| NLS2019028, Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 0 | 24 October 2018 | Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 0 | |
| ML16351A248 | 14 December 2016 | Code Case N-513-3 Evaluation of High Pressure Service Water Piping Thinning | |
| ML16351A249 | 14 December 2016 | HPSW Wall Thinning- 1601004.301 - Appendix a Sipe Files | |
| ML15126A430 | 30 April 2015 | Offsite Dose Assessment Manual, January 1, 2014 Through December 31, 2014 and Process Control Program | Time of Discovery
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Process Control Program
Annual Radiological Effluent Release Report
Power change |
| NLS2012103, Calculation Nedc 07-048, Ccn 5C3, Revised Pressure Temperature Curves. | 27 August 2012 | Calculation Nedc 07-048, Ccn 5C3, Revised Pressure Temperature Curves. | Shutdown Margin
Hydrostatic
Maintenance Rule Program |
| ML12279A238 | 24 August 2012 | to Calculation 1100445.303, Revised P-T-Curve Calculation. | Shutdown Margin
Hydrostatic
Finite Element Analysis |
| NLS2012033, Enclosure 4 - Calculation Nedc 11-109, Rev. 0, Instrument Drift Analysis for NBI-PS-51A/B/C/D (Barksdale B2T-M12SS) | 3 October 2011 | Enclosure 4 - Calculation Nedc 11-109, Rev. 0, Instrument Drift Analysis for NBI-PS-51A/B/C/D (Barksdale B2T-M12SS) | Grace period |
| NLS2008014, Enclosure 3, Nedc 07-082, Rev 2 - Radiological Dose Analysis for a Loss of Coolant Accident (LOCA) at Cooper Nuclear Station | 13 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) | 1 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) | Safe Shutdown Earthquake
Deep Dose Equivalent |
| ML081540380 | 8 May 2008 | Enclosure 2, Design Calculation Cover Sheet, EPM Calculation 1906-07-06 Task 7.6 NFPA 805 Fire Ignition Fire Ignition Frequencies. | Safe Shutdown
Loop seal
Fire Protection Program
Fire Watch |
| NLS2007069, Calculation Nedc 06-035, Revision 0, Reactor Core Thermal Power University, Enclosure 7 | 23 October 2007 | Calculation Nedc 06-035, Revision 0, Reactor Core Thermal Power University, Enclosure 7 | Reactor Vessel Water Level |
| ML071240347 | 1 May 2007 | Enclosure 2, Cooper - Offsite Dose Assessment Manual | Time of Discovery
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Process Control Program
Annual Radiological Effluent Release Report
Power change |
| 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. | 29 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. | Deep Dose Equivalent
Recently irradiated fuel |
| NLS2005090, Calculation No. Nedc 05-019, Rev 0, Reactor Pressure Vessel Fluence Evaluation. | 9 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. | 20 November 2002 | Nedc 87-131B, Revision 8, Cooper Nuclear Station, 250 Vdc Division II Load and Voltage Study. | Safe Shutdown
Stroke time |
| NLS2003111, to Calculation No. 98-024, APRM -RBM Setpoint Calculation. | 17 May 2000 | to Calculation No. 98-024, APRM -RBM Setpoint Calculation. | Grace period |
| ML003671699 | 10 December 1999 | to Calculation Nedc 99-034, Review of Scientech Calculation 17080-M-04, Control Room, Eab, and LPZ Doses Following a Crda. | Fuel cladding |