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MONTHYEARRS-15-064, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report2015-03-12012 March 2015 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report Project stage: Request ML15093A3112015-03-16016 March 2015 NRR E-mail Capture - Request for Additional Information: Clinton Flooding Hazard Reevaluation Report Project stage: RAI RS-15-110, Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2015-05-0505 May 2015 Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report Project stage: Response to RAI ML15148A2862015-07-21021 July 2015 Nuclear Regulatory Commission Plan for the Audit of Exelon Generation Company, Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 -Flooding Project stage: Other ML15219A6452015-09-0303 September 2015 Tables 1 and 2 Project stage: Other ML15212A0102015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation Project stage: Other ML15212A7272015-09-0404 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request Flood-Causing Mechanism Reevaluation Project stage: Other ML15219A6672015-09-0404 September 2015 Tables 1 and 2 Project stage: Request ML15279A1342015-10-27027 October 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request-Flood-Causing Mechanism Reevaluation Project stage: Other ML15321A0342015-11-18018 November 2015 Correction to Staff Assessment of Response to Request for Information Pursuant to 10 CFR 50.54(f)-Flood Causing Mechanisms Reevaluation Project stage: RAI RS-16-055, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-03-24024 March 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal Project stage: Other 2015-05-05
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Category:Graphics incl Charts and Tables
MONTHYEARML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15219A6452015-09-0303 September 2015 Tables 1 and 2 ML15212A0102015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation RA-13-081, Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term.2013-09-16016 September 2013 Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term. RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites2013-09-12012 September 2013 Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010 Re-Submittal of the Exelon Cyber Security Plan RS-08-141, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2008-10-31031 October 2008 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RA-08-057, Unit 1, Application for Approval of License Transfers2008-06-20020 June 2008 Unit 1, Application for Approval of License Transfers ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0617102122006-06-15015 June 2006 Oak Ridge Institute for Science and Education - Analytical Results for 21 Water Samples, Batch One, from the Vicinity of the Clinton Station, Clinton, Illinois (Inspection Report No. 050-00461/2006-004) (Rfta No. 06-001) ML0709202062005-01-31031 January 2005 Cps/Usar, Chapter 5, Reactor Coolant System and Connected System, Revision 11 ML0709302252005-01-31031 January 2005 Cps/Usar, Chapter 6, Engineered Safety Features, Revision 11 ML0709302282005-01-31031 January 2005 Cps/Usar, Chapter 7, Instrumentation and Control Systems, Revision 11 ML0709302362005-01-31031 January 2005 Cps/Usar, Chapter 10, Steam and Power Conversion System, Revision 11 ML0709302402005-01-31031 January 2005 Cps/Usar, Chapter 11, Radioactive Waste Management, Revision 11 ML0709302452005-01-31031 January 2005 Cps/Usar, Chapter 12, Radiation Protection, Revision 11 ML0709302542005-01-31031 January 2005 Cps/Usar, Chapter 14, Initial Test Program, Revision 11 ML0709302592005-01-31031 January 2005 Cps/Usar, Chapter 15, Accident Analyses, Revision 11 ML0709303592005-01-31031 January 2005 Cps/Usar, Appendix C, Computer Programs, Revision 11 ML0709303602005-01-31031 January 2005 Cps/Usar, Appendix D, Requirements Resulting from TMI-2 Accident, Revision 11 2016-03-11
[Table view] Category:Letter
MONTHYEARML24211A2302024-09-11011 September 2024 – Request for Partial Site Release for Facility Operating License No. NPF-62 RS-24-087, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2024-09-0909 September 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station IR 05000461/20240112024-09-0909 September 2024 Commercial Grade Dedication Inspection Report 05000461/2024011 IR 05000461/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Clinton Power Station (Report 05000461/2024005) ML24222A3952024-08-23023 August 2024 Regulatory Audit Report to Support the Review of the Amendments to Revise Reactor Water Cleanup Valve Isolation Timing IR 05000461/20240022024-08-0909 August 2024 Integrated Inspection Report 05000461/2024002 ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24220A2772024-08-0707 August 2024 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000461/2025010 ML24212A2212024-08-0202 August 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-LNE-0000) (Docket Number: 50-461) ML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing ML24158A0772024-07-0303 July 2024 Notice of Consideration of Approval of Partial Site Release, Public Meeting, and Request for Comments (EPID L-2023-LLA-0088) - Letter ML24163A3252024-06-28028 June 2024 Aging Management Regulatory Audit Plan ML24163A3242024-06-28028 June 2024 LRA - Portal Letter ML24179A3112024-06-27027 June 2024 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24176A0272024-06-25025 June 2024 Confirmation of Initial License Examination, July 2025 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes IR 05000461/20240122024-05-20020 May 2024 Biennial Problem Identification and Resolution Inspection Report Report 05000461/2024012 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20240012024-05-0707 May 2024 Integrated Inspection Report 05000461/2024001 ML24103A1032024-05-0101 May 2024 SHPO Consultation Letter for Clinton License Renewal ML24120A3462024-04-30030 April 2024 Ltr. to Douglas Lankford, Chief, Miami Tribe of Oklahoma; Re., CPS Section 106 Consultation ML24120A3452024-04-30030 April 2024 Ltr. to Lester Randell, Chairman, Kickapoo Tribe of Indians of the Kickapoo Reservation in Kansas; Re., CPS Section 106 Consultation ML24103A0992024-04-30030 April 2024 Achp Scoping Letter for Clinton License Renewal ML24120A3432024-04-30030 April 2024 Ltr. to Darwin Kaskaske, Chairman, Kickapoo Tribe of Oklahoma; Re., CPS Section 106 Consultation ML24120A3442024-04-30030 April 2024 Ltr. to Gena Kakkak, Chairman, Menominee Indian Tribe of Wisconsin; Re., CPS Section 106 Consultation ML24103A1152024-04-30030 April 2024 Ltr. to Geoffrey Standing Bear, Principal Chief, the Osage Nation; Re., CPS Section 106 Consultation RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24107B0312024-04-29029 April 2024 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24089A2222024-04-11011 April 2024 LRA - Acceptance and Opportunity for Hearing - Letter ML24092A3452024-04-0101 April 2024 Updated Safety Analysis Report (Usar), Revision 23 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3552024-04-0101 April 2024 Request for Information for NRC License Renewal Inspection: Inspection Report 05000461/2024010 RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24045A1422024-02-29029 February 2024 License Renewal Application Receipt and Availability - Letter IR 05000461/20230062024-02-28028 February 2024 Annual Assessment Letter for Clinton Power Station (Report 05000461/2023006) ML24054A7112024-02-23023 February 2024 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000461/2024011 ML24045A0242024-02-14014 February 2024 Application for Renewed Operating License RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release ML23338A1102024-02-0606 February 2024 Issuance of Amendment No. 252 Revision of Technical Specification 3.8.3, Diesel Fuel Oil, and Starting Air IR 05000461/20230042024-02-0202 February 2024 Integrated Inspection Report 05000461/2023004 ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation ML24004A0792024-01-18018 January 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0041 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 2024-09-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 September 3, 2015
SUBJECT:
CLINTON POWER STATION, UNIT NO. 1 -INTERIM STAFF RESPONSE TO REEVALUATED FLOOD HAZARDS SUBMITTED IN RESPONSE TO 10 CFR 50.54(f) INFORMATION REQUEST-FLOOD-CAUSING MECHANISM REEVALUATION (TAC NO. MF3654)
Dear Mr. Hanson:
The purpose of this letter is to provide a summary of the U.S. Nuclear Regulatory Commission (NRC) staff's assessment of the re-evaluated flood-causing mechanisms described in the March 12, 2014 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 14079A415), flood hazard reevaluation report (FHRR) submitted by Exelon Generation Company, LLC (Exelon, the licensee) for Clinton Power Station, Unit No. 1 (Clinton), as well as supplemental information resulting from requests for additional information and audits. By letter dated March 12, 2012, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50. 54(f) (hereafter referred to as the 50. 54(f) letter) (ADAMS Accession No. ML 12053A340).
The request was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to re-evaluate flood-causing mechanisms using present-day methodologies and guidance.
Concurrently, with the reevaluation of flooding hazards, licensees were required to develop and implement mitigating strategies in accordance with NRC Order EA-12-049, "Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML 12054A735).
On March 30, 2015, the Commission provided Staff Requirements Memoranda (SRM) (ADAMS Accession No. ML 15089A236) to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards," dated November 21, 2014 (ADAMS Accession No. ML 14309A256), affirming that licensees need to address the reevaluated flooding hazards within their mitigating strategies for beyond-design-basis external events. The NRC staff has reviewed the flood hazard information submitted by the licensee and has summarized the results of the review in the table provided as an Enclosure to this letter.
B. Hanson Table 1 provides the current design-basis flood hazard mechanisms.
All the reevaluated flood hazard mechanisms at Clinton are bounded by the current design-basis.
The NRC staff has concluded that the licensee's reevaluated flood hazards information, as summarized in the Enclosure, is suitable for the assessment of mitigating strategies developed in response to Order EA-12-049 (i.e., defines the mitigating strategies flood hazard information described in guidance documents currently being finalized by the industry and NRC staff) for Clinton. Further, the NRC staff has concluded that the licensee's reevaluated flood hazard information is a suitable input for other assessments associated with Near-Term Task Force Recommendation 2.1 "Flooding".
The NRC staff plans to issue a staff assessment documenting the basis for these conclusions at a later time. In addition, NEI 12-06 "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" is currently being revised. This revision will include a methodology to perform a Mitigating Strategies Assessment (MSA) with respect to the reevaluated flood hazards. Once this methodology is endorsed by the NRC, flood event duration parameters and applicable flood associated effects should be considered as part of the Clinton MSA. The NRC staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood-related associated effects developed by the licensee during the NRC staff's review of the MSA. Because the reevaluated flood hazard mechanisms at Clinton are bounded by the current design-basis, it is unnecessary for the licensee to perform an integrated assessment or focused evaluation, as described in NRC letter, "Coordination of Request for Information Regarding Flooding Hazard Reevaluation and Mitigating Strategies for Beyond Design Bases External Events" (ADAMS Accession No. ML 15174A257).
This letter describes the changes in the NRC's approach to the flood hazard reevaluations that were approved by the Commission in its SRM to COMSECY-15-0019, "Closure Plan for the Reevaluation of Flooding Hazards for Operating Nuclear Power Plants" (ADAMS Accession No. ML 15209A682).
Therefore, the NRC staff confirms that the licensee responded appropriately to Enclosure 2 of the 50.54(f) letter.
B. Hanson If you have any questions, please contact me at (301) 415-6197 or e-mail at Tekia.Govan@nrc.gov.
Docket No. 50-461
Enclosure:
Summary of Results of Flooding Hazard Re-Evaluation Report cc w/encl: Distribution via Listserv Tekia Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation ENCLOSURE:
SUMMARY
TABLE OF REEVALUATED FLOOD HAZARD LEVELS Clinton 1 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Local Intense Precipitation Local Intense Precipitation and Associated Drainage Streams and Rivers 1 Failure of Dams and Onsite Water Control/Storage Structures Storm Surge Probable maximum flooding on cooling pond I Seiche I I 1 Tsunami i Ice-Induced Flooding 1 Channel Migrations/Diversions Stillwater Elevation Waves/ Run up Design Basis Hazard Elevation Reference 736.8 ft MSL Not applicable 736.8 ft MSL FHRR Section 2.2.1 and Table 4.0.2 No impact on No impact on No impact on the site the site the site identified identified identified No impact on No impact on N . I o impact on : the site the site the site 1 identified identified identified 1 No impact on the site identified I No impact on 1 No impact on the site ' the site identified i identified I I No impact on No impact on No impact on the site the site the site identified identified I N . IN . o impact on o impact on the site ; the site identified identified I No impact on I No impact on the site
- the site identified identified identified No impact on the site identified No impact on the site identified No impact on the site identified No impact on No impact on the site the site identified identified I FHRR Section 2.2.2 FHRR Section 2.2.3 FHRR Section 2.2.5 FHRR Section 2.2.5 FHRR Section 2.2.6 FHRR Section 2.2.7 FHRR Section 2.2.8 Note: Reported values are rounded to the nearest one-tenth of a foot.
B. Hanson If you have any questions, please contact me at (301) 415-6197 or e-mail at Tekia.Govan@nrc.gov.
Docket No. 50-461
Enclosure:
Sincerely, /RAJ Tekia Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Summary of Results of Flooding Hazard Re-Evaluation Report cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC TGovan, NRR RidsNrrDorllpl3-2 Resource RidsRgn3MailCenter Resource RidsOpaMail Resource ARivera-Varona, NRO MWillingham, NRO MShams, NRR JLD R/F LQuinn-Willingham, NRO RidsNrrDorl Resource RidsNrrLASLent RidsAcrsAcnw_MailCtr Resource KErwin, NRO RRivera-Lugo, NRO RidsNRRJLD Resource RidsNroDsea Resource RidsNrrPMClinton Resource RidsOgcMailCenter Resource CCook, NRO ACampbell, NRO BHarvey, NRO ADAMS Accession No.PKG ML 15230A012; LTR: ML 15212A010; ENCL: ML 15219A645
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