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{{Adams | |||
| number = ML18348B112 | |||
| issue date = 12/14/2018 | |||
| title = Fermi 2, 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 (Order Number EA-13-109 | |||
| author name = Polson K J | |||
| author affiliation = DTE Energy | |||
| addressee name = | |||
| addressee affiliation = NRC/Document Control Desk, NRC/NRR | |||
| docket = 05000341 | |||
| license number = NPF-043 | |||
| contact person = | |||
| case reference number = EA-13-109, NRC-18-0054 | |||
| document type = Letter, Operating Plan, Report, Miscellaneous | |||
| page count = 94 | |||
| project = | |||
| stage = Other | |||
}} | |||
=Text= | |||
{{#Wiki_filter:1WheretwoADAMSaccessionnumbersarelisted,thefirstisthereferencedocumentandthesecondistheNRCendorsementofthatdocument.2NEI13 02Revision1AppendixJcontainsHCVSFAQ 01throughHCVS FAQ 09. | |||
WetwelllevelWetwellLevelinstrumentrange(T50R804B):12'to+4.66'Spilloverheight1.7'Freeboardheight4.66'Additionalfreeboardheight10.33'DrywellfloorWetwellvolumeversuslevel,~6700gallons/inchEstimateoftherateoflevelchangeinthesuppressionpoolforvariousSAWAflowrates:500gpm:13.4minutes/inch;100gpm:67minutes/inch.Wetwellbottomheight | |||
Bus72C FcontainspowerforRHRValvesusedforSAWAalignment | |||
SAWAHosepathshowninRedRefuelinglocationsinBlue Flow/flowcontrollocationforSAWA/SAWMshowninGreen FLEXAirinYellow HCVS Panel HCVSPipe CoreSourcetermRHRExternalConnection(SAWA Actions)HCVSVentPipeSourceTermSFPActions(RB) HCVSActions(PrimaryBlue)HCVSActions(SecondaryRed) | |||
CoreSourceTerm HCVSVentPi p e SAWARBAlignmentActions HCVSSecondaryActions Red HCVSPrimaryActionsBlue(DCShedding) | |||
CoreSourceTerm HCVSPipeSourceTermHCVSAlternateControlLocationSAWAElectricalActionsHCVSPrimaryActionsandcontrollocation CoreSourceTerm HCVSPipeSourceTermHCVSPrimaryActionsBlue CoreSourceTermHCVSPipeSourceTerm HCVSPipeInspectionPrimary/SecondaryActionsinfirsthour | |||
3SeeUFSAR3.11/7.6.1.12forqualificationcodeofrecordIEEE3231974andIEEE3441975.Wherelatercodeyearsarereferenced,thiswasreconciledinthedesignprocess. | |||
4EvaluationtimingisfromNEI13 02tosupportradiologicalevaluations.}} | |||
Revision as of 04:46, 22 February 2019
| ML18348B112 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/14/2018 |
| From: | Polson K J DTE Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-13-109, NRC-18-0054 | |
| Download: ML18348B112 (94) | |
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[Table view]Request for Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic NRC-19-0067, Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval2019-10-0808 October 2019 Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval NRC-18-0054, 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 (Order Number EA-13-109)2018-12-14014 December 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 (Order Number EA-13-109) NRC-18-0022, Submittal of 2017 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2018-04-19019 April 2018 Submittal of 2017 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML17305A0382017-10-16016 October 2017 Enclosures 1-6: 10CFR50.59 Evaluation Summary Report, Commitment Management Report, Revisions to Technical Requirements Manual and Technical Specifications Bases NRC-17-0026, Submittal of 2016 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2017-04-0606 April 2017 Submittal of 2016 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML16231A4432016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) NRC-16-0026, Submittal of 2015 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2016-04-27027 April 2016 Submittal of 2015 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML16057A7592016-02-25025 February 2016 Comments on Advance Notice of Proposed Rulemaking on Regulatory Improvements for Decommissioning Power Reactors NRC-16-0014, Comments on the Nrc'S Safety Evaluation Report with Open Items Related to the License Renewal2016-02-25025 February 2016 Comments on the Nrc'S Safety Evaluation Report with Open Items Related to the License Renewal NRC-15-0085, Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask NRC-15-0043, Submittal of 2014 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2015-04-28028 April 2015 Submittal of 2014 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-14-0058, 10 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the TN-RAM Cask Due to As-Built Discrepancies Identified by Cask Certificate Holder2014-08-13013 August 2014 10 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the TN-RAM Cask Due to As-Built Discrepancies Identified by Cask Certificate Holder NRC-14-0061, Post Accident Monitoring Report Regarding Inoperable Instrumentation2014-08-0707 August 2014 Post Accident Monitoring Report Regarding Inoperable Instrumentation ML14093A7662014-05-0606 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NRC-14-0030, Submittal of 2013 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2014-04-28028 April 2014 Submittal of 2013 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-13-0052, CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time2013-09-0909 September 2013 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time NRC-13-0017, Submittal of 2012 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2013-04-26026 April 2013 Submittal of 2012 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-13-0013, DTE Electric Submittal of Flooding Hazard Reevaluation Report in Response to March 12, 2012 Information Request Regarding Flood Protection Evaluations2013-03-0808 March 2013 DTE Electric Submittal of Flooding Hazard Reevaluation Report in Response to March 12, 2012 Information Request Regarding Flood Protection Evaluations ML12341A3702012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-109 Through Page D-211 ML12341A3582012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-247 Through C-335 ML12341A3612012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-336 Through C-426 ML12341A3642012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-43 Through C-149 NRC-12-0075, TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-212 Through End2012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-212 Through End ML12341A3692012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-8 Through Page D-108 ML12341A3682012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-629 Through Appendix D, Page D-7 ML12341A3672012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-530 Through C-628 ML12341A3662012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-427 Through C-529 ML12341A3632012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Cover Through Appendix C, Page C-42 ML12341A3652012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-150 Through C-246 NRC-12-0067, Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases2012-11-0505 November 2012 Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants NRC-11-0036, Enrico Fermi Atomic Power Plant, Unit 1 - License Termination Plan, Revision 42011-06-29029 June 2011 Enrico Fermi Atomic Power Plant, Unit 1 - License Termination Plan, Revision 4 NRC-09-0080, Impact of Revised Unsaturated Zone Thickness on Fermi 1 Soil Dcgl Values2009-11-30030 November 2009 Impact of Revised Unsaturated Zone Thickness on Fermi 1 Soil Dcgl Values ML0929604282009-10-23023 October 2009 Independent Spent Fuel Storage Installation Control of Heavy Loads Inspection Document Request NRC-09-0025, Submittal of 2008 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2009-04-17017 April 2009 Submittal of 2008 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML0818304092008-06-30030 June 2008 GE-NE-0000-0047-1716-R1, DTE Energy Enrico Fermi 2, Safer/Gestr Loss-of-Coolant Accident Analysis for GE11 Fuel. ML0818304112008-06-30030 June 2008 GE-NE-0000-0030-6565-R1, DTE Energy, Enrico Fermi 2, Safer/Gestr Loss-of-Coolant Accident Analysis for GE14 Fuel NRC-08-0035, Submittal of 2007 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2008-04-28028 April 2008 Submittal of 2007 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML0723403152007-08-22022 August 2007 Staff Evaluation of BWRVIP Response to Nuclear Regulatory Commission Safety Evaluation of BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (BWRVIP-14-A) NRC-07-0029, Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator2007-05-23023 May 2007 Response to Request for Additional Information Regarding License Amendment Request for Extension of Completion Time for an Inoperable Emergency Diesel Generator NRC-06-0058, Groundwater Protection - Data Collection Questionnaire2006-07-28028 July 2006 Groundwater Protection - Data Collection Questionnaire ML0414602392004-05-17017 May 2004 Rev 38 to Tlcomp, Restricted Engineered Components List. ML0626304082004-03-0101 March 2004 PSEG Nuclear, LLC Salem/Hope Creek Safety Culture Assessment ML0318903172003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-For-Duty Enhancements for Nuclear Security Force Personnel for Fermi 2 NRC-03-0018, Submittal of Changes to Emergency Response Data System for Integrated Plant Computer System Replacement2003-03-25025 March 2003 Submittal of Changes to Emergency Response Data System for Integrated Plant Computer System Replacement NRC-02-0013, Annual Report for 20012002-04-16016 April 2002 Annual Report for 2001 2021-05-17 |
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1WheretwoADAMSaccessionnumbersarelisted,thefirstisthereferencedocumentandthesecondistheNRCendorsementofthatdocument.2NEI13 02Revision1AppendixJcontainsHCVSFAQ 01throughHCVS FAQ 09.
WetwelllevelWetwellLevelinstrumentrange(T50R804B):12'to+4.66'Spilloverheight1.7'Freeboardheight4.66'Additionalfreeboardheight10.33'DrywellfloorWetwellvolumeversuslevel,~6700gallons/inchEstimateoftherateoflevelchangeinthesuppressionpoolforvariousSAWAflowrates:500gpm:13.4minutes/inch;100gpm:67minutes/inch.Wetwellbottomheight
Bus72C FcontainspowerforRHRValvesusedforSAWAalignment
SAWAHosepathshowninRedRefuelinglocationsinBlue Flow/flowcontrollocationforSAWA/SAWMshowninGreen FLEXAirinYellow HCVS Panel HCVSPipe CoreSourcetermRHRExternalConnection(SAWA Actions)HCVSVentPipeSourceTermSFPActions(RB) HCVSActions(PrimaryBlue)HCVSActions(SecondaryRed)
CoreSourceTerm HCVSVentPi p e SAWARBAlignmentActions HCVSSecondaryActions Red HCVSPrimaryActionsBlue(DCShedding)
CoreSourceTerm HCVSPipeSourceTermHCVSAlternateControlLocationSAWAElectricalActionsHCVSPrimaryActionsandcontrollocation CoreSourceTerm HCVSPipeSourceTermHCVSPrimaryActionsBlue CoreSourceTermHCVSPipeSourceTerm HCVSPipeInspectionPrimary/SecondaryActionsinfirsthour
3SeeUFSAR3.11/7.6.1.12forqualificationcodeofrecordIEEE3231974andIEEE3441975.Wherelatercodeyearsarereferenced,thiswasreconciledinthedesignprocess.
4EvaluationtimingisfromNEI13 02tosupportradiologicalevaluations.
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