee in this resource intensive, first-of-a-kind effort which has greatly improved the quality of each SDP notebook to reflect the plant design-features, operational procedures and, in many cases, reduced unnecessary conservatism.
Over the course of this two year effort, insights were gained and it became apparent that these lessons learned would need to be captured in all of the notebooks, with additional effort needed for updating the notebooks that were benchmarked early in the process. It was also recognized that periodic maintenance would be required to achieve a reasonable level of accuracy as a screening tool, given changes in plant design, procedures, and revisions to the plant-specific probabilistic risk assessment (PRA) models since the original benchmarking visit.
In April of 2004, the NRC and its contractor Brookhaven National Laboratory (BNL) embarked on an SDP notebook enhancement/standardization effort for all 71 notebooks through a revision 2 process. Each revision 2 SDP notebook will contain a target set of equipment that is pre-solved in a manner similar to what was performed as part of the revision 1 benchmarking effort, in addition to capturing the lessons learned, and requesting information specific to gaps in the individual notebooks. The NRC estimates completion of the revision 2 SDP notebooks by June 30, 2005.
In order to achieve this milestone with minimal burden, the NRC requests that the plant-specific information for St. Lucie and Turkey Point specified on the enclosed CD be sent to the address provided below. The CD also contains the revision 1 SDP notebooks generated from the initial benchmarking visit. The NRC requests that your response to the plant-specific information be provided on a CD within 30 days of receipt of this request. In addition to the plant-specific requests, the NRC welcomes your comments on the revision 1 SDP notebooks.
C. Guey 2 Mailing address for response:
Michael Tschiltz, Chief Probabilistic Safety Assessment Branch MS: O10-H4 U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 The NRC staff is continuing to review the appropriate classification of the enclosed CD documents within the records management program considering changes in our practices following the events of September 11, 2001. Pending a final determination, the information request and the notebooks have been marked as Proprietary Information in accordance with Section 2.390(d) of Title 10 of the Code of Federal Regulations (10 CFR 2.390). Please control the document accordingly (i.e., treat the document as trade secrets and commercial or financial information that you considered privileged or confidential). We will inform you if the designation of the documents change as a result of our ongoing assessments.
If you have any questions regarding the request, please contact See-Meng Wong at 301-415-1125.
Sincerely,
/RA/
Michael Tschiltz, Chief Probabilistic Safety Assessment Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation Nuclear Regulatory Commission
Enclosure:
As stated
C. Guey 2 Mailing address for response:
Michael Tschiltz, Chief Probabilistic Safety Assessment Branch MS: O10-H4 U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 The NRC staff is continuing to review the appropriate classification of the enclosed CD documents within the records management program considering changes in our practices following the events of September 11, 2001. Pending a final determination, the information request and the notebooks have been marked as Proprietary Information in accordance with Section 2.390(d) of Title 10 of the Code of Federal Regulations (10 CFR 2.390). Please control the document accordingly (i.e., treat the document as trade secrets and commercial or financial information that you considered privileged or confidential). We will inform you if the designation of the documents change as a result of our ongoing assessments.
If you have any questions regarding the request, please contact See-Meng Wong at 301-415-1125.
Sincerely,
/RA/
Michael Tschiltz, Chief Probabilistic Safety Assessment Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation Nuclear Regulatory Commission
Enclosure:
As stated DISTRIBUTION PUBLIC (w/o enclosure)
Adams Accession No. ML042510227 NRR-106 OFFICE SPSB-B SPSB-B SPSB-B/SC SPSB/BC NAME TValentine RPerch MCaruso MTschiltz DATE 8/ 24 /04 8/ 28 /04 9/ 01 /04 9/ 02 /04 OFFICIAL RECORD COPY