ML15274A009
| ML15274A009 | |
| Person / Time | |
|---|---|
| Issue date: | 10/01/2015 |
| From: | Office of New Reactors |
| To: | |
| Bladey C | |
| References | |
| RIN 3150-AI85 | |
| Download: ML15274A009 (3) | |
Text
ESBWR Design Certification Final Rule Regulatory History Index (DRAFT)
ADAMS Accession No./
Document web link/ Federal Register citation Proposed Rule Documents:
SECY-11-0006, Proposed RuleESBWR Design Certification .......................................................................................... ML102220172 Staff Requirements Memorandum for SECY-11-0006, Proposed RuleESBWR Design Certification ............................. ML110670047 General Electric Company Application for Final Design Approval and Design Certification of ESBWR Standard Plant De- ML052450245 sign.
ESBWR Design Control Document, Revision 9 ........................................................................................................................ ML103440266 ESBWR Final Safety Evaluation Report (NUREG-1966) ......................................................................................................... ML14100A304 ESBWR FSER Final Chapters .................................................................................................................................................. ML103470210 Final Design Approval for the Economic Simplified Boiling Water Reactor ............................................................................. ML110540310 ESBWR Draft Environmental Assessment ................................................................................................................................ ML102220247 ESBWR Proposed Rule Federal Register Notice, 76 FR 16549, March 24, 2011 ................................................................ ML110610353 Public Comments on the March 2011 Proposed Rule:
Comment (1) from Farouk D. Baxter on Environmental Impact Statement for Two AP1000 Units at Levy County Site ........ ML102350160 Comment submission S1 from Paul C. Daugherty ................................................................................................................... ML110880057 Comment submission S2 from Farouk D. Baxter ..................................................................................................................... ML110880315 Comment submission S3 from Patricia T. Birnie, Chair, General Electric Stockholders Alliance ........................................... ML11158A088 Comment submission S4 from anonymous .............................................................................................................................. ML11187A303 Comment submission P1, Emergency Petition To Suspend All Pending Reactor Licensing Decisions and Related Rule- ML111040472 making Decisions Pending Investigation of Lessons Learned From Fukushima Daiichi Nuclear Power Station Accident (initial).
Comment submission P2, Emergency Petition To Suspend All Pending Reactor Licensing Decisions and Related Rule- ML111080855 making Decisions Pending Investigation of Lessons Learned From Fukushima Daiichi Nuclear Power Station Accident (amended).
Comment submission P3, Declaration of Dr. Arjun Makhijani in Support of Emergency Petition To Suspend All Pending ML111100618 Reactor Licensing Decisions and Relating Rulemaking Decisions Pending Investigation of Lessons Learned From Fukushima Daiichi Nuclear Power Station Accident.
Comment submission P4, Comment of Jerald Head on Behalf of GE-Hitachi Nuclear Energy Opposing Petition To Sus- ML11124A103 pend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions Pending Investigation of Lessons Learned From Fukushima Daiichi Nuclear Power Station Accident.
Comment submission P5, Petitioners Reply to Responses to Emergency Petition To Suspend All Pending Reactor Li- ML111260637 censing Decisions and Related Rulemaking Decisions Pending Investigation of Lessons Learned From Fukushima Daiichi Nuclear Power Station Accident.
Comment submission P6, Comments of Terry J. Lodge on PR 52, NEPA Requirement To Address Safety and Environ- ML112430118 mental Implications of the Fukushima Task Force Report From ESBWR, Fermi 3 Intervenors.
Public Comments CompilationFinal RuleESBWR Design Certification (RIN 3150-AI85) ................................................ ML113130141 Supplemental Safety Evaluation for the ESBWR Design Certification:
Advanced Supplemental Safety Evaluation Report for the Economic Simplified Boiling-Water Reactor Standard Plant De- ML14043A134 sign.
Supplemental Safety Evaluation Report for the Economic Simplified Boiling-Water Reactor Standard Plant Design ............ ML14155A333 Supplemental Proposed Rule Documents:
ESBWR Design Control Document, Rev. 10 ............................................................................................................................ ML14104A929 ESBWR Supplemental Proposed Rule Federal Register Notice, 79 FR 25715, May 6, 2014 .............................................. ML14043A508 Final Rule Documents:
SECY-14-0081, Final RuleESBWR Design Certification .................................................................................................. ML111730346 Staff Requirements Memorandum for SECY-14-0081, Final RuleESBWR Design Certification ..................................... ML14259A545 ESBWR Final Environmental Assessment ................................................................................................................................ ML111730382 Other Documents Relevant to the ESBWR Rulemaking:
NEDO-33306, Revision 4, ESBWR Severe Accident Mitigation Design Alternatives .......................................................... ML102990433 NEDO-33312, Rev. 5, ESBWR Steam Dryer Acoustic Load Definition ............................................................................... ML13344B157
2 ADAMS Accession No./
Document web link/ Federal Register citation NEDO-33313, Rev. 5, ESBWR Steam Dryer Structural Evaluation ..................................................................................... ML13344B158 NEDO-33338, Revision 1, ESBWR Feedwater Temperature Operating Domain Transient and Accident Analysis ........... ML091380173 NEDO-33408P, Revision 5, ESBWR Steam DryerPlant-Based Load Evaluation Methodology, PBLE01 Model Descrip- ML13344B159 tion.
Commission Memorandum and Order (CLI-11-05), September 9, 2011 (available on the NRC Web site in Volume 74 at ML112521106 http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0750/).
Commission Order, Scheduling Order of the Secretary Regarding Petitions To Suspend Adjudicatory, Licensing and ML111101277 Rulemaking Activities (PR 52 re ESBWR Design Certification).
Order EA-12-049, Order Modifying Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design- ML12054A735 Basis External Events.
Order EA 12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation ........................... ML12054A679 Staff Requirements Memorandum for SECY-90-377, Requirements for Design Certification Under 10 CFR Part 52 ...... ML003707892 SECY-94-084, Policy and Technical Issues Associated With the Regulatory Treatment of Non-Safety Systems in Pas- ML003708068 sive Plant Designs.
Staff Requirements Memorandum for SECY-96-077, Certification of Two Evolutionary Designs ...................................... ML003754873 SECY-96-077, Certification of Two Evolutionary Designs ................................................................................................... ML003708129 Staff Requirements Memorandum for SECY-11-0093, Near-Team Report and Recommendations for Agency Actions ML112310021 Following the Events in Japan.
Enclosure:
The Near-Term Task Force Review of Insights From the Fukushima Dai-ichi Accident ........ ML111861807 Staff Requirements Memorandum for SECY-11-0117, Proposed Charter for the Longer-Term Review of Lessons ML112920034 Learned From the March 11, 2011, Japanese Earthquake and Tsunami.
SECY-11-0117, Proposed Charter for the Longer-Term Review of Lessons Learned From the March 11, 2011, Japa- ML11231A723 nese Earthquake and Tsunami.
SECY-11-0124, Recommended Actions To Be Taken Without Delay From The Near-Term Task Force Report ............. ML11245A127 SECY-11-0137, Prioritization of Recommended Actions To Be Taken in Response to Fukushima Lessons Learned ..... ML11269A204 Staff Requirements Memorandum for SECY-12-0025, Proposed Orders and Requests for Information in Response to ML120690347 Lessons Learned From Japans March 11, 2011, Great To hoku Earthquake and Tsunami.
SECY-12-0025, Proposed Orders and Requests for Information in Response to Lessons Learned From Japans March ML12039A103 11, 2011, Great To hoku Earthquake and Tsunami.
SECY-14-0046, Fifth 6-Month Status Update on Response to Lessons Learned From Japans March 11, 2011, Great ML14064A523 To hoku Earthquake and Subsequent Tsunami.
Regulatory Guide 1.13, Spent Fuel Storage Facility Design Basis ....................................................................................... ML070310035 Regulatory Guide 1.20, Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and ML070260376 Initial Startup Testing.
Regulatory Guide 1.27, Ultimate Heat Sink for Nuclear Power Plants (for Comment) ......................................................... ML003739996 Regulatory Guide 1.76, Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants ........................................ ML070360253 Regulatory Guide 1.117, Tornado Design Classification ....................................................................................................... ML003739346 Regulatory Guide 1.143, Design Guidance for Radioactive Waste Management Systems, Structures, and Components ML003740200 Installed in Light-Water-Cooled Nuclear Power Plants.
Regulatory Guide 1.206, Section C.I.1, Standard Format and Content of Combined License ApplicationsIntroduction ML070630005 and General Description of the Plant.
Regulatory Guide 1.221, Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants ................................. ML110940303 NUREG-0700, Revision 2, Human-Systems Interface Design Review Guidelines (three volumes) ................................... ML021700337 ML021700342 ML021700371 NUREG-0711, Revision 2, Human Factors Engineering Program Review Model ............................................................... ML040770540 NUREG-0711, Revision 3, Human Factors Engineering Program Review Model ............................................................... ML12324A013 NUREG-0800, Section 3.8.4, Revision 2, Other Seismic Category I Structures, Appendix D, Guidance on Spent Fuel ML070550054 Pool Racks.
NUREG-0800, Section 3.9.2, Revision 3, Dynamic Testing and Analysis of Systems, Structures, and Components ....... ML070230008 NUREG-0800, Section 3.9.5, Revision 3, Reactor ................................................................................................................. ML070230009 Pressure Vessel Internals ........................................................................................................................................................
NUREG-0800, SRP Section 6.4, Revision 3, Control Room Habitability System ................................................................ ML070550069 NUREG-0800, SRP Section 9.1.2, Revision 4, New and Spent Fuel Storage .................................................................... ML070550057 NUREG-0800, SRP Section 13.4, Revision 3, Operational Programs ................................................................................. ML070470463 NUREG-0800, SRP Section 13.5.2.1, Revision 2, Operating and Emergency Operating Procedures ............................... ML070100635 NUREG-0800, SRP Section 18, Revision 2, Human Factors Engineering .......................................................................... ML070670253 NUREG-1242, NRC Review of Electric Power Research Institutes Advanced Light Water Reactor Utility Requirements ML100610048 Document, Evolutionary Plant Designs (five volumes). ML100430013 ML063620331 ML070600372 ML070600373 NRC Bulletin 2012-01: Design Vulnerability in Electric Power System ................................................................................... ML12074A115 Interim Staff Guidance DC/COL-ISG-8, Necessary Content of Plant-Specific Technical Specifications ............................ ML083310259 JLD-ISG-2012-03 Revision 0, Compliance With Order EA-12-051, Reliable Spent Fuel Pool Instrumentation, ............. ML12221A339 NEI 12-02, Revision 1, Industry Guidance for Compliance With NRC Order EA-12-051, To Modify Licenses With Re- ML122400399 gard to Reliable Spent Fuel Pool Instrumentation.
Clarifications Requested by NRC Staff on Economic Simplified Boiling Water Reactor Fuel Design .................................. ML11269A093 Audit Report, ESBWR Fuel Seismic Audit Summary ............................................................................................................ ML112860614
ADAMS Accession No./
Document web link/ Federal Register citation Notice of Violation, ESBWR AIA Inspection Report Inspection, NRC Inspection Report No. 0520000/10/2010-201 and ML102740292 Notice of Violation.
Reply to Notice of Violation, NRC Inspection Report 052000010-10-201 .............................................................................. ML103010047 GE-Hitachi Nuclear Energy Americas, LLC, Reply to Notice of Violation, NRC IR 052000010-10-201 ............................... ML103400150 ACRS MemorandumFinal RuleESBWR Design Certification (RIN 3150-AI85) ................................................................ ML113120076 ACRS MemorandumESBWR Design Certification Rulemaking and Supplemental Final Safety Evaluation Report ........... ML11340A043 ACRS MemorandumSupplemental Final Safety Evaluation Report on the General Electric-Hitachi Nuclear Energy ML14107A263 (GEH) Application for Certification of the Economic Simplified Boiling Water Reactor (ESBWR) Design.
ACRS MemorandumFinal RuleESBWR Design Certification (RIN 3150-AI85) ................................................................ ML14196A207 Regulatory History of Design Certification 6 .............................................................................................................................. ML003761550