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MONTHYEARML15147A5912015-06-0101 June 2015 Nuclear Regulatory Commission Plan for the Audit of Florida Power and Light Company'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1-Flooding for St. Lucie Plant, Units 1 and 2 Project stage: Other ML15224B4492015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation Project stage: Other ML15236A0762015-09-0303 September 2015 Enclosure, Revised St Lucie Tables-LQ-W Project stage: Other ML15273A2092015-10-0101 October 2015 Nuclear Regulatory Commission Report for the Audit of Florida Power and Light Company'S Flood Hazard Reevaluation Report Submittals Relating to the Near-Term Task Force Recommendation 2.1-Flooding for St. Lucie Plant Units 1 and 2 Project stage: Other 2015-06-01
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Category:Audit Report
MONTHYEARML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML22188A0862022-07-0707 July 2022 SLRA - Audit Report ML22130A6702022-01-21021 January 2022 Trp 076 St. Lucie SLRA Breakout Questions Irr. Concr. Steel AP DD Jd (Combined) ML22130A6732022-01-11011 January 2022 TRP16 - St. Lucie SLRA Breakout Questions_Pwr Internals ML21245A3052021-09-24024 September 2021 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML19217A0032019-12-0202 December 2019 Audit Report Regarding Generic Letter 2004 02 Closure Methodology (EPID-2017-LRC-0000) ML15273A2092015-10-0101 October 2015 Nuclear Regulatory Commission Report for the Audit of Florida Power and Light Company'S Flood Hazard Reevaluation Report Submittals Relating to the Near-Term Task Force Recommendation 2.1-Flooding for St. Lucie Plant Units 1 and 2 ML15215A4942015-08-18018 August 2015 Audit of the Licensee'S Management of Regulatory Commitments ML15086A0542015-04-28028 April 2015 Report of Audit to Support Proposed Amendment Transitioning the Fire Protection Licensing Basis to NFPA 805 ML15035A6702015-02-27027 February 2015 Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14002A1242014-02-0606 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML12356A4952012-12-31031 December 2012 Audit of Licensee'S Management of Regulatory Commitments (TAC Nos. ME8077 and ME8078) ML0904008752009-02-25025 February 2009 Audit of the Licensee'S Management of Regulatory Commitments 2023-10-23
[Table view] Category:Letter
MONTHYEARIR 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 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 1, 2015 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
NUCLEAR REGULATORY COMMISSION REPORT FOR THE AUDIT OF FLORIDA POWER AND LIGHT COMPANY'S FLOOD HAZARD REEVALUATION REPORT SUBMITTALS RELATING TO THE NEAR-TERM TASK FORCE RECOMMENDATION 2.1-FLOODING FOR ST. LUCIE PLANT, UNITS 1AND2 (TAC NOS. MF6113 AND MF6114)
Dear Mr. Nazar:
By letter dated June 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15147A591), the U.S. Nuclear Regulatory Commission (NRC) informed you of the staff's plan to conduct a regulatory audit of Florida Power and Light Company's (the licensee, FPL) Flood Hazard Reevaluation Report (FHRR) submittals related to the Near-Term Task Force Recommendation 2.1-Flooding. The audit was intended to support the NRC staff review of the licensees FHRRs and the subsequent issuance of a staff assessment.
The audit was conducted on July 23, 2015, and was performed consistent with NRC Office of Nuclear Reactor Regulation, Office Instruction LIC-111, "Regulatory Audits," dated December 29, 2008, (ADAMS Accession No. ML082900195). Therefore, the purpose of this letter is to provide you with the final audit report, which summarizes and documents the NRC's regulatory audit of FPL's FHRR submittals. The details of this audit have been discussed with Mr. Ken Frehafer of your staff.
M. Nazar If you have any questions, please contact me at (301) 415-6185 or by e-mail at Anthony.Minarik@nrc.gov.
Sincerely, Docket Nos. 50-335 and 50-389
Enclosure:
Audit Report cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 U.S. NUCLEAR REGULATORY COMMISSION AUDIT REPORT FOR THE AUDIT OF FLORIDA POWER AND LIGHT COMPANY'S FLOOD HAZARD REEVALUATION REPORT SUBMITTALS RELATING TO THE NEAR-TERM TASK FORCE RECOMMENDATION 2.1-FLOODING FOR ST. LUCIE PLANT, UNITS 1 AND 2 BACKGROUND AND AUDIT BASIS By letter dated March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued a request for information to all power reactor licensees and holders of construction permits in active or deferred status, pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.54(f) "Conditions of license" (hereafter referred to as the "50.54(f) letter"). The request was issued in connection with implementing lessons-learned from the 2011 accident at the Fukushima Dai-ichi nuclear power plant, as documented in The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. Recommendation 2.1 in that document recommended that the NRC staff issue orders to all licensees to reevaluate seismic and flooding for their sites against current NRC requirements and guidance. Subsequent Staff Requirements Memoranda associated with Commission Papers SECY 11-0124 and SECY 0137, instructed the NRC staff to issue requests for information to licensees pursuant to 10 CFR 50.54(f).
By letter dated March 10, 2015, Florida Power and Light Company (FPL, the licensee) submitted its Flood Hazard Reevaluation Reports (FHRRs) for St. Lucie Plant, Units 1 and 2 (St. Lucie) (Agencywide Documents Access and Management System (ADAMS) Accession Package No. ML15083A306). The NRC is in the process of reviewing the aforementioned submittals and has completed a regulatory audit of FPL to inform the licensee of its development of the submittals, identify any similarities/differences with past work completed and ultimately aid in its review of licensees' FHRRs. This audit summary is being completed in accordance with the guidance set forth in NRC Office of Nuclear Reactor Regulation, Office Instruction LIC-111, "Regulatory Audits," dated December 29, 2008 (ADAMS Accession No. ML082900195).
AUDIT LOCATION AND DATES The audit was completed by document review via electronic reading room and teleconference on July 23, 2015, from 9:00 am to 10:00 am.
Enclosure
AUDIT TEAMS Title Team Member Organization Team Leader, NRR/JLD Anthony Minarik NRC Branch Chief, NRO/DSEA Christopher Cook NRC Technical Lead Laura Quinn-Willingham NRC Technical Suooort Peter Chaput NRC Technical Suooort Henry Jones NRC Technical Support Christopher Bender Taylor Eng./NRC Support DOCUMENTS AUDITED of this report contains a list, which details all the documents that were reviewed by the NRC staff, in part or in whole, as part of this audit. The documents were located in an electronic reading room during the NRC staff review. The documents, or portions thereof, that were used by the staff as part of the technical analysis and/or as reference in the completion of the staff assessment, were submitted by the licensee and docketed for transparency and completeness of information, as necessary. They are identified in Table 1.
AUDIT ACTIVITIES In general, the audit activities consisted mainly of the following actions:
- Review background information on site topography and geographical characteristics of the watershed.
- Review site physical features and plant layout
- Understand the selection of important assumptions and parameters that would be the basis for evaluating the individual flood causing mechanisms described in the 50.54(f) letter.
- Review model input/output files to computer files such as Delft-3D and FL0-2D to have an understanding of how modeling assumptions were programmed and executed Table 1 on the following page, provides more detail and summarizes specific technical topics (and resolution) of important items that were discussed and clarified during the audit. The items discussed in Table 1 may be referenced/mentioned in the staff assessment in more detail.
Table 1: Sample of Technical Topics of Discussion Info Need Information Need Description Post-Audit Status No.
1 All Flood Causing Mechanisms - The licensee stated that the current Com~arison of Reevaluated Flood Hazard design-basis and CLB values are the with Current Design-Basis same, therefore the NRC Staff can interpret mentioning of the CLB as the
Background:
The FHRR for the St Lucie site current design-basis in the FHRR.
provides comparisons of the reevaluated flood The NRC staff accepts this response hazards with the current licensing basis (CLB) as sufficient and the issue resolved, for all flood causing mechanisms for which a therefore no substantial discussion was CLB had been established in Section 3.0. In needed during the audit. However, the FHRR Section 5.14 of the report is a summary NRC did request that the licensee of this comparison. The 50.54(f) letter provide a letter stating this explanation requested a comparison with the current on the docket.
design-basis.
Request: The licensee is requested to provide clarification regarding the inconsistencies identified in the FHRR with regard to the comparison of the reevaluated flood hazard to the current design-basis and submit a revised hazard comparison consistent with the instructions provided in the 50.54(f) letter.
2 Local Intense Preci~itation The licensee discussed that the 20-feet by 20-feet resolution is sufficient for the
Background:
The FHRR presents a local flow conditions. During the audit, the intense precipitation (LIP) flood reevaluation licensee provided additional discussion using a grid size of 20-feet in the FL0-2D regarding how vehicle barrier systems model. This approach may not capture the and other obstructions were modeled potentially most conservative and bounding with this grid size.
flood condition resulting from precipitation Additional discussion regarding events of different magnitude and duration. durations have been made irrelevant by LIP duration white paper.
Request: Provide justification that the 20-feet grid size described FHRR is bounding in terms of flood depth. This justification should include sensitivity analysis of LIP event for grid sizes less than 20-feet (e.g. 10-feet, 5-feet).
Info Need Information Need Description Post*Audit Status No.
3 Local Intense Preci(:!itation The licensee directed staff to the
Background:
The FHRR includes Figure 4-6, figures in calculation package FPL-Points of Interest (POI), and Figure 4-7, 072-CALC-003 "Local Intense Maximum Water Depths at POis for All Precipitation (LIP) Flooding Simulations, which combined locate the Calculation", Revision 1, Section 7, openings to safety related structures and the Attachment A During the audit, NRC LIP time-depth plots at selected locations. staff explained that the information was This information focuses on specific points at being requested to assist in the the site, and may not provide enough completion of the staff assessment.
information regarding overall areas of LIP The NRC staff informed the licensee flooding concern. This type of graphical that docketing of the final LIP analysis information could be used to determine where FL0-2D output files would be to focus mitigating strategies, interim actions necessary for the NRC Staff to and other flood mitigation and protection document its review of the LIP activities (e.g. improving drainage along a analysis. The NRC staff has no further building rather than installing multiple flood issues on this topic.
doors).
Request: Provide detailed figures or maps of the flooding depths that result from LIP flooding across the entire site, rather than depths and elevations at select locations. The figures or maps can only be for the LIP event that produces the Qreatest flooding depth.
EXIT MEETING/BRIEFING:
On July 23, 2015, the NRC staff closed out the discussion of the technical topics described above. The NRC staff determined the information that would need to be provided to resolve some of the items discussed during the audit and the licensee agreed to provide the information as soon as possible. This information included the following:
- 1) An explanation via letter that references to the current licensing basis in the FHRR could be taken to mean the current design-basis.
- 2) The FL0-2D output files related to the final LIP analysis.
ATTACHMENT 1 FHRR Reference Lists FPL-072-CALC-001, FL0-2D Bathvmetrv and Topography Processing Calculation, Rev. 1 FPL-072-CALC-002, Local Intense Precipitation Rainfall Distribution Calculation, Rev. 1 FPL-072-CALC-003, Local Intense Precipitation (LIP) Flooding Calculation, Rev. 1 FPL-072-CALC-004, DELFT3D BATHYMETRY AND TOPOGRAPHY CALCULATION FPL-072-CALC-005, REGIONAL HURRICANE CLIMATOLOGY CALCULATION FPL-072-CALC-006, PROBABLE MAXIMUM STORM (PMS) PARAMETERS AND STORM TRACKS CALCULATION FPL-072-CALC-007, 10% EXCEEDANCE HIGH AND LOW TIDES CALCULATION FPL-072-CALC-008, SEA LEVEL RISE CALCULATION FPL-072-CALC-009, DELFT3D SURGE MODEL GEOMETRY CALCULATION FPL-072-CALC-010, DELFT3D SURGE MODEL CALIBRATION FPL-072-CALC-011, PROBABLE MAXIMUM STORM SURGE (PMSS) CALCULATION FPL-072-CALC-012, SEICHE CALCULATION FPL-072-CALC-013, PROBABLE MAXIMUM STORM SURGE (PMSS) WAVE RUNUP AND COMBINED EFFECTS CALCULATION FPL-072-CALC-017, PROBABLE MAXIMUM STORM SURGE - HYDROSTATIC, HYDRODYNAMIC, DEBRIS, AND SEDIMENTATION LOADING CALCULATION
M. Nazar If you have any questions, please contact me at (301) 415-6185 or by e-mail at Anthony.Minarik@nrc.gov.
Sincerely, IRA/
Anthony Minarik, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389
Enclosure:
Audit Report cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC JLD R/F RidsNRRJLD Resource JUribe, NRR RidsNrrPMStlucie Resource MShams, NRR ARivera, NRO MFranovich, NRR KErwin, NRO LQuinn-Willingham, NRO CCook, NRO YChen, NRO PChaput, NRO JBowen, NRR RidsNrrDorlLPL2-2 Resource ADAMS Accession No.: ML15273A209 OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME AMinarik Slent MShams AMinarik DATE 10/1/2015 10/1/2015 10/1/2015 10/1/2015 OFFICAL RECORD COPY