|
---|
Category:Letter
MONTHYEARIR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
[Table view] Category:Report
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5.2014-12-0909 December 2014 Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-92332014-08-11011 August 2014 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station2014-04-25025 April 2014 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... ML13365A2532014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14028A0742014-02-0606 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Hope Creek Generating Station, TAC No. MF0867 LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic2014-01-29029 January 2014 Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 92012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G2012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G ML13052A6772012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 ML13052A6782012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 ML13052A6792012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G LR-N12-0366, Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 52012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary2012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6752012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6802012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J ML13052A6812012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75 ML13052A6822012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 2023-09-06
[Table view] Category:Miscellaneous
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5.2014-12-0909 December 2014 Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-92332014-08-11011 August 2014 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station2014-04-25025 April 2014 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13052A6752012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary2012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML12220A2502012-08-10010 August 2012 Closeout of Bulletin 2011-01, Mitigating Strategies ML12159A3552012-06-0808 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML11203A0782011-07-13013 July 2011 Independent Spent Fuel Storage Installation, 10 CFR 72.212 Evaluation Report, Revision 6 LR-N11-0090, 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations2011-04-0808 April 2011 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations ML11061A0052011-03-30030 March 2011 Ncsa Hope Creek Observations Rev. 4 LR-N10-0355, Salem, EAL Technical Bases Supporting Documents2010-10-14014 October 2010 Salem, EAL Technical Bases Supporting Documents ML1100602392010-10-14014 October 2010 Salem, EAL Technical Bases Supporting Documents ML11263A0302010-09-20020 September 2010 E-mail with Attachment from B. Pham, NRR to L. Perkins, NRR, on Forward Salem/Hope Creek Chapter 5 SAMA Input ML11263A0282010-09-16016 September 2010 E-mail with Attachment from T. Ghosh, NRR, to C. Eccleston, NRR Et Al, on Reaction Hope Creek SAMA Transmittal Memo LR-N10-0306, 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S2010-08-10010 August 2010 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S LR-N09-0206, Special Report - North Plant Vent Radiation Monitoring System (Rms)2009-08-24024 August 2009 Special Report - North Plant Vent Radiation Monitoring System (Rms) LR-N08-0224, Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit2008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit ML0831008272008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit LR-N08-0247, Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action2008-10-30030 October 2008 Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action ML0826005732008-09-0202 September 2008 NFS-0255, Revision 0, Hope Creek Generating Station - Initial Implementation of WCAP-15942-P-A (Formerly CENO-287), Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement to CENP-287, Evaluation of Control Blade I ML0732300962007-11-0909 November 2007 Discharge Confirmation Report - Retraction of Reported Discharge to the Delaware River HCH-2007-052, Notice of Noncompliance and Affirmative Defense of Laboratory Error2007-05-23023 May 2007 Notice of Noncompliance and Affirmative Defense of Laboratory Error LR-N07-0040, Special Report - North Plant Vent Radiation Monitoring System (Rms)2007-02-20020 February 2007 Special Report - North Plant Vent Radiation Monitoring System (Rms) LR-N06-0401, Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models2006-09-28028 September 2006 Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models ML0626900642006-09-0101 September 2006 Attachment 26, C.D.I. Report No. 06-16NP, Rev 1, Estimating High Frequency Flow Induced Vibration in the Main Stream Lines at Hope Creek Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. ML0622805562006-07-27027 July 2006 Groundwater Protection - Data Collection Questionnaire LR-N06-0216, Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment Report2006-05-0404 May 2006 Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment Report ML0607204372006-03-0707 March 2006 Redacted Response to Request for Information Regarding Executive Review Board Commitments; PSEG ML0606703012006-02-0707 February 2006 PSEG-News Document Detailing Chris Bakken Will Succeed Anderson as President and CNO of PSEG Nuclear ML0605801622006-02-0101 February 2006 Performance Themes for Use After Inspection Exits (Regarding Poor Equipment Reliability, Corrective Action Ineffectiveness) and Organizational Issues (Regarding Engineering, Maintenance & Work Control, Operations, and Licensing/Regulatory C ML0524901582005-08-31031 August 2005 Allegation Receipt Report Regarding Facility: Hope Creek ML0526302272005-08-23023 August 2005 Communication Plan & Notification Sequence Regarding Receipt & Docketing of PSEG Assessment Reports ML0531803762005-04-30030 April 2005 NEDO-33186, Revision 1, MELLLA Tracg Divom Evaluation for Hope Creek at Cppu Conditions. 2023-12-15
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 18, 2013 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION- AUDIT REPORT REGARDING FLOODING WALKDOWNS TO SUPPORT IMPLEMENTATION OF NEAR-TERM TASK FORCE RECOMMENDATION 2.3 RELATED TO THE FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT ACCIDENT (TAC NO. MF0236)
Dear Mr. Joyce:
On March 12, 2012, the U.S. Nuclear Regulatory Commission staff (NRC or the staff) issued a request for information letter per Title 10 of the Code of Federal Regulations, Subpart 50.54(f)
(50.54(f) letter). The 50.54(f) letter was issued to power reactor licensees and holders of construction permits requesting addressees to provide further information to support the NRC staff's evaluation of regulatory actions to be taken in response to lessons learned from Japan's March 11, 2011, Great Tohoku Earthquake and subsequent tsunami. The request addressed the methods and procedures for plants to conduct seismic and flooding hazard walkdowns to identify and address degraded, nonconforming, or unanalyzed conditions through the corrective action program, and to verify the adequacy of the monitoring and maintenance procedures.
By letter dated November 26, 2012, as supplemented by letter dated April 12, 2013, PSEG Nuclear, LLC (PSEG) submitted a Flooding Walkdown Report as requested per Enclosure 4 of the 50.54(f) letter for the Hope Creek Generating Station. On June 25, 2013, an NRC audit team completed the on-site audit to gain a better understanding of the methods and procedures used by PSEG to conduct the flooding walkdowns. The information gained during the audit will facilitate the NRC staff review of the walkdown report and allow for more concise requests for information if needed. The NRC staff appreciates your support of the audit. The final audit report has been included as an enclosure to this letter.
T.Joyce If you have any questions, please contact me at 301-415-3204 or by e-mail at john. hughey@nrc.gov.
po Sincerely, John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Audit Report cc w/encl: Distribution via Listserv
REPORT OF REGULATORY AUDIT ON JUNE 25 TO JUNE 27, 2013 FLOODING WALKDOWNS PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354
- 1. Introduction This document provides a summary of the United States Nuclear Regulatory Commission (NRC) audit of the flooding walkdowns performed by Hope Creek Generating Station, Unit 1.
The walkdowns were performed in response to NRC's request for information contained in the March 12, 2012, 50.54(f) letter, 1 Enclosure 4.
1.1 Background By letter dated March 12, 2012, 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, Section 50.54(f) (hence referred to as the 50.54(f) letter). The request was issued as a part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 4 of the 50.54(f) letter requested that licensees plan and perform flooding walkdowns to identify degraded, nonconforming, or unanalyzed conditions related to the licensing bases of structures, systems, and components (SSCs) important to safety and to verify the adequacy of monitoring and maintenance procedures.
By letter dated November 26, 2012, 2 PSEG Nuclear, LLC (PSEG) submitted a report documenting the flooding walkdowns for Hope Creek Generating Station, Unit 1, as requested per Enclosure 4 of the 50.54(f) letter. By letter dated April 12, 2013, 3 PSEG submitted a supplement to the original report.
1.2 Regulatory Audit Basis The NRC staff conducted a regulatory audit to gain a better understanding of the methods and associated procedures used by PSEG to conduct the flooding walkdowns at Hope Creek Generating Station, Unit 1, and facilitate the assessment of the licensee's report documenting site walkdowns.
The Nuclear Energy Institute (NEI) developed guidance for performing the flooding walkdowns with extensive review and input from NRC staff in numerous public meetings, webinars, and 1
Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340.
2 ADAMS under Accession No. ML12334A452.
3 ADAMS under Accession No. ML13106A066.
Enclosure
public conference calls. NEI submitted NEI 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features,"4 for endorsement. The NRC staff subsequently endorsed the walkdown guidance by letter dated May 31, 2012. 5 By letter dated June 7, 2012, 6 PSEG confirmed that it will follow the NRC endorsed guidance for performance of the flooding walkdowns at Hope Creek Generating Station, Unit 1.
1.3 Audit Logistics An audit plan was issued to PSEG on May 20, 2013. 7 The audit plan included a proposed audit schedule and a list of information that NRC requested that the licensee make available for review during the audit. The audit plan also requested that the personnel (licensee staff and contractors) who performed the walkdowns be available for interviews.
The NRC staff performed an audit of Hope Creek Generating Station, Unit 1 on June 25-27, 2013. The audit was performed in accordance with the Office of Nuclear Reactor Regulation Office Instruction, LIC-111, "Regulatory Audits." 8 The Hope Creek Generating Station audit team, consisting of NRC staff and contractors, is listed in Table 1. It is noted that, because the audit of Hope Creek Generation Station, Unit 1, was performed concurrent with the audit of Salem Nuclear Generating Station, there was considerable interaction between the site audit teams for both sites.
An entrance meeting was held on June 25, 2013, to convey to the licensee background information and the purpose of the audit. An exit meeting was held on June 27, 2013, to convey to the licensee observations from the audit, including: (1) observations related to whether the walkdowns were performed in accordance with NEI 12-07, and (2) observations forwarded to the resident inspectors for additional action, if appropriate.
Table 1: NRC Audit Team Audit team member Affiliation Audit Role Stephen Campbell NRC/NRRIDIRS/IRIB Audit lead Michelle Bensi NRC/NRO/DSEA/RHMB Technical lead Sherlyn lbarrola NRC/R-1/DRP/PB3/HCRO Resident inspector George Wilson NRC/NRR Management support Terri Patton Argonne National Laboratory Flooding technical support 4
ADAMS Accession No. ML12144A401.
5 ADAMS Accession No. ML12144A142.
6 ADAMS Accession No. ML12160A292.
7 ADAMS Accession No. ML13127A116.
8 ADAMS Accession No. ML082900195.
- 2. Audit Scope The audit provides support for the ongoing NRC staff assessment of the licensee-submitted walkdown report. The audit scope included review of information and documents available onsite and interviews of licensee staff and contractors to aid NRC staff understanding of:
( 1) how the licensee performed the flooding walkdowns, and (2) whether the walkdowns were performed in accordance with NEI 12-07.
The audit also helped to identify additional information that will require docketing to support the staff conclusions related to the staff assessment. Observations made by the audit team that were not within the scope of the audit were transferred to the resident inspector for additional action, if appropriate.
- 3. Audit Activities and Remarks The NRC staff prepared a preliminary list of questions, which were communicated to the licensee prior to the arrival of the team on site. The preliminary list of questions addressed the following topical areas:
- Evaluation and disposition of available physical margin (APM) information in light of statements made by the licensee in the walkdown report regarding flood heights and flood protection elevations at the intake structure
- Assessment and disposition of flood protection features identified in the walkdown report as having "documentation insufficient for determining hydrostatic rating"
- Disposition via the corrective action program (CAP) of potential deficiencies identified in Attachment A of the licensee's walkdown report
- Computation of APM for barriers and penetration seals
- Identification and disposition of flood protection features associated with small or negative margin
- Disposition of observations of cracking, missing seals, leakage (or signs of historical leakage), rust, calcification, or seal degradation Throughout the audit, the licensee addressed the staff questions related to the above topics and provided clarification with regard to the processes used to: compute APM, identify and address potential deficiencies, assess and disposition observations not immediately judged to be acceptable, and address instances of small (or potentially negative) margin.
Once on site, the audit team reviewed documents related to the licensee's performance of the flooding walkdowns, including:
- Walkdown record forms and other supplemental forms and worksheets generated by the licensee to document observations associated with the walkdowns
- Flood-specific procedures that are part of flood protection strategy and severe weather response that were reviewed or used by the licensee as part of the flood walkdowns
- Listing of entries into the CAP resulting from the performance of the flood walkdowns
- The "Check-in Self-Assessment Report" generated by the licensee to evaluate the status of Hope Creek Generating Station's flooding walkdowns
- Site plans and maps, as well as relevant plant drawings
- Relevant sections of the updated final safety analysis report (UFSAR) for the site The audit team also interviewed site personnel and walkdown participants to inquire about: (1) performance of visual inspections (e.g., to discuss criteria used to determine flood protection feature acceptability), (2) calculation of APM and consideration of safety consequences associated with any instances of small margin, and (3) estimation of time required to perform manual actions.
All audit team members participated in a site familiarization tour. As necessary, staff also participated in additional field visits to observe areas of the site that are associated with plant flood response or were examined by the licensee as part of flooding walkdowns.
The licensee made presentations to provide an overview of the site walkdowns and describe the format used by the licensee to document the walkdown. The walkdown record forms at Hope Creek Generating Station were comprised of two parts: (1) a copy of the walkdown record form contained in Appendix B of NEI 12-07 that was generically populated for each class of flood protection features (e.g., penetration seals, flood doors, structural walls), and (2) a detailed spreadsheet containing information on each individual flood protection feature included in the walkdown scope (e.g., the spreadsheet contained an entry for each individual penetration seal, flood door, and credited structural wall). As part of the audit, a sample of entries from the spreadsheet was reviewed for the reactor buildings, auxiliary building, service water intake structure, and rad waste building.
Audit review responsibilities associated with flood protection features were generally divided among audit team members based on plant building or area. In addition, one audit team member focused on the review of reasonable simulations performed as part of the walkdowns.
Another audit team member reviewed walkdown record forms for a sample of structures (walls),
doors, and seals in Room 202 of the service water structure, Room 4304 of the Unit 1 reactor building, and Room RB2 of the Unit 2 reactor building. The audit team members reviewed information related to: material condition; critical design characteristics; whether equipment can be operated as expected; APM (including flood height at locations of flood protection features and capacity/rating of the features); whether features with small margin were entered into the CAP; and associated CAP notifications. The audit team members noted the following as a result of the review:
- Flood heights used to calculate APM for some features were not consistent with the design-basis flood height for the site. In response to NRC staff questions, the licensee explained that the reason for this difference was that the evaluation of APM for some walls and doors considered a limiting flood height that was relevant to defining the structural capacity of the feature rather than being based on the design-basis flood elevation. Consequently, the evaluation of APM for these walls and doors considered
structural capacity, but the licensee did not consider the potential for overtopping of barriers due to feature height.
- The licensee completed Question 27 (related to identification of whether small margin and significant consequences appear to exist) of the walkdown record form from Appendix B of NEI 12-07 on a generic basis (e.g., for each "class" of flood protection features) rather than on a feature-specific basis. As a result, individual flood protection features with small margin were not associated with a resulting evaluation of safety consequences or entrance into the CAP for any individual feature.
- While APM was systematically evaluated at the site on a feature-specific basis (e.g., for each individual seal or door), the limiting APM associated with composite barriers (e.g.,
a flood barrier comprised of structural components, flood doors, and penetration seals) was not identified.
An audit team member reviewed the walkdown records for at least one flood protection feature in each of the following rooms in the rad waste building: waste collector tank room, waste neutralizer room, cable tray area, electric penetration room, rad waste control room, and Rooms 3114, 3124, 3145, and 3167. In addition, the audit team member reviewed walkdown records for at least one flood protection feature in each of the following rooms in the auxiliary building:
electrical equipment area, diesel fuel storage tank rooms and corridors, battery room, access area, diesel generator room, corridor, electrical access room, and Rooms 5220 and 5228. The audit team member reviewed information in the walkdown records related to: observed material condition; the seal capacity rating relative to flood level; the reported flood level relative to the elevation maps (if specified) or the UFSAR; and the APM calculations. For those flood protection features with notification numbers, the audit team member also verified their status in the CAP program. The audit team member noted the following, as part of the review:
- Notifications were initiated for flood protection features that were inaccessible or restricted access, when the material condition was unacceptable, and, in some cases, when the APM was zero. All of the notifications that were reviewed were still in process at the time of the audit.
- The walkdown record spreadsheet did not address Question 2 (related to preventative maintenance programs) and Question 3 (related to periodic testing) from the walkdown record form in Appendix B of NEI 12-07, but the audit team member was able to review general documentation identifying concrete structures and components that are inspected and maintained. The document did not describe how seals are inspected and maintained, but further discussions with plant personnel indicated seals are inspected periodically and any deficiencies found are addressed through the CAP.
In addition, an audit team member reviewed the reasonable simulations performed of the procedures, OP-AA-1 08-11-1001, Revision 7, "Severe Weather and Natural Disaster Guidelines," and HC.OP-AB.MISC-0001(Q), Revision 21, "Acts of Nature." The staff conducted field walkdowns and interviewed licensee personnel on the implementation of the procedures.
The audit team member noted the following as part of the review:
- Prior to the performance of the flood walkdowns, the licensee recently executed the flood-specific procedure for an actual event. Therefore no reasonable simulation was
performed during the walkdowns and conclusions made regarding manual actions were based on actual performance data.
- A review of the logs and procedures from previous events verified the ability of the licensee to perform required activities within the associated timelines (e.g., shut and "dog" a series of watertight doors within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- The licensee did not perform reasonable simulation of activities that they identified as asset protection (e.g., placement of sand bag walls around several door openings).
An audit team member also noted that the UFSAR indicates that "all roof openings are watertight and provided with either metal sleeves or concrete curbs of sufficient height to exceed any possible pending levels," and also describes roof drainage systems and scuppers.
The licensee did not include the roofs of structures within the walkdown scope. The licensee indicated that a walkdown of the roof was out of scope.
Based on the audit team's reviews, the NRC staff has several observations directly related to whether the licensee performed the audit in accordance with NEI 12-07. Those observations are described in Section 4.1 of this audit summary.
- 4. Audit Summary As described in Section 2, the goal of the audit was to support the development of the staff assessment of the licensee's walkdown report. Observations made by the audit team during the audit were compiled and conveyed to the licensee during the exit meeting. These observations are neither findings nor potential violations; however, they will be used to inform the NRC staff assessment of the licensee's walkdown report.
4.1 Observations related to NEI12-07 The audit team made observations during the audit directly related to the scope of the audit.
These observations are described below.
Section 5.8, "Documentation of Available Physical Margin," of NEI 12-07 states that information on APM should be collected and documented in the walkdown record forms. In addition, if the APM of a flood protection feature appears to be small and the consequences of flooding at that location appear to be significant, the condition should be entered into the CAP. The CAP disposition should consider the size of the margin and the consequences of flooding the area affected by the flood protection. Once entered into the CAP, licensees are to take appropriate actions. In consultation with licensee staff, NRC staff learned that there were three "classes" of small margin characterized by the licensee:
- 1. "Administratively small (or zero)" margin: During the walkdowns, the licensee encountered challenges associated with documentation of capacity for some flood protection features. While the licensee believes that these features are capable of withstanding flood events larger than the design-basis flood, existing documentation is only available to demonstrate that flood protection features are capable of withstanding the design basis flood. These features were thus assigned an APM of zero and
classified as having "administratively small (or zero)" margin. The licensee has initiated a "margin recovery effort" to better quantify available margin to supplement existing documentation.
- 2. Seals of unknown capacity: The site has flood protection seals for which the seal capacity is unknown (typically due to documentation issues). The licensee assigned an APM of zero to such seals given that design control or similar processes are intended to assure flood protection features are able to meet the licensing basis.
- 3. Verified small margin: This classification is used to identify flood protection features that are capable of withstanding the design-basis flood, but with small margin available to withstand larger floods.
Initially, the licensee indicated to the audit team that the only instances of small margin at the site were either: ( 1) "administratively small (or zero)" margin (i.e., class 1 above), or (2) associated with seals of unknown capacity (i.e., class 2 above). For this reason, the licensee did not believe that it was necessary to evaluate safety consequences of small margin for any flood protection features. However, as a result of NRC staff questions during the audit, the licensee identified 10 penetration seals at the site with verified small margin (i.e., class 3 above) for which safety consequences were not considered. In accordance with NEI 12-07, instances of small margin should have been documented in Question 27 of Part E of the walkdown record form. The licensee initiated a CAP notification in response to NRC observations.
As described above, Section 5.8 of NEI 12-07 provided guidance on the need to calculate APM.
This calculation relies heavily on design and licensing basis flood heights. During the audit, NRC staff found multiple and varying flood heights for flood protection features (e.g., flood doors) used to evaluate APM. Initially, the licensee could not readily provide a basis for the flood heights. After further questioning, NRC staff was provided with an explanation of these values, which were based on the limiting flood height for evaluating structural loading (see section 3 of this report for additional explanation). For this reason, the evaluation of APM for these flood protection features did not consider their susceptibility to overtopping. At the time of the audit it was not clear to NRC staff if these values were appropriate or sufficient for calculating APM and NRC staff may request additional information (See Section 5 for further discussion).
4.2 Observations communicated to resident inspectors The audit team made observations related to the plant response to flooding hazards that were not directly related to the scope of the audit:
- During the audit team's site familiarization tour, NRC staff observed several outside watertight doors that are normally open. This practice exposes the seals to the environment, thereby potentially degrading seals more rapidly than normally closed watertight doors. This degradation may impact the flood sealing capability of these doors and therefore may require an increased preventative maintenance frequency.
- While reviewing the licensee's flood protection procedures that were implemented during Hurricane Sandy that were common to Hope Creek Generating Station and Salem Nuclear Generating Station, (i.e., OP-AA-108-11-1001, Revision 7, "Severe Weather and
Natural Disaster Guidelines") the NRC staff noted inconsistencies in the documentation of the implementation of the procedures between the sites.
These observations were forwarded to the site resident inspectors for additional action, if appropriate.
- 5. Potential additional information needs In response to the observations described in Section 4.1 of this audit summary, and to support the staff assessments of the licensee walkdown reports, the NRC staff may require additional information from the licensee regarding the methodology used to evaluate APM and responses to Question 27 for the walkdown record form in Appendix B of NEI 12-07 for flood protection features with small or zero APM. In addition, the NRC staff may require additional information regarding the flood heights used to calculate APM for certain flood protection features.
Moreover, the NRC staff may require additional information to clarify whether deficiencies were identified during the site walkdowns. Section 5.9, "Documenting Possible Deficiencies," of NEI 12-07, states all flooding observations identified as deficiencies by the licensee's CAP (and other items identified during the walkdowns but awaiting final disposition by the CAP) must be reported to the NRC as part of the licensee's walkdown report. In Section 5, of the Hope Creek Generating Station Walkdown report, the licensee stated that attachment A to the report includes both deficiencies and observations awaiting disposition. However, during the audit, the licensee indicated that, upon further review, there are no deficiencies identified for the site.
NRC staff may require additional information to clarify whether deficiencies were in fact identified at the site.
- 6. Conclusions The audit provided the NRC staff and contractors with information that is relevant to the staff assessment of the licensee's walkdown report. The audit team identified two observations during the audit related to NEI 12-07; two additional observations were forwarded to the Hope Creek Generating Station Resident Inspectors. In response to the audit, the NRC may require additional information as described in Section 5. This audit summary will be used as an input to the staff assessment of the licensee's walkdown report.
T. Joyce If you have any questions, please contact me at 301-415-3204 or by e-mail at john.hughey@nrc.gov.
Sincerely, Ira/
John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Audit Report cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsRgn1 MaiiCenter Resource NChokshi, NRR/DSEA LPLI-2 R/F RidsOpaMail Resource DRich, EDO Rl, Rll, Rill, RIV RidsNroDsea RidsNrrLAABaxter Resource RidsAcrsAcnw MaiiCTR Resource RidsNrrDorl Resource RidsNrrPMHopeCreek Resource RidsNrrDorllpii-2Resource ADAMS Accession Number: ML13266A297 *via email OFFICE DORL/LPLI-2/PM JLD/PMB/PM DORL/LPLI-2/LA DSEA/RHMB NAME JHughey GEM iller ABaxter
- MBensi DATE 11/06/13 10/01/13 09/27/13 10/21/13 OFFICE DSEA/RHMB DSEA/RHMB/BC DIRS/IRIB DORL/LPLI-2/BC NAME PChaput CCook
- VRodriguez DATE 10/18/13 11/1/13 10/28/13 11/13/13 OFFICE DSEA/DD DORL/LPLI-2/PM NAME NChokshi
- JHu_g_hey DATE 10/23/13 10/18/13 OFFICIAL RECORD COPY