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Accession Number: ML092310639

Date Released: Thursday, August 27, 2009

Package Contents

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- ML092310641 - Yucca Mountain - Response to Request for Additional Information - Safety Evaluation Report, Vol. 3, Chapter 2.2.1.2.1 (Scenario Analysis), 4th Set (U.S. Dept. of Energy's Safety Analysis Report Section 2.2.1.2) - Resubmittal of DOE Reference Citations. (41 page(s), 8/11/2009)
- ML092310643 - TDR-EDC-NU-000007, Rev. 00, "Evaluation of Codisposal Viability for Th/U Carbide (Fort Saint Vrain HTGR) DOE-Owned Fuel." (120 page(s), 9/28/2001)
- ML092310645 - Calculation No. CAL-EDC-NU-000008, "Benchmark and Critical Limit Calculation for DOE SNF." (368 page(s), 3/29/2002)
- ML092310646 - Calculation No. CAL-DSD-NU-000002, Rev. A, "Criticality Calculation for the Most Reactive Degraded Configurations of the FFTF SNF Codisposal WP Containing an Intact Ident-69 Container." (62 page(s), 8/28/2002)
- ML092310647 - Calculation No. CAL-DSD-NU-000003, Rev. 00A, "Analysis of Critical Benchmark Experiments and Critical Limit Calculation for DOE SNF." (150 page(s), 7/2/2003)
- ML092310648 - Calculation No. CAL-DSD-NU-000003, Rev 00A, ECN No. 1, "Analysis of Critical Benchmark Experiments and Critical Limit Calculation for DOE SNF." (1 page(s), 7/26/2005)
- ML092310649 - Calculation No. CAL-DSD-NU-000004, Rev. 00A, "Intact and Degraded Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package". (75 page(s), 3/23/2004)
- ML092310650 - Calculation No. CAL-DSD-NU-000004, Rev. 00A, ECN No. 1, "Intact and Degraded Mode Criticality Calculation for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package." (1 page(s), 6/1/2005)
- ML092310651 - Calculation No. CAL-DSD-NU-000004, Rev. 00A, ECN No. 2, "Intact and Degraded Mode Criticality Calculations for the Codisposal of TMI-2 Spent Nuclear Fuel in a Waste Package." (1 page(s), 7/26/2005)
- ML092310652 - Calculation No. BBA000000-01717-0210-00037, Rev. 00, "Enrico Fermi Fast Reactor Spent Nuclear Fuel Criticality Calculations: Intact Model." (63 page(s), 4/5/1999)
- ML092310653 - Calculation No. BBA000000-01717-0210-00037, Rev. 00, ECN No. 1, "Enrico Fermi Fast Reactor Spent Nuclear Fuel Criticality Calculations: Intact Mode." (1 page(s), 7/26/2005)
- ML092310660 - Calculation No. BBA000000-01717-0210-00051, Rev. 00, "Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculations: Intact SNF Canister." (101 page(s), 6/3/1999)
- ML092310661 - Calculation No. CAL-MGR-NU-000001, Rev. 00, "TRIGA Fuel Phase I and II Criticality Calculation." (68 page(s), 11/22/1999)
- ML092310662 - Calculation No. CAL-MGR-NU-000001, Rev. 00, ECN No. 1, "TRIGA Fuel Phase I and II Criticality Calculation." (1 page(s), 7/26/2005)
- ML092310663 - TDR-EDC-NU-000005, Rev. 00, "Evaluation of Codisposal Viability for Th/U Oxide (Shippingport LWBR) DOE-Owned Fuel." (124 page(s), 9/18/2000)
- ML092310664 - Calculation No. CAL-EDC-NU-000004, Rev. 00, "Intact and Degraded Criticality Calculations for the Codisposal of Shippingport LWBR Spent Nuclear Fuel in a Waste Package." (86 page(s), 9/11/2000)
- ML092310665 - TDR-EDC-NU-000004, Rev. 00, "Evaluation of Codisposal Viability for U-Metal (N Reactor) DOE-Owned Fuel." (137 page(s), 1/31/2001)
- ML092310666 - TDR-DSD-MD-000001, Rev. 00, ERD No. 01, "DOE SNF Phase I and II Summary Report". (1 page(s), 12/2/2008)
- ML092310667 - Calculation No. B00000000-01717-0210-00002, Rev. 00, "CRC Reactivity Calculations for Crystal River Unit 3." (259 page(s), 6/19/1998)
- ML092310668 - Calculation No. B00000000-01717-0210-00006, Rev. 00, "CRC Reactivity Calculations for Sequoyah Unit 2," Cover through Page 63. (63 page(s), 5/13/1998)
- ML092310659 - Calculation No. B00000000-01717-0210-00006, Rev. 00, "CRC Reactivity Calculations for Sequoyah Unit 2," Attachment I, Page 1 through 333. (331 page(s), 8/11/2009)
- ML092310672 - Calculation No. B00000000-01717-0210-00006, Rev. 00, "CRC Reactivity Calculations for Sequoyah Unit 2," Attachment I, Page 334 of 656 through Attachment VI. (329 page(s), 8/11/2009)
- ML092310673 - Calculation No. B00000000-01717-0210-00008, Rev. 00, "CRC Reactivity Calculations for Three Mile Island Unit 1." (80 page(s), 6/4/1998)
- ML092310674 - Calculation No. 32-5029393-00, "Commercial Reactor Reactivity Analysis for Grand Gulf, Unit 1." (83 page(s), 9/26/2003)
- ML092310675 - Calculation No. 32-5045840-00, "Analysis of Critical Benchmark Experiments for Configurations External to WP." (114 page(s), 6/28/2004)
- ML092310676 - Calculation No. 32-5045840-01, "Analysis of Critical Benchmark Experiments for Configurations External to WP." (6 page(s), 12/7/2004)
- ML092310677 - ORNL/TM-2007/127, "Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel." (141 page(s), 10/31/2007)
- ML092310678 - DOE/SNF/REP-090, Rev. 0, "Packaging Strategies for Criticality Safety for 'Other' DOE Fuels in a Repository." (124 page(s), 6/23/2004)
- ML092310679 - DOE/SNF/REP-086, "Interim Report on the Corrosion Performance of a Neutron Absorbing Ni-Cr-Mo-Gd Alloy". (59 page(s), 3/22/2004)
- ML092310680 - UCRL-ID-119564, Vol. 3, Rev. 1.1, "Engineered Materials Characterization Report," Cover through Chapter 2, Section 2.7. (264 page(s), 7/31/1998)
- ML092310671 - UCRL-ID-119564, Vol. 3, Rev. 1.1, "Engineered Materials Characterization Report," Chapter 2, Section 2.8 through Appendix. (186 page(s), 7/31/1998)
- ML092310704 - INL/EXT-06-11772, Rev. 1, "Electrochemical Corrosion Testing of Neutron Absorber Materials," Cover through Page 12. (25 page(s), 5/31/2007)
- ML092310692 - INL/EXT-06-11772, Rev. 1, "Electrochemical Corrosion Testing of Neutron Absorber Materials," Page 13 through 28. (16 page(s), 5/31/2007)
- ML092310693 - INL/EXT-06-11772, Rev. 1, "Electrochemical Corrosion Testing of Neutron Absorber Materials", Page 29 through 36. (8 page(s), 5/31/2007)
- ML092310694 - INL/EXT-06-11772, Rev. 1, "Electrochemical Corrosion Testing of Neutron Absorber Materials," Page 37 through 56. (20 page(s), 5/31/2007)
- ML092310695 - INL/EXT-07-12633, Rev. 1, "Electrochemical Corrosion Testing of Borated Stainless Steel Alloys." (26 page(s), 9/5/2007)
- ML092310696 - Calculation No. ANL-DS0-NU-000001, Rev./Add. 00, ERD No. 03, "Screening Analysis of Criticality Features, Events, and Processes for License Application." (4 page(s), 2/26/2009)
- ML092310697 - Calculation No. CAL-MGR-MD-000001, Rev. 00, "Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams." (65 page(s), 2/14/2000)
- ML092310698 - Calculation No. CAL-EDC-NU-000007, Rev. 00, "Intact and Degraded Mode Criticality Calculations for the Codisposal of Fort Saint Vrain HTGR Spent Nuclear Fuel in a Waste Package." (89 page(s), 9/28/2001)
- ML092310699 - Calculation No. BBA000000-01717-0210-00033, Rev. 01, "Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculation: Degraded SNF Canister." (246 page(s), 6/4/1999)
- ML092310700 - Calculation No. CAL-EDC-NU-000003, Rev. 00, "Intact and Degraded Component Criticality Calculations of N Reactor Spent Nuclear Fuel." (141 page(s), 1/31/2001)
- ML092310709 - INEEL/EXT-98-00799, Rev. 2, "Fuel Summary Report: Shippingport Light Water Breeder Reactor," Cover through Chapter 3. (74 page(s), 9/30/2002)
- ML092310710 - INEEL/EXT-98-00799, Rev. 2, "Fuel Summary Report: Shippingport Light Water Breeder Reactor," Chapter 4 through Appendix A. (108 page(s), 9/30/2002)
- ML092310711 - INEEL/EXT-98-00799, Rev. 2, "Fuel Summary Report: Shippingport Light Water Breeder Reactor," Appendix B through D. (206 page(s), 9/30/2002)
- ML092310712 - Calculation No. CAL-DSU-NU-000004, Rev. 00A, "Isotopic Generation and Confirmation of the PWR Application Model." (87 page(s), 10/20/2003)
- ML092310713 - Calculation No. CAL-DSU-NU-000004, Rev. 00A, ECN No. 1, "Isotopic Generation and Confirmation of the PWR Application Model." (1 page(s), 5/23/2005)
- ML092310714 - Calculation No. CAL-DSU-NU-000004, Rev. 00A, ECN: 2, "Isotopic Generation and Confirmation of the PWR Application Model." (1 page(s), 7/26/2005)
- ML092310715 - Calculation No. 32-5041666-02, "Reactor Record Uncertainty Determination," Cover through Page 65. (65 page(s), 5/26/2004)
- ML092310716 - Calculation No. 32-5041666-02, "Reactor Record Uncertainty Determination," Page 66 through End. (64 page(s), 5/26/2004)
- ML092310717 - Calculation No. 32-5041666-03, "Reactor Record Uncertainty Determination." (6 page(s), 12/6/2004)
- ML092310719 - Calculation No. 32-5035847-01, "Isotopic Generation and Confirmation of the BWR Appl. Model," Cover through Page 48. (48 page(s), 6/24/2004)
- ML092310722 - Calculation No. 32-5035847-01, "Isotopic Generation and Confirmation of the BWR Appl. Model", Pages 49 through 89. (41 page(s), 6/24/2004)
- ML092310723 - Calculation No. 32-5035847-01, "Isotopic Generation and Confirmation of the BWR Appl. Model", Pages 89 through 121. (33 page(s), 6/24/2004)
- ML092310724 - Calculation No. 32-5035847-01, "Isotopic Generation and Confirmation of the BWR Appl. Model", Page 122 through 143. (22 page(s), 6/24/2004)
- ML092310725 - Calculation No. 32-5035847-02, "Isotopic Generation and Confirmation of the BWR Application Model." (6 page(s), 12/8/2004)
- ML092310726 - CAL-DNC-NU-000002, Rev. 00C, ERD 01, "Waste Package Flooding Probability Evaluation." (1 page(s), 3/31/2008)
- ML092310727 - CAL-DN0-NU-000002, Rev. 00C, AD01, ERD No. 02, "Waste Package Flooding Probability Evaluation." (29 page(s), 2/4/2009)