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Issue date | Title | Topic | |
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ML030910204 | 19 March 2003 | Response to Request for Additional Information - Integrated Leak Rate Test Deferral for License Amendment Request No. 318 | Probabilistic Risk Assessment Coatings Nondestructive Examination Large early release frequency Moisture barrier Fatality |
ML031290130 | 30 April 2003 | Combined 2002 Annual Radioactive Effluent Release Report | Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Process Control Program |
ML031290160 | 30 April 2003 | Combined 2002 Annual Radioactive Effluent Release Report, Attachment 1, Table 1A Through Off Dose Calculation Manual, Revision 23 | Shutdown Margin Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
ML031630807 | 30 April 2003 | Combined 2002 Annual Radioactive Effluent Release Report, Section 3.0 Through Table 2.1-2 | Offsite Dose Calculation Manual Incorporated by reference Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program |
ML033510550 | 13 May 1998 | CRC Depletion Calculations for Three Mile Island Unit 1 | Fuel cladding |
ML052220638 | 12 July 2005 | Calculation No. C-1101-900-E000-083 Revision 2, Eab, LPZ, and CR Doses Due to Fuel Handling Accident in Reactor Building with Hatch Doors Opened. | Deep Dose Equivalent |
ML052660212 | 12 September 2005 | Calculation No. C-1101-900-EOOO-083, Revision 3, Eab, LPZ, and CR Doses Due to Fuel Handling Accident in Reactor Building with Hatch Doors Opened. | |
ML061320352 | 1 July 2003 | Calculation 6610-PLN-4200.01,Rev 24, Offsite Dose Calculation Manual. | Shutdown Margin Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
ML063540172 | 17 November 2006 | Calculation No. C-1101-900-E000-083, Revision 4, Eab, LPZ, and CR Doses Due to Fuel Handling Accidents. | Deep Dose Equivalent |
ML092310649 | 23 March 2004 | 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 | |
ML092310650 | 1 June 2005 | 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. | |
ML092310651 | 26 July 2005 | 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. | |
ML14120A337 | 25 April 2014 | CY-TM-170-300, Rev. 3, Offsite Dose Calculation Manual | Shutdown Margin Grab sample Offsite Dose Calculation Manual Incorporated by reference Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report Fire Protection Program Power change |
ML18121A155 | 30 April 2018 | Three Miles Island, Units 1 and 2, Combined 2017 Annual Radioactive Effluent Release Report - ODCM Change for TMI Offsite Dose Calculation Manual, Revision 5, CY-TM-170-300 | Shutdown Margin Grab sample Offsite Dose Calculation Manual Incorporated by reference FLEX Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program Power change |
ML19093A955 | 19 March 2019 | Orano Federal Services Calculation CALC-3021323, TMI-2 Canister Top-End Dose Rates for TMI-2 ISFSI License Renewal, Revision 1 | |
ML19093A957 | 19 March 2019 | Orano Federal Services Calculation CALC-3021788, TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal, Revision 1 | |
ML19182A104 | 1 July 2019 | Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E | Ultimate heat sink Time to boil Probabilistic Risk Assessment Aging Management Fukushima Dai-Ichi License Renewal Exemption Request Earthquake Control of Heavy Loads Fuel cladding Fire Protection Program Grace period Fatality |
ML21133A265 | 1 February 2021 | Calculation TMI2-EN-RPT-0002, Revision 0, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library | |
ML22010A067 | 5 January 2022 | Supplemental Information to License Amendment Request, Revision to TMl2-EN-RPT-0001 Determination of the Safe Fuel Mass Limit for Decommissioning TMl-2 | Grab sample |
ML22010A068 | 5 January 2022 | Supplemental Information to License Amendment Request, Revision to TMl2-EN-RPT-0002 MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library | |
ML22101A079 | 23 March 2022 | TMI2-EN-RPT-0001, Revision 1, Determination of the Safe Fuel Mass Limit for Decommissioning | Grab sample |
ML22105A092 | 8 April 2022 | Attachment 5 - Gpu Nuclear Calculation 4440-7380-90-017, Revision 3, Pdms SAR Section 8.2.5 Fire Analysis Source Terms | Grab sample Fire Protection Program |
TMI-09-047, Offsite Dose Calculation Manual | 24 September 2008 | Offsite Dose Calculation Manual | Shutdown Margin Grab sample Offsite Dose Calculation Manual Incorporated by reference Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program Power change |
TMI-11-078, Response to Request for Additional Information - Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds | 25 April 2011 | Response to Request for Additional Information - Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds | Safe Shutdown Earthquake Weld Overlay Hydrostatic Stress corrosion cracking Earthquake Dissimilar Metal Weld Exclusive Use Affidavit |
TMI-13-009, Response to Request for Additional Information - Relief Request RR-12-02 Re Installation of Full Structural Weld Overlay on Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds & Alloy 600 Safe-End | 17 January 2013 | Response to Request for Additional Information - Relief Request RR-12-02 Re Installation of Full Structural Weld Overlay on Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds & Alloy 600 Safe-End | Weld Overlay Dissimilar Metal Weld |
TMI-15-052, ODCM Change for TMI, Offsite Dose Calculation Manual, Revision 3, CY-TM-170-300 | 30 April 2015 | ODCM Change for TMI, Offsite Dose Calculation Manual, Revision 3, CY-TM-170-300 | Shutdown Margin Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Annual Radiological Effluent Release Report Power change |