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Category:Calculation
MONTHYEARML22105A0922022-04-0808 April 2022
Attachment 5 - Gpu Nuclear Calculation 4440-7380-90-017, Revision 3, Pdms SAR Section 8.2.5 Fire Analysis Source Terms
ML22101A0792022-03-23023 March 2022
TMI2-EN-RPT-0001, Revision 1, Determination of the Safe Fuel Mass Limit for Decommissioning
ML22010A0672022-01-0505 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
ML22010A0682022-01-0505 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
ML21133A2652021-02-0101 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
ML20301A1782020-11-23023 November 2020
U.S. Nuclear Regulatory Commission Nuclear Waste Fund Expenditures for October 2020 - Enclosure
ML20274A1802020-10-22022 October 2020
U.S. Nuclear Regulatory Commission Nuclear Waste Fund Expenditures for September 2020 - Enclosure
ML19182A1042019-07-0101 July 2019
Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E
ML19093A9572019-03-19019 March 2019
Orano Federal Services Calculation CALC-3021788, TMI-2 Canister Licon Criticality Analysis for TMI-2 ISFSI License Renewal, Revision 1
ML19093A9552019-03-19019 March 2019
Orano Federal Services Calculation CALC-3021323, TMI-2 Canister Top-End Dose Rates for TMI-2 ISFSI License Renewal, Revision 1
ML18121A1552018-04-30030 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
TMI-15-052, ODCM Change for TMI, Offsite Dose Calculation Manual, Revision 3, CY-TM-170-3002015-04-30030 April 2015
ODCM Change for TMI, Offsite Dose Calculation Manual, Revision 3, CY-TM-170-300
ML14120A3372014-04-25025 April 2014
CY-TM-170-300, Rev. 3, Offsite Dose Calculation Manual
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-End2013-01-17017 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
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 Welds2011-04-25025 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
ML0923106592009-08-11011 August 2009
Calculation No. B00000000-01717-0210-00006, Rev. 00, CRC Reactivity Calculations for Sequoyah Unit 2, Attachment I, Page 1 Through 333
ML0923106722009-08-11011 August 2009
Calculation No. B00000000-01717-0210-00006, Rev. 00, CRC Reactivity Calculations for Sequoyah Unit 2, Attachment I, Page 334 of 656 Through Attachment VI
TMI-09-047, Offsite Dose Calculation Manual2008-09-24024 September 2008
Offsite Dose Calculation Manual
ML0635401722006-11-17017 November 2006
Calculation No. C-1101-900-E000-083, Revision 4, Eab, LPZ, and CR Doses Due to Fuel Handling Accidents.
ML0526602122005-09-12012 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.
ML0923106532005-07-26026 July 2005
Calculation No. BBA000000-01717-0210-00037, Rev. 00, ECN No. 1, Enrico Fermi Fast Reactor Spent Nuclear Fuel Criticality Calculations: Intact Mode.
ML0923106512005-07-26026 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.
ML0522206382005-07-12012 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.
ML0923106502005-06-0101 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.
ML0923106492004-03-23023 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
ML0923106742003-09-26026 September 2003
Calculation No. 32-5029393-00, Commercial Reactor Reactivity Analysis for Grand Gulf, Unit 1.
ML1001305452003-08-11011 August 2003
CAL-DSU-NU-000002 Rev 00A, Limerick Unit 1 Radiochemical Assay Comparisons to SAS2H Calculations.
ML0613203522003-07-0101 July 2003
Calculation 6610-PLN-4200.01,Rev 24, Offsite Dose Calculation Manual.
ML0312901602003-04-30030 April 2003
Combined 2002 Annual Radioactive Effluent Release Report, Attachment 1, Table 1A Through Off Dose Calculation Manual, Revision 23
ML0312901302003-04-30030 April 2003
Combined 2002 Annual Radioactive Effluent Release Report
ML0316308072003-04-30030 April 2003
Combined 2002 Annual Radioactive Effluent Release Report, Section 3.0 Through Table 2.1-2
ML0309102042003-03-19019 March 2003
Response to Request for Additional Information - Integrated Leak Rate Test Deferral for License Amendment Request No. 318
ML0335105501998-05-13013 May 1998
CRC Depletion Calculations for Three Mile Island Unit 1
2022-04-08
[Table view] |
Text
DOC.20050801.0001 Engineering Change Notice I. QA: QA SSC 2. Page I of _1_
Complete only applicable items.
- 3. DocU\TII:i11 Jdl'nlificr: 4,Rev.: 5 Tille: 6. ECN:
Intact and Degraded ~lode Criticality Calculations for the CAL-DSD-l\ru-000004 OOA 2 Codisposal ofTMI-2 Spent Nuclear Fuel in a Waste Package
- 7. ,Reason ror Change:
Per LP-3.12Q-IlSC Design Calculations and Analyses Section 5.1 (2} c, "The decision of tile DEM, PCSA Manager, Criticality Manager, or peA Manager to issue calculations or analyses with a "colTlmitted" status will be based on an experienced assessment of the likelihood that the results of the calculation or analysis will change, and the dcgree of impactlhose changes will have on designs that support the regulatory submitta Is or procurelllcllt activities, based on the design's bounding conservatism."
the status designation of lmaN and Degraded A10de Criticality Calculatiollsjor tlte Codisposal uJ'liHl-2 Spellt NIIc:lear Fllel illll Waste Package (CAL-DSD-NU-000004 REV OOA) can be changed to "Commil1ed" as the results arc not expected to change in such a manner that will affect support of regulatory submiUals.
It Su~cOOs '-'hang!! Document: IDyes If, Yes,Charl~Iloc.: 181 NQ 9, Change Impact:
Inpu~ ChIit\8oo: Dyes ~No R..,\,>uJu Imp:lClcd: Dyes 181 No ASWi11pliolls Changed: Dyes 181 No ~isn 11l1PI1Cled: Dyes I8l No to. Dcscriplioo of ClmlgC: (Add~s llUY "Yr:.$** llI1S\\'ffil)
Add a "Conuniued" option in Illock 7 on the cover sheet and change the "Document Status Designation" from Preliminary to "Conunittcd", Illock 7 on the cover sheet should rcad as follows:
It Document StatuS De~lgnaliqn I
D Pretimillary ~.. {:ommttted D Final CJ Caricelled I
- 11. OnQJnalor: (Prlntl$lgP/Dare)
Abdt;lhalirn Alsaed /~d'~ :;;/2?/b'5
!1L Q,.. I, ... ',- //~~-l Checker: (PrintiSign/Dale)
Jolm Scaglione .A I\pprovcd: (I'TintiSignlDale)
William Hutchins h~&~,< zC2<~~ 2 ; 7/6' 5
