ML20129J895
| ML20129J895 | |
| Person / Time | |
|---|---|
| Site: | 05200045 |
| Issue date: | 05/08/2020 |
| From: | James Shea NRC/NRR/DNRL/NRLB |
| To: | |
| Shea J | |
| Shared Package | |
| ML20129J892 | List: |
| References | |
| Download: ML20129J895 (11) | |
Text
B-1 Appendix B ABWR DC License Renewal Supplemental FSER References This appendix contains a listing of the references used by the U.S. Nuclear Regulatory Commission (NRC) staff regarding the review of the ABWR DC License Renewal under Docket No. 052-000045.
- 1.
Atomic Energy Act of 1954, as Amended.
- 2.
10 CFR 20.1101, Radiation protection programs.
- 3.
10 CFR 20.1201, Occupational dose limits for adults.
- 4.
10 CFR 20.1406, Minimization of Contamination.
- 5.
10 CFR 20.1601, Control of access to high radiation areas.
- 6.
10 CFR 20.1602, Control of access to very high radiation areas.
- 7.
10 CFR 21.21, Notification of failure to comply or existence of a defect and its evaluation.
- 8.
10 CFR 50.34, Contents of applications; technical information.
- 9.
10 CFR 50.36, Technical Specifications.
- 10.
10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors.
- 11.
10 CFR 50.48, Fire Protection.
- 12.
10 CFR 50.49, Environmental qualification of electric equipment important to safety for nuclear power plants.
- 13.
10 CFR 50.54, Conditions of Licenses.
- 14.
10 CFR 50.55a, Codes and Standards.
- 15.
10 CFR 50.68, Criticality Accident Requirements.
- 16.
10 CFR 50.150, Aircraft impact assessment.
- 17.
10 CFR 50.155, Mitigation of Beyond-Design Basis Events, MBDBE Rule.
- 18.
10 CFR 52.47, Contents of Applications; Technical Information.
- 19.
10 CFR 52.57, Application for renewal.
- 20.
10 CFR 52.59, Criteria for Renewal.
- 21.
10 CFR 52.63, Finality of standard design certifications.
B-2
- 22.
10 CFR 52.79, Contents of applications; technical information in final safety analysis report.
- 23.
10 CFR 52.80, Contents of applications; additional technical information.
- 24.
10 CFR Part 20, Standards for Protection Against Radiation.
- 25.
10 CFR Part 21, Reporting of Defects and Noncompliance.
- 26.
10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities.
- 27.
10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants.
- 28.
10 CFR Part 50, Appendix A, GDC 1, Quality Standards and Records.
- 29.
10 CFR Part 50, Appendix A, GDC 2 (1997), Design bases for protection against natural phenomena.
- 30.
10 CFR Part 50, Appendix A, GDC 2, Design Bases for Protection Against Natural Phenomena.
- 31.
10 CFR Part 50, Appendix A, GDC 3, Fire Protection.
- 32.
10 CFR Part 50, Appendix A, GDC 4, Environmental and Dynamic Effects Design Bases, (1997).
- 33.
10 CFR Part 50, Appendix A, GDC 16, Containment Design,
- 34.
10 CFR Part 50, Appendix A, GDC 17, Electric Power Systems, 1997.
- 35.
10 CFR Part 50, Appendix A, GDC 19, Control Room.
- 36.
10 CFR Part 50, Appendix A, GDC 28, Reactivity limits.
- 37.
10 CFR Part 50, Appendix A, GDC 30, Quality of reactor coolant pressure boundary.
- 38.
10 CFR Part 50, Appendix A, GDC 33, Reactor Coolant Makeup.
- 39.
10 CFR Part 50, Appendix A, GDC 34, Residual Heat Removal.
- 40.
10 CFR Part 50, Appendix A, GDC 35, Emergency Core Cooling.
- 41.
10 CFR Part 50, Appendix A, GDC 38, Containment Heat Removal.
- 42.
10 CFR Part 50, Appendix A, GDC 50, Containment Design Basis.
- 43.
10 CFR Part 50, Appendix A, GDC 60, Control of Releases of Radioactive Materials to The Environment.
- 44.
10 CFR Part 50, Appendix A, GDC 61, Fuel Storage and Handling and Radioactivity Control.
- 45.
10 CFR Part 50, Appendix A, GDC 62, Prevention of Criticality in Fuel Storage and Handling.
B-3
- 46.
10 CFR Part 50, Appendix A, GDC 63, Monitoring Fuel and Waste Storage.
- 47.
10 CFR Part 50, Appendix B (1997), Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.
- 48.
10 CFR Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.
- 49.
10 CFR Part 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities.
- 50.
10 CFR Part 50, Appendix K, ECCS Evaluation Models.
- 51.
10 CFR Part 52, Appendix A, Design Certification Rule for the U.S. Advanced Boiling Water Reactor.
- 52.
10 CFR Part 73, Physical and Protection of Plants and Materials.
- 53.
10 CFR Part 100, Reactor Site Criteria.
- 54.
10 CFR Part 100, Appendix A (1997), Seismic and Geologic Siting Criteria for Nuclear Power Plants.
- 55.
40 CFR Part 190, Environmental Protection Standards for Nuclear Power Operations.
- 56.
NRC, BL 93 02, Debris Plugging of Emergency Core Cooling Suction Strainers.
- 57.
NRC, BL 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors, May 6, 1996.
- 58.
NRC, BL 2012-01, Design Vulnerability in Electric Power System, July 2012 (ADAMS Accession No. ML12074A114).
- 59.
NRC, DC/COL-ISG-019, Review of Evaluation to Address Gas Accumulation Issues in Safety Related Systems and Systems Important to Safety, September 16, 2011 (ADAMS Accession No. ML111110572).
- 60.
NRC, DC/COL-ISG-024, Implementation of Regulatory Guide 1.221 on Design-Basis Hurricane and Hurricane Missiles, May 2013 (ADAMS Accession No. ML13015A693).
- 61.
NRC, EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, March 12, 2012 (ADAMS Accession No. ML12054A735).
- 62.
NRC, EA-12-050, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents, March 12, 2012 (ADAMS Accession No. ML12054A694).
- 63.
NRC, EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, March 12, 2012 (ADAMS Accession No. ML12056A044).
- 64.
NRC, GL 82-33, Supplement 1 to NUREG-0737-requirements for Emergency Response Capability, December 1982.
B-4
- 65.
NRC, GSI-191, Assessment of [Effect of] Debris Accumulation on PWR Sump Performance.
- 66.
NRC, IN 92-71, Partial Plugging of Suppression Pool Strainers at a Foreign BWR, September 30, 1992 (ADAMS Accession No. ML031200327).
- 67.
NRC, IN 93-34, Potential for Loss of Emergency Cooling Function due to a Combination of Operational and Post-LOCA Debris in Containment, April 26, 1993.
- 68.
NRC, IN 93-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment, Supplement 1, May 6, 1993.
- 69.
NRC, IN 2009-23, Nuclear Fuel Thermal Conductivity Degradation, October 8, 2009 (ADAMS Accession No. ML091550527).
- 70.
NRC, JLD-ISG-2012-03, Revision 0, Compliance with Order EA 12-051, Reliable Spent Fuel Pool Instrumentation, August 29, 2012 (ADAMS Accession No. ML12221A339).
- 71.
NRC, Letter from C. O. Thomas, NRC, to J. S. Charnley, (GE), "Acceptance for Referencing of Licensing Topical Report NEDE-24011-P Amendment 7 to Revision 6, General Electric Standard Application for Reactor Fuel," March 1, 1985 (ADAMS Accession No. ML090760583 (non-public)).
- 72.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 9.1.5, Revision 1, Overhead Heavy Load Handling Systems, March 2007(ADAMS Accession No. ML070380201).
- 73.
NRC, NUREG-1503, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design, July 1994 (ADAMS Accession No. ML080670592).
- 74.
NRC, NUREG-1503, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design, Supplement 1, May 1997 (ADAMS Accession No. ML080710134).
- 75.
NRC, NUREG/CR-2326, Calculations of Reactor Accident Consequences Version 2, CRAC2: Computer Code, Users Guide, February 1983.
- 76.
NRC, NUREG/CR-6367, Experimental Study of Head Loss and Filtration for LOCA Debris, dated February 1996.
- 77.
NRC, NUREG/CR-7004, Technical Basis for Regulatory Guidance on Design-Basis Hurricane-Borne Missile Speeds for Nuclear Power Plants, November 2011 (ADAMS Accession No. ML11341A102).
- 78.
NRC, NUREG/CR-7005, Technical Basis for Regulatory Guidance on Design-Basis Hurricane Wind Speeds for Nuclear Power Plants, November 2011 (ADAMS Accession No. ML11335A031).
- 79.
NRC, NUREG-0554, Single Failure-Proof Cranes for Nuclear Power Plants, May 1979 (ADAMS Accession No. ML110450636).
B-5
- 80.
NRC, NUREG-0654/FEMA (Federal Emergency Management Agency)-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Revision 1, November 1980 (ADAMS Accession No. ML040420012).
- 81.
NRC, NUREG-0696, Functional Criteria for Emergency Response Facilities, February 1981 (ADAMS Accession No. ML051390358).
- 82.
NRC, NUREG-0737, Clarification of TMI Action Plan Requirements, November 1980 (ADAMS Accession No. ML051400208).
- 83.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (ADAMS Accession No. ML051400208).
- 84.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition), Section 19.0, Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors, Revision 3, December 2015 (ADAMS Accession No. ML15089A068).
- 85.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 3.4.2, Analysis Procedures, Revision 3, March 2007 (ADAMS Accession No. ML070570003).
- 86.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 4.2, Revision 2, Fuel System Design, July 1981 (ADAMS Accession No. ML052340660).
- 87.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Revision 2, Section 5.2.5, Reactor Coolant Pressure Boundary Leakage Detection, March 2007 (ADAMS Accession No. ML070610277).
- 88.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 5.4.7, Residual Heat Removal (RHR)
System, Revision 5, May 2010 (ADAMS Accession No. ML100680577).
- 89.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 6.2.1.1.C, Pressure-Suppression Type BWR Containments, Revision 6 August 1984 (ADAMS Accession No. ML052340657).
- 90.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 6.2.2, Containment Heat Removal Systems, Revision 5, March 2007 (ADAMS Accession No. ML070160661).
- 91.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 9.1.2, New and Spent Fuel Storage, Revision 4, March 2007 (ADAMS Accession No. ML070550057).
B-6
- 92.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 14.3, Inspections, Tests, Analyses, And Acceptance Criteria - Design Certification, Draft Revision 0, April 1996 (ADAMS Accession No. ML052070653).
- 93.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 19.5, Adequacy of Design Features and Functional Capabilities Identified and Described for Withstanding Aircraft Impacts, Revision 0, April 2013 (ADAMS Accession No. ML12276A112).
- 94.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (SRP), Section 13.5.2.1, Revision 2, March 2007 (ADAMS Accession No. ML070100635).
- 95.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 3.3.1, Wind Loadings, Revision 2, 1981 (ADAMS Accession No. ML052340621).
- 96.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 3.3.2 Tornado Loadings, Revision 2, July 1981 (ADAMS Accession No. ML052340625).
- 97.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 3.5.1.4, Missiles Generated by Natural Phenomena, Revision 2, July 1981 (ADAMS Accession No. ML052340526).
- 98.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 6.2.1.1.C, "Pressure-Suppression Type BWR Containments," Revision 7, March 2007(ADAMS Accession No. ML063600403).
- 99.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, (LWR Edition), Chapter 8, Branch Technical Position 8-9, Open Phase Conditions in Electric Power System, July 2015 (ADAMS Accession No. ML15057A085).
100.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 9.1.2, Revision 3, New and Spent Fuel Storage, July 1981 (ADAMS Accession No. ML052360614).
101.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 9.1.2, Revision 4, New and Spent Fuel Storage, March 2007 (ADAMS Accession No. ML070550057).
102.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 9.1.4, Revision 4, Light Load Handling System and Refueling Cavity Design, July 2014 (ADAMS Accession No. ML13318A923).
103.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 9.5.1, Fire Protection Program, Revision 3, July 1981 (ADAMS Accession No. ML052350030).
B-7 104.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 6.4, Control Room Habitability System, Revision 2, July 1981 (ADAMS Accession No. ML052340712).
105.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 13.3, Emergency Planning, Revision 2, July 1981 (ADAMS Accession No. ML052350065).
106.
NRC, NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 13.3, Emergency Planning, Revision 3, March 2007 (ADAMS Accession No. ML063410307).
107.
NRC, NUREG-0800, Section 3.7.3, Seismic Subsystem Analysis, Revision 2, August 1989 (ADAMS Accession No. ML052340570).
108.
NRC, NUREG-800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 9.1.1, Revision 2, Criticality Safety of Fresh and Spent Fuel Storage and Handling, July 1981 (ADAMS Accession No. ML052350536).
109.
NRC, NUREG-800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 3.8.4, Revision 4, Other Seismic Category I Structures, Appendix D, Guidance on Spent Fuel Pool Racks, September 2013.
110.
NRC, NUREG-1242, NRC Review of Electric Power Research Institutes Advanced Light Water Reactor Utility Requirements Document, August 1992 (ADAMS Accession No. ML100430013).
111.
NRC, NUREG-1503, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design, July 1994 (ADAMS Accession No. ML080670592).
112.
NRC, NUREG-1503, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design, Supplement 1, May 1997 (ADAMS Accession No. ML080710134).
113.
NRC, RG 1.100, Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants, Revision 3, September 2009 (ADAMS Accession No. ML091320468).
114.
NRC, RG 1.153, Criteria for Safety Systems, Revision 1, June 1996 (ADAMS Accession No. ML003740022).
115.
NRC, RG 1.189, Fire Protection for Nuclear Power Plants, Revision 2, October 2009 (ADAMS Accession No. ML092580550).
116.
NRC, RG 1.206, Applications for Nuclear Power Plants, Revision 1, October 2018, Section C.1.11.b, Supplemental Information.
B-8 117.
NRC, RG 1.217, Guidance for the Assessment of Beyond-Design-Basis Aircraft Impacts, Revision 0, August 2011 (ADAMS Accession No. ML092900004).
118.
NRC, RG 1.221, Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants, Revision 0, October 2011 (ADAMS Accession No. ML110940300).
119.
NRC, RG 1.226, "Flexible Mitigation Strategies for Beyond-Design-Basis Events, Revision 0, June 2019.
120.
NRC, RG 1.227, "Wide-Range Spent Fuel Pool Level Instrumentation," Revision 0, June 2019.
121.
NRC, RG 1.26, Revision 5, Quality Group Classifications and Standards for Water-,
Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants, February 2017 (ADAMS Accession No. ML16082A501).
122.
NRC, RG 1.29, Revision 5, Seismic Design Classification for Nuclear Power Plants, July 2016 (ADAMS Accession No. ML16118A148).
123.
NRC, RG 1.45, Guidance on Monitoring and Responding to Reactor Coolant System Leakage, Revision 1, May 2008 (ADAMS Accession No. ML073200271).
124.
NRC, RG 1.75, Physical Independence of Electric Systems, Revision 2, September 1976 (ADAMS Accession No. ML003740265).
125.
NRC, RG 1.82, Water Sources for Long-Term Recirculation Cooling Following a Loss-Of-Coolant Accident, Revision 1, November 1985 (ADAMS Accession No. ML003740236).
126.
NRC, RG 1.82, Water Sources for Long-Term Recirculation Cooling Following A Loss-Of-Coolant Accident, Revision 4, March 2012 (ADAMS Accession No. ML111330278).
127.
NRC, RG-1.143, Design Guidance for Radioactive Waste Management Systems, Structures, And Components Installed In Light-Water-Cooled Nuclear Power Plants, Revision 1, October 1979.
128.
NRC, RG-1.76, Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants, Revision 1, March 2007 (ADAMS Accession No. ML070360253).
129.
NRC, SECY-11-0093, Near Term Report and Recommendations for Agency Actions Following the Events in Japan, July 12, 2011 (ADAMS Accession No. ML11186A950).
130.
NRC, SECY-11-0124, Recommended Actions to be Taken Without Delay from the NTTF Report, September 9, 2011 (ADAMS Accession No. ML11245A127).
131.
NRC, SECY-11-0137, Prioritization of Recommended Actions to Be Taken in Response to Fukushima Lessons Learned, October 3, 2011 (ADAMS Accession No. ML11269A204) 132.
NRC, SECY-12-0025, Proposed Orders and Requests for Information in Response to Lessons Learned from Japans March 11, 2011, Great Tohoku Earthquake and Tsunami, February 22, 2012 (ADAMS Accession No. ML12039A111).
B-9 133.
NRC, Safety Evaluation by the Office of Nuclear Reactor Regulation, Topical Report (TR) WCAP-16406-P-A, Revision 1, Evaluation of Downstream Sump Debris Effects in Support of GSI-191, Pressurized Water Reactor Owners Group, Project No. 694, December 2007 (ADAMS Accession No. ML073520295).
134.
NRC, staff letter to GEH, Enclosure 1 and 2, Staff Assessment of General Electric Codes and Methods with Regard to Thermal Conductivity Degradation, March 23, 2012 (ADAMS Accession No. ML120750001 - Public and ML120680592 -Non-Public).
135.
NRC, staff letter to GEH, Nuclear Fuel Thermal Conductivity Degradation Evaluation for Light Water Reactors Using Ge-Hitachi Nuclear Energy Codes and Methods. March 23, 2012 (ADAMS Accession No. ML120680571).
136.
NRC, U.S. Nuclear Regulatory Commission Regulatory Audit Summary Report: GE Hitachi U.S. Advanced Boiling-Water Reactor Design Certification Renewal Emergency Core Cooling System Strainer Design, January 24, 2019 (ADAMS Accession No. ML18354B167).
137.
ANSI/ASCE, 7-88, Minimum Design Loads for Buildings and Other Structures, 1990.
138.
ANSI/ASCE, 7-88, 1990, Minimum Design Loads for Buildings and Other Structures, October 5, 2018.
139.
ASME Boiler and Pressure Vessel Code -Section II, Materials.
140.
ASME Boiler and Pressure Vessel Code -Section III, Rules for Construction of Nuclear Power Plant Components.
141.
ASME Standard QME-1-2007, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, November 2007.
142.
ASME, Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Facility Components, 1989 Edition.
143.
ASME, Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition.
144.
ASME, NOG-01, Rules for Construction of Overhead and Gantry Cranes, 2004.
145.
ASME/ANSI, OMa-1988 Addenda to ASME/ANSI Standard OM-1987, Operation and Maintenance of Nuclear Power Plants.
146.
Bechtel Topical Report, BC-TOP-3-A, Tornado and Extreme Wind Design Criteria for Nuclear Power Plants, Revision 3, August 1974 (ADAMS Accession No. ML14093A218).
147.
GEH, ABWR Standard Plant Design Certification Renewal Application Design Control Document, Revision 4, Tier 1 and Tier 2, December 2010 (ADAMS Accession No. ML11126A129).
148.
GEH, ABWR Standard Plant Design Certification Renewal Application Design Control Document, Revision 5, Tier 1 and Tier 2, December 2010 (ADAMS Accession No. ML110040323).
B-10 149.
GEH, ABWR Standard Plant Design Certification Renewal Application Design Control Document, Revision 6, Tier 1 and Tier 2, February 2016 (ADAMS Accession No. ML16214A015).
150.
GEH, ABWR Standard Plant Design Certification Renewal Application Design Control Document, Revision 7, Tier 1 and Tier 2, December 2019 (ADAMS Accession No. ML20007E371).
151.
GEH, NEDC-32721P-A "Application Methodology for the General Electric Stacked Disk ECCS Suction Strainer," Revision 2, March 2003 (ADAMS Accession Nos.
ML031010388, public version, and ML031010390, proprietary version).
152.
GEH, NEDE-33878P, ABWR ECCS Suction Strainer Evaluation of Long-Term Recirculation Capability, Revision 3, March 2018 (ADAMS Accession Nos. ML18092A306, public version, and ML18092A308, proprietary version).
153.
GEH, NEDO-32686-A, Utility Resolution Guide for ECCS Suction Strainer Blockage, Volumes 1 through 4, Revision 0, October 1998 (ADAMS Accession Nos. ML092530482, ML092530500, ML092530505, and ML092530507).
154.
GEH, NEDO-33372, Advanced Boiling Water Reactor (ABWR) Containment Analysis."
155.
GEH, Topical Report - NEDE-21175-3-P, BWR Fuel Assembly Evaluation of Combined Safe Shutdown Earthquake (SSE) and Loss-of-Coolant Accident (LOCA) loadings, Amendment 3, July 1982.
156.
GEH, Topical Report - NEDE-31152P, "General Electric Fuel Bundle Designs Evaluated with GESTAR-Mechanical Analysis Bases (proprietary)," December 1988 (ADAMS Accession No. ML003725063 (non-public)).
157.
IEEE Std. 279-1971, IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations.
158.
IEEE Std. 308-1980, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations.
159.
IEEE Std. 384-1981, IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits.
160.
Ludwig and Roth, Influence of Corrosion Processes on the Protected Sump Intake after Coolant Loss Accidents, Nuclear Technology Annual Convention 2006, English translation (ADAMS Accession No. ML083510156).
161.
NEI 00-01, Guidance for Post Fire Safe Shutdown Circuit Analysis, Revision 2, June 2009 (ADAMS Accession No. ML091770265).
162.
NEI 06-12, B.5.b Phase 2 & 3 Submittal Guideline, Revision 2, December 2006 (ADAMS Accession No. ML070090060).
163.
NEI 07-13, Methodology for Performing Aircraft Impact Assessments for New Plant Designs, Revision 8, April 2011 (ADAMS Accession No. ML111440006).
B-11 164.
NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities, Revision 0, May 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12125A412).
165.
NEI 12-02, Revision 1, Industry Guidance for Compliance with NRC Order EA-12-051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, August 2012 (ADAMS Accession No. ML122400399).
166.
NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 0, September 2014 (ADAMS Accession No. ML14269A236).
167.
NEI 91-04, "Severe Accident Issue Closure Guidelines", Revision 1, dated December 1994, the industry standard for SAMGs (ADAMS Accession No. ML072850981).
168.
South Texas Project, Unit 3 Combined License No. NPF-097, February 12, 2016 (ADAMS Accession No. ML16033A020).
169.
South Texas Project, Unit 4 Combined License No. NPF-098, February 12, 2016 (ADAMS Accession No. ML16033A047).