ML16351A249
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| ML16351A249 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/14/2016 |
| From: | Structural Integrity Associates |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16351A264 | List: |
| References | |
| Download: ML16351A249 (6) | |
Similar Documents at Cooper | |
|---|---|
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
[Table view]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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