Letter Sequence Other |
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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
[Table View] |
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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
MONTHYEARIR 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
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
IR 05000461/20230032023-11-0808 November 2023
Integrated Inspection Report 05000461/2023003
ML22300A2212023-11-0202 November 2023
Preliminary Decommissioning Cost Estimate and Fuel Management Plan
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
IR 05000461/20233012023-09-12012 September 2023
NRC Initial License Examination Report 05000461/2023301
RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023
Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station
RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
IR 05000461/20234202023-08-29029 August 2023
Security Baseline Inspection Report 05000461/2023420
RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023
Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
IR 05000461/20230022023-08-0404 August 2023
Integrated Inspection Report 05000461/2023002
RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023
Supplemental Information Related to Request for Partial Site Release
ML23209A8102023-07-28028 July 2023
05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23198A0152023-07-27027 July 2023
License Renewal Application Public Meeting Summary of Pre-Submittal Meeting
ML23202A0992023-07-24024 July 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000461/2023004
ML23200A2592023-07-24024 July 2023
June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary
IR 05000461/20234012023-07-19019 July 2023
Cyber Security Inspection Report 05000461/2023401
ML23194A1662023-07-19019 July 2023
Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Partial Site Release
ML23191A8772023-07-11011 July 2023
Operator Licensing Examination Approval Clinton Power Station July 2023
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
RS-23-073, Request for Partial Site Release2023-06-0707 June 2023
Request for Partial Site Release
IR 05000461/20230102023-05-26026 May 2023
Triennial Fire Protection Inspection Report 05000461/2023010
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
ML23143A3182023-05-23023 May 2023
Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1
IR 05000461/20230012023-05-0404 May 2023
Integrated Inspection Report 05000461/2023001
ML23118A3472023-05-0101 May 2023
County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
ML23081A0382023-04-25025 April 2023
County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23061A1632023-03-0303 March 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
IR 05000461/20220062023-03-0101 March 2023
Annual Assessment Letter for Clinton Power Station, Unit 1 (Report 05000461/2022006)
RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023
Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air
ML23031A2972023-03-0101 March 2023
Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
ML23039A1852023-02-10010 February 2023
Integrated Inspection Report 05000461/2022004 07201046/2022001
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
IR 05000461/20220112023-01-27027 January 2023
Biennial Problem Identification and Resolution Inspection Report 05000461/2022011
RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023
Application to Adopt TSTF-332, ECCS Response Time Testing
ML23005A0682023-01-0505 January 2023
Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000461/2023010
ML22341A6042022-12-0808 December 2022
Confirmation of Initial License Examination
IR 05000461/20224022022-12-0606 December 2022
Security Baseline Inspection Report 05000461/2022402
RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022
Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
2024-02-02
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 3, 2015 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
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. ML14079A415), 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. ML12053A340). 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. ML12054A735). On March 30, 2015, the Commission provided Staff Requirements Memoranda (SRM) (ADAMS Accession No. ML15089A236) 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. ML14309A256), 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. ML15174A257). 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. ML15209A682). 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.
Tekia Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosure:
Summary of Results of Flooding Hazard Re-Evaluation Report cc w/encl: Distribution via Listserv
ENCLOSURE:
SUMMARY
TABLE OF REEVALUATED FLOOD HAZARD LEVELS
Clinton 1 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Run up Hazard
Elevation
~~~~~-
Local Intense Precipitation Local Intense Precipitation and 736.8 ft MSL Not 736.8 ft MSL FHRR Section 2.2.1 and Table 4.0.2 Associated Drainage applicable Streams and Rivers No impact on No impact on No impact on FHRR Section 2.2.2 the site the site the site identified identified identified 1
Failure of Dams and Onsite Water Control/Storage Structures
. I No impact on No impact on No impact on : FHRR Section 2.2.3 the site the site the site 1 1
identified identified identified I I Storm Surge Probable maximum flooding on No impact on No impact on No impact on 1
FHRR Section 2.2.5 cooling pond the site the site ' the site identified identified i identified I
I Seiche I
No impact on No impact on No impact on FHRR Section 2.2.5 the site the site the site I
identified identified identified I
Tsunami 1
I i
No .impact on IN o .impact on No impact on FHRR Section 2.2.6 the site ; the site the site identified identified identified Ice-Induced Flooding I
No impact on I No impact on No impact on FHRR Section 2.2.7 the site
- the site the site identified identified identified 1
Channel Migrations/Diversions No impact on No impact on No impact on FHRR Section 2.2.8 the site the site the site identified identified identified Note: Reported values are rounded to the nearest one-tenth of a foot.
PKG ML15230A012; LTR: ML15212A010; ENCL: ML15219A645 *via email OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRO/DSEA/RHM2/TR* NRO/DSEA/RHM2/BC*
NAME AMinarik Slent PChaput ARivera-Varona DATE 8 / 25 /15 07/31/15 08/17/15 08/17/15 OFFICE NRR/JLD/JHMB/BC OGC* NRR/JLD/JHMB/PM NAME MShams SClark TGovan DATE 8 / 28 /15 08/14/15 9 / 3 /15
