Letter Sequence Request |
---|
EPID:L-2018-JLD-0172, Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding: Integrated Assessment Submittal (Open) |
|
|
|
---|
Category:Letter type:RA
MONTHYEARRA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023 Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0064, Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval2023-04-24024 April 2023 Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023 Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0043, Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations2023-03-30030 March 2023 Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0055, Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 22023-03-24024 March 2023 Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 2 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-02-0909 February 2023 Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-23-0027, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 20222023-01-30030 January 2023 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 2022 RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0347, Transmittal of Core Operating Limits Report2022-12-0202 December 2022 Transmittal of Core Operating Limits Report RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2022-11-0101 November 2022 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-22-0245, Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.162022-09-0808 September 2022 Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)2022-08-0909 August 2022 Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-07-28028 July 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0179, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2022-06-15015 June 2022 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes2022-05-24024 May 2022 Duke Energy Common Emergency Plan, Revision 2, Summary of Changes RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 RA-22-0148, 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory2022-05-16016 May 2022 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) RA-22-0106, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-04-28028 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 2024-02-05
[Table view] |
Text
Ernest J. Kapopoulos, Jr. H. B. Robinson Steam Electric Plant Unit 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, S C 29550 0: 843 9511704 F: 843 9511319 Ernie.Kapopoulos@duke-energy.com 10 CFR 50.4 10 CFR 50.54(f) Serial: RA-18-0265 DEC 19 2018 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 50-261/Renewed License Number DPR-23
Subject:
RESPONSE TO MARCH 12, 2012 REQUEST FOR INFORMATION ENCLOSURE 2, RECOMMENDATION 2.1, FLOODING; INTEGRATED ASSESSMENT SUBMITTAL
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc i dent, dat e d March 12, 2012, ADAMS Accession Number ML12056A046
- 2. NRC Letter, Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 1, 2013, ADAMS Accession Number ML13044A561
- 3. Duk e E nergy L etter, H. B. Robinson Steam Electric Plant, Unit No. 2, Flood Hazard Reevaluation Report, Response to NRC 1 O CFR 50.54(f) Request for Information Pursuant to Title 1 O of the Code of Federal Regulations 50.54(f) regarding Recommendations 2.1 , 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2014, ADAMS Accession Number ML14086A384
- 4. Duke Energy Letter, H. B. Robinson Unit 2 -Submittal of Response to the NRC Request for Additional Information Regarding Flood Hazard Reevaluation Report ,' dated July 9, 2014, ADAMS Accession Number ML14206A787 (Non-Publicly Available)
- 5. Duke Energy Letter, Response to NRC Request for Additional Information Regarding H. B. Robinson Steam Electric Plant, Unit No. 2, Flood Hazard Reevaluation Report (FHRR), dated May 26, 2015, ADAMS Accession Number ML15146A390
- 6. Duke Energy Letter, Submittal of Revision to Flooding Hazard Reevaluation Report to Provide a Revised Site Specific Local Intense Precipitation Storm for H.B. Robinson Steam Electric Plant, Unit No. 2, dated August 29, 2015 ADAMS Accession Number ML15243A077 (Non-Publicly Available)
- 7. Duke Energy Letter, Submittal of Response to the NRC Request for Additional Information Regarding H.B. Robinson Steam Electric Plant, Unit No. 2, Flood Hazard Reevaluation Report Related to Selection of the Dam Breach Trigger Elevation, dated December 15, 2015, ADAMS Accession Number ML15349A796 (Non-Publicly Available)
United States Nuclear Regulatory Commission Serial RA-18-0265 Page 2 of 4 8. NRC Letter, H. B. Robinson Steam Electric Plant, Unit 2 -Request for Additional Information Regarding Flood Hazard Reevaluation Report, dated June 18, 2014, ADAMS Accession Number ML14168A050
- 9. NRC email, Request for Additional Information
-H.B. Robinson 2.1 Flood Hazard Reevaluation Report, dated March 4, 2015, ADAMS Accession Number ML15065A085
- 10. COMSECY-15-0019, Closure Plan for the Reevaluation of Flooding Hazard for Operating Nuclear Power Plants, dated June 30, 2015, ADAMS Accession Number ML15153A104
- 11. NRC Letter, Coordination of Requests for Information Regarding Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events, dated September 1, 2015, ADAMS Accession Number ML15174A257
- 12. NRC email, Robinson RAI regarding NTTF 2.1 Flooding, Duke, dated December 14, 2015, ADAMS Accession Number ML15348A340
- 13. NRC Letter, H. B. Robinson Steam Electric Plant, Unit No. 2 -Interim Staff Response to reevaluated Flood Hazards Submitted in Response to 1 O CFR 50.54(f) Information Request -Flood Causing Mechanism Reevaluation, dated December 23, 2015, ADAMS Accession Number ML15357A065 (non-publicly Available)
- 14. Nuclear Energy Institute (NEI) Report, NEI 16-05, Revision 1, External Flooding Assessment Guidelines, dated June 2016 15. JLD-ISG-2016-01, Revision 0, Guidance for Activities Related to Near-Term Task Force Recommendation 2.1, Flood Hazard Reevaluation; Focused Evaluation and Integrated Assessment, dated July 11, 2016 16. NRC Letter, H. B. Robinson Steam Electric Plant, Unit No. 2 -Staff Assessment of Response to 10 CFR 50.54(f) Information Request -Flood Causing Mechanism Reevaluation, dated January 5, 2017, ADAMS Accession Number ML16355A381
- 17. NRC Letter, H. 8. Robinson Steam Electric Plant, Unit No. 2 -Flood Hazard Mitigation Strategies Assessment, dated May 9, 2018, ADAMS Accession Number ML17249A701 (non-publicly Available)
Ladies and Gentlemen:
On March 12, 2012, the NRC issued Reference 1, which requested information associated with Near-Term Task Force {NTTF) Recommendation 2.1 for flooding.
One of the Required Responses in Reference 1 directed licensees to submit a Flood Hazard Reevaluation Report (FHRR) to reevaluate the flood hazards for their sites using present-day methods and guidance.
For H. 8. Robinson Steam Electric Plant (H8RSEP), Unit No. 2, the FHRR was submitted on March 12, 2014 (Reference 3). Additional information was provided with References 4 through 7, which were in response to References 8, 9 and 12. In accordance with Reference 2, the NRC considers the reevaluated flood hazard to be "beyond the current design/licensing basis of operating plants." Following the Commission's directive to NRC Staff (Reference 10), the NRC issued a letter to industry (Reference
- 11) indicating that new guidance is being prepared to replace instructions and provide for a "graded approach to flooding reevaluations" and "more focused evaluations of local intense precipitation and available physical margin in lieu of proceeding to an integrated assessment." The Nuclear Energy Institute (NEI) prepared NEI 16-05, "External Flooding Assessment Guidelines" (Reference 14). The NRC endorsed NEI 16-05 (Reference
- 15) and recommended changes, which have been incorporated into NEI 16-05, Revision 1. NEI 16-05 indicates that each flood-causing United States Nuclear Regulatory Commission Serial RA-18-0265 Page 3 of 4 mechanism not bounded by the Design Basis (DB) flood (using only stillwater and/or wind-wave runup level) should follow one of the following five assessment paths:
- Path 1: Demonstrate Flood Mechanism is Bounded Through Improved Realism
- Path 2: Demonstrate Effective Flood Protection
- Path 3: Demonstrate a Feasible Response to Local Intense Precipitation (LIP)
- Path 4: Demonstrate Effective Mitigation
- Path 5: Scenario-Based Approach Non-bounded flood-causing mechanisms in Paths 1, 2 or 3, would only require a Focused Evaluation (FE) to complete the actions related to external flooding required by the March 12, 2012 1 O CFR 50.54(f) letter (Reference 1 ). Mechanisms in Paths 4 or 5 require an Integrated Assessment (IA). The reevaluated flood hazard, summarized by the NRC in References 13 and 16, was utilized as input to this Flooding Integrated Assessment.
There are five mechanisms that were found to be not bounded by the plant's design basis. These mechanisms were evaluated for the need to improve realism as described in Section 6.1 of NEI 16-05, and in accordance with NEI 16-05 Appendix A Reduction of Conservatisms (Reference 14). These mechanisms are listed below: 1. LIP 2. Upstream Dam Failures 3. Seiche 4. Storm Surge 5. Streams & Rivers Regarding the LIP mechanism, the NEI 16-05, Appendix A process was followed with a site-specific storm and subsequently the FHRR was revised in December 2015 (Reference 7). Following the FHRR Revision, HBRSEP concluded that no further evaluation for improving realisms in the LIP flooding mechanism was warranted.
The most appropriate path for the LIP mechanism, crediting strategies in the Flood Mitigation Strategies Assessment, was determined to be NEI 16-05 Path 3. Enclosure 1 of this submittal addresses the site response to the LIP hazard. The Upstream Dam Failures, Seiche, and Storm Surge flooding mechanisms are unbounded by the current design bases. Stillwater levels for these flooding mechanisms are below site grade, but the maximum water surface elevation including combined effects are above site grade. The Streams & Rivers mechanism is above site grade, and bounds all other flooding mechanisms, therefore, conservatisms were re-evaluated for this mechanism.
The Wind-Driven Wave (WOW) component in each of the combined effects scenarios were also re-evaluated.
Enclosure 2 of this submittal describes the refinements to the Streams & Rivers Probable Maximum Flood (PMF) hazard and the changes to the WOW component.
After improving realisms in the controlling Streams & Rivers mechanism, it was determined the NEI 16-05 Path 5 Scenario Based Approach is the most appropriate path. Enclosure 3 describes the site response to the Streams & Rivers PMF hazard. The Flooding FE and IA concludes that HBRSEP's response to non-bounded flood events ensure availability of all Key Safety Functions and includes a FLEX-based mitigation strategy.
This submittal completes the actions related to external flooding required by the March 12, 2012 1 O CFR 50.54(f) Request for Information letter (Reference 1 ).
United States Nuclear Regulatory Commission Serial RA-18-0265 Page 4 of 4 This letter contains no new regulatory commitments.
Please address any comments or questions regarding this submittal to Kevin Ellis, Manger -Nuclear Regulatory Affairs, at 843-951-1329.
I .declare under penalty of perjury that the foregoing is true and correct. Executed on I '1 V fC. ~of~ . Sincerely, 0)1{~ Ernest J. Kapopoulos, Jr. Site Vice President EJK/jmw
Enclosures:
1: Demonstration of Feasible Response to the LIP Event (NEI 16-05 Path 3) 2: Refinement to RNP FHRR Flooding in Streams & Rivers and Wind-Driven Wave Component 3: Scenario-Based Approach on Streams & Rivers PMF with Combined Effects (NEI 16-05 Path 5) c: NRC Resident Inspectors, HBRSEP, Unit No. 2 Regional Administrator, NRC, Region II Nate Jordan, NRC Project Manager, NRR