Category:Calculation
MONTHYEARNLS2019028, Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 02018-10-24024 October 2018
Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 0
ML16351A2482016-12-14014 December 2016
Code Case N-513-3 Evaluation of High Pressure Service Water Piping Thinning
ML16351A2492016-12-14014 December 2016
HPSW Wall Thinning- 1601004.301 - Appendix a Sipe Files
ML15126A4302015-04-30030 April 2015
Offsite Dose Assessment Manual, January 1, 2014 Through December 31, 2014 and Process Control Program
NLS2012103, Calculation Nedc 07-048, Ccn 5C3, Revised Pressure Temperature Curves.2012-08-27027 August 2012
Calculation Nedc 07-048, Ccn 5C3, Revised Pressure Temperature Curves.
ML12279A2382012-08-24024 August 2012
to Calculation 1100445.303, Revised P-T-Curve Calculation.
NLS2012033, Enclosure 4 - Calculation Nedc 11-109, Rev. 0, Instrument Drift Analysis for NBI-PS-51A/B/C/D (Barksdale B2T-M12SS)2011-10-0303 October 2011
Enclosure 4 - Calculation Nedc 11-109, Rev. 0, Instrument Drift Analysis for NBI-PS-51A/B/C/D (Barksdale B2T-M12SS)
NLS2008014, Enclosure 3, Nedc 07-082, Rev 2 - Radiological Dose Analysis for a Loss of Coolant Accident (LOCA) at Cooper Nuclear Station2008-10-13013 October 2008
Enclosure 3, Nedc 07-082, Rev 2 - Radiological Dose Analysis for a Loss of Coolant Accident (LOCA) at Cooper Nuclear Station
NLS2009044, Enclosure 3, Calculation, Nedc 07-082, Rev. 2, Radiological Dose Analysis for a Loss of Coolant Accident (LOCA) at Cooper Nuclear Station, (Non-Proprietary Version)2008-10-0101 October 2008
Enclosure 3, Calculation, Nedc 07-082, Rev. 2, Radiological Dose Analysis for a Loss of Coolant Accident (LOCA) at Cooper Nuclear Station, (Non-Proprietary Version)
ML0815403802008-05-0808 May 2008
Enclosure 2, Design Calculation Cover Sheet, EPM Calculation 1906-07-06 Task 7.6 NFPA 805 Fire Ignition Fire Ignition Frequencies.
NLS2007069, Calculation Nedc 06-035, Revision 0, Reactor Core Thermal Power University, Enclosure 72007-10-23023 October 2007
Calculation Nedc 06-035, Revision 0, Reactor Core Thermal Power University, Enclosure 7
ML0712403472007-05-0101 May 2007
Enclosure 2, Cooper - Offsite Dose Assessment Manual
NLS2005075, Calculation Nedc 05-031, Review of Alion Calculation ALION-CAL-NPPD-3236-001, Radiological Dose Analysis for a Fuel Handling Accident (FHA) at Cooper Nuclear Station.2005-09-29029 September 2005
Calculation Nedc 05-031, Review of Alion Calculation ALION-CAL-NPPD-3236-001, Radiological Dose Analysis for a Fuel Handling Accident (FHA) at Cooper Nuclear Station.
NLS2005090, Calculation No. Nedc 05-019, Rev 0, Reactor Pressure Vessel Fluence Evaluation.2005-05-0909 May 2005
Calculation No. Nedc 05-019, Rev 0, Reactor Pressure Vessel Fluence Evaluation.
NLS2009057, Nedc 87-131B, Revision 8, Cooper Nuclear Station, 250 Vdc Division II Load and Voltage Study.2002-11-20020 November 2002
Nedc 87-131B, Revision 8, Cooper Nuclear Station, 250 Vdc Division II Load and Voltage Study.
NLS2003111, to Calculation No. 98-024, APRM -RBM Setpoint Calculation.2000-05-17017 May 2000
to Calculation No. 98-024, APRM -RBM Setpoint Calculation.
ML0036716991999-12-10010 December 1999
to Calculation Nedc 99-034, Review of Scientech Calculation 17080-M-04, Control Room, Eab, and LPZ Doses Following a Crda.
2018-10-24
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