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Category:Letter type:RNP
MONTHYEARRNP-RA/21-0035, Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-18018 February 2021 Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/20-0234, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2020-07-23023 July 2020 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RNP-RA/20-0199, Registration of Use of Spent Fuel Casks2020-06-25025 June 2020 Registration of Use of Spent Fuel Casks RNP-RA/18-0063, Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal2018-11-29029 November 2018 Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal RNP-RA/18-0060, Transmittal of Core Operating Limits Report2018-10-17017 October 2018 Transmittal of Core Operating Limits Report RNP-RA/18-0050, Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change2018-08-0101 August 2018 Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/18-0039, Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis2018-06-27027 June 2018 Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis RNP-RA/18-0041, Independent Spent Fuel Storage Installation - Register as User for Cask2018-06-13013 June 2018 Independent Spent Fuel Storage Installation - Register as User for Cask RNP-RA/18-0036, Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ...2018-05-16016 May 2018 Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ... RNP-RA/18-0029, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-0808 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report RNP-RA/18-0031, (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 352018-04-23023 April 2018 (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 35 RNP-RA/18-0015, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program2018-04-16016 April 2018 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018 Report of Changes Pursuant to 10 CFR 50.59(d)(2) RNP-RA/18-0020, Notification of Change in Licensed Operator Status2018-02-20020 February 2018 Notification of Change in Licensed Operator Status RNP-RA/18-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2018-01-23023 January 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2018-01-0808 January 2018 Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0086, Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses2017-12-14014 December 2017 Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses RNP-RA/17-0081, Submittal of Change in Licensed Operators Medical Status2017-12-11011 December 2017 Submittal of Change in Licensed Operators Medical Status RNP-RA/17-0079, Operator License Renewal Application2017-12-0707 December 2017 Operator License Renewal Application RNP-RA/17-0071, Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks2017-10-19019 October 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks RNP-RA/17-0068, Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-09-28028 September 2017 Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0037, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers2017-09-27027 September 2017 License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/17-0043, Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-42017-09-22022 September 2017 Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4 RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report2017-09-18018 September 2017 Refueling Outage 30 Steam Generator Tube Inspection Report RNP-RA/17-0060, Notification of Change in Licensed Operator Status2017-08-10010 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0058, Notification of Change in Licensed Operator Status2017-08-0303 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0055, Transmittal of Core Operating Limits Report for Cycle 312017-07-26026 July 2017 Transmittal of Core Operating Limits Report for Cycle 31 RNP-RA/17-0042, Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2017-06-29029 June 2017 Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report2017-06-29029 June 2017 Submittal of Nine Day Inservice Inspection Summary Report RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RNP-RA/17-0038, (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report2017-05-0909 May 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) RNP-RA/17-0036, (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 342017-04-25025 April 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 34 RNP-RA/17-0031, Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 02017-04-20020 April 2017 Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 0 RNP-RA/17-0033, Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal2017-04-12012 April 2017 Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal RNP-RA/17-0014, Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0028, Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0021, Transmittal of Core Operating Limits Report2017-03-13013 March 2017 Transmittal of Core Operating Limits Report RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RNP-RA/17-0015, Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/17-0016, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2017-02-22022 February 2017 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RNP-RA/17-0015, H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/16-0100, Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-2272017-01-24024 January 2017 Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-227 RNP-RA/16-0097, Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/20154052016-12-15015 December 2016 Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/2015405 RNP-RA/16-0089, Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2016-11-10010 November 2016 Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/16-0090, Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise2016-11-10010 November 2016 Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016 Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-10-0505 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. 2021-02-18
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SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE, THIS TRANSMITTAL DOCUMENT IS DECONTROLLED Emest J . Kapopou/os Jr.
H B Robinson Steam Electnc Plant Unit 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 0 843 857 1701 F 843 8571319 Ernie.KaptJpoulo.Juht*tn~rgy.cnm 10 CFR 50.54(f)
Serial: RNP-RA/17-0033 APR 12 2017 ATTN : Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 DUKE ENERGY H.B. ROBINSON FLOOD HAZARD MITIGATING STRATEGIES ASSESSMENT (MSA) REPORT 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 Accident, dated March 12, 2012, (ADAMS Accession No. ML12056A046).
- 2. Duke Energy Letter, H. B. Robinson Steam Electric Plant, Unit No. 2, Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) 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 Accident, dated March 12, 2014, (ADAMS Accession No. ML14086A384).
- 3. 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 No. ML15146A390).
- 4. Nuclear Energy Institute (NEI), Report NEI 12-06, Rev. 2, Diverse And Flexible Coping Strategies (FLEX) Implementation Guide, dated December 2015, (ADAMS Accession No. ML16005A625).
- 5. NRC (2016), JLD-ISG-2012-01, Revision 1, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated January 22, 2016, (ADAMS Accession No. ML15357A163).
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE, THIS TRANSMITTAL DOCUMENT IS DECONTROLLED
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE, THIS TRANSMITTAL DOCUMENT IS DECONTROLLED United States Nuclear Regulatory Commission Serial: RNP-RA/17-0033 Page 2 of 4
- 6. NRC Letter, H. B. Robinson Steam Electric Plant, Unit No. 2 - Interim Staff Response to reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request
- Flood Causing Mechanism Reevaluation, dated December 23, 2015, (ADAMS Accession No. ML15357A065).
- 7. 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 No. ML13044A561).
- 8. 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 No. ML16355A381).
- 9. 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 No. ML14168A050).
- 10. Duke Energy Letter, Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
For H. B. Robinson Steam Electric Plant, Unit No. 2, dated August 19, 2015, (ADAMS Accession No. ML 115232A007).
- 11. NRC Process Outlined in COMSECY-15-0019, Closure Plan for the Reevaluation of Flooding Hazard for Operating Nuclear Power Plants, dated June 30, 2015, (ADAMS Accession No. ML15153A104).
- 12. Duke Energy Letter, H. B. Robinson Unit 2 - Submittal of Revision to Flooding Hazard Reevaluation Report to Provide a Revised Site Specific Local Intense Precipitation Storm, dated August 29, 2015, (ADAMS Accession No. ML15243A077).
- 13. Duke Energy Letter, H. B. Robinson Unit 2 - Submittal of Response to the NRC Request for Additional Information Regarding Flood Hazard Reevaluation Report, Related to Selection of the Dam Breach Trigger Elevation, dated December 15, 2015, (ADAMS Accession No. ML15349A796).
- 14. NRC email from Victor Hall, Project Manager, Japanese Lessons-Learned Division to Steve Callis and Dean Hubbard, Duke, Request for Additional Information - H.B. Robinson 2.1 Flood Hazard Reevaluation Report, dated March 4, 2015, (ADAMS Accession No. ML15065A085).
- 15. 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 No. ML14206A787).
- 16. NRC email from Juan Uribe, Project Manager, Japanese Lessons-Learned Division to Al Maysam and Paul Guill, Duke, Robinson RAI regarding NTTF 2.1 Flooding, dated December 14, 2015, (ADAMS Accession No. ML15348A340).
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE, THIS TRANSMITTAL DOCUMENT IS DECONTROLLED
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE, THIS TRANSMITTAL DOCUMENT IS DECONTROLLED United States Nuclear Regulatory Commission Serial: RNP-RA/17-0033 Page 3of4 Ladies and Gentlemen:
On March 12, 2012, the NRC issued Reference 1 to request information associated with Near-Term Task Force (NTTF) Recommendation 2.1 for Flooding. Enclosure 2 to the 50.54(f) letter requested that licensees reevaluate flood hazards for their respective sites using present-day methods and regulatory guidance used by the NRC staff when reviewing applications for early site permits (ESPs) and combined licenses (COLs). Per Reference 7, the NRC considers the reevaluated flood hazard to be "beyond the current design/licensing basis of operating plants."
For H. B. Robinson Steam Electric Plant, Unit 2 (RNP), the Flood Hazard Reevaluation Report (FHRR) was submitted on March 12, 2014 (Enclosure 1 to Reference 2) . The reevaluated flood hazard was further developed in response to a series of requests for additional information (RAI),
dated June 18, 2014, March 4, 2015, and December 14, 2015 (References 9, 14 and 16). Duke Energy responded to the RAI by letters dated July 9, 2014, May 26, 2015, and December 15, 2015 (References 15, 3 and 13). A revised FHRR with a new Local Intense Precipitation (LIP) and associated site drainage analysis that included a site-specific Probable Maximum Precipitation (ssPMP) evaluation was submitted on August 29, 2015 (Reference 12).
On December 23, 2015 (Reference 6), the NRC issued a revised Interim Staff Response (ISR) letter to the licensee. The purpose of the ISR letter is to inform Robinson that the flood hazard information provided is suitable for the assessment of the mitigating strategies developed in response to Order EA-12-049, "Requirements for Mitigation Strategies for Beyond-Design-Basis External Events." As stated in the ISR letter, the reevaluated flood hazard results for local intense precipitation, streams and rivers, failure of dams, storm surge, and seiche were not bounded by the current design-basis flood hazard. In response to the unbounded flood-causing mechanism, Duke Energy has completed an assessment of the mitigation strategies (MSA) developed in response to the Order EA-12-049.
By References 6 and 8, the NRC acknowledged that the Robinson FHRR and responses to the associated RAls provide the flood hazard input necessary to complete assessments consistent with the process outlined in COMSECY-15-0019 (Reference 11 ). Guidance for performing Mitigating Strategies Assessments (MSA) is contained in Appendix G of Reference 4, which was endorsed by the NRC (with conditions) by Reference 5.
The Robinson site Current Design Basis (CDB) is that external flooding does not exceed site grade; i.e., Robinson is a dry site. The FHRR concluded that several flooding mechanisms could result in site flooding that exceeds the CDB. In terms of the flood controlling parameters (i.e., flood height, inundation time, warning time), all applicable flood mechanisms are bounded by the LIP event and the Rivers and Streams Probable Maximum Flood (PMF) event. FLEX strategies as described in the Final Integrated Plan (Reference 10) are impacted by the LIP and PMF events.
Based on impacts to the FLEX strategies, Robinson developed Alternate Mitigating Strategies (AMSs) for the LIP and PMF events (NEI 12-06, Revision 2. Appendix G.4.3). The enclosure to this letter provides the Alternate Mitigating Strategies based on the Robinson FHRR.
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE, THIS TRANSMITTAL DOCUMENT IS DECONTROLLED
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE, THIS TRANSMITTAL DOCUMENT IS DECONTROLLED United States Nuclear Regulatory Commission Serial: RNP-RA/17-0033 Page 4of4 The enclosure contains Security-Related Information, withhold from public disclosure under 10 CFR 2.390, in accordance with 10 CFR 2.390(d)(1 ).
There are no regulatory commitments associated with this letter.
Should you have any questions regarding this matter, please contact Mr. Tony Pila, Manager-Nuclear Regulatory Affairs, at (843) 857-1409.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on t 2 Af@.\L
~~~~~~~~-
zo l7 Sincerely, Ernest J. Kapopoulos Jr.
Site Vice President EJK/am
Enclosure:
ROBINSON NUCLEAR PLANT FLOOD HAZARD MITIGATING STRATEGIES ASSESSMENT FOR NEW FLOOD HAZARD INFORMATION cc: NRC Resident Inspector, HBRSEP Unit No. 2 Juan Uribe, NRC Project Manager, NRR, Japan Lessons-Learned Division NRC Regional Administrator, NRC, Region II Dennis Galvin, NRC Project Manager, NRR SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE, THIS TRANSMITTAL DOCUMENT IS DECONTROLLED