ML15155B367
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| ML15155B367 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/01/2014 |
| From: | Summers T J FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML15155B372 | List: |
| References | |
| L-15-0105 | |
| Download: ML15155B367 (201) | |
Similar Documents at Davis Besse | |
|---|---|
Category:Calculation
MONTHYEARL-20-093, Offsite Dose Calculation Manual, Revision 372019-11-0404 November 2019
[Table view]Offsite Dose Calculation Manual, Revision 37 ML20142A4012019-02-13013 February 2019 Offsite Dose Calculation Manual, Revision 36 L-16-134, Offsite Dose Calculation Manual, Revision 312015-06-30030 June 2015 Offsite Dose Calculation Manual, Revision 31 L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits.2015-05-0606 May 2015 C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits. ML16147A0092015-01-14014 January 2015 Offsite Dose Calculation Manual, Revision 30 ML15280A3092014-09-0303 September 2014 C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 1 of 7 ML15280A3032014-09-0303 September 2014 C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 4 of 7 ML15280A3042014-09-0303 September 2014 C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 5 of 7 ML15280A3052014-09-0303 September 2014 C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 6 of 7 ML15280A3062014-09-0303 September 2014 C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 7 of 7 ML15280A3102014-09-0303 September 2014 C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 2 of 7 ML15280A3112014-09-0303 September 2014 C-CSS-099.20-063, Rev 1, Shield Building Design Calculation. Part 3 of 7 L-15-010, Offsite Dose Calculation Manual, Revision 292014-05-14014 May 2014 Offsite Dose Calculation Manual, Revision 29 ML15155B3672014-02-0101 February 2014 Offsite Dose Calculation Manual, Revision 28 L-14-135, Offsite Dose Calculation Model, Revision 272013-02-27027 February 2013 Offsite Dose Calculation Model, Revision 27 ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. ML13009A3742012-12-11011 December 2012 Enclosure a to L-12-444, Calculation 32-9195423-000, DB-1 EMA of RPV Inlet & Outlet Nozzle-to-Shell Welds for 60 Years - Non-Proprietary. ML12213A3332012-07-27027 July 2012 SB-0033 - Calculation C-CSS-099.20-054, Revision 0 ML12213A3342012-07-27027 July 2012 SB-0034 - Bechtel Response to Calculation C-CSS-099.20-054, Revision 0 L-12-152, Offsite Dose Calculation Manual, Revision 262011-11-0202 November 2011 Offsite Dose Calculation Manual, Revision 26 ML15280A3082011-10-31031 October 2011 C-CSS-099.20-055, Rev. 01, Ii/I Evaluation for Architectural Flute Shoulder. ML11109A0842011-04-15015 April 2011 Attachments B-D, to L-11-107, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application L-11-150, Offsite Dose Calculation Manual, Rev. 242011-03-11011 March 2011 Offsite Dose Calculation Manual, Rev. 24 ML12174A0962011-02-22022 February 2011 Offsite Dose Calculation Manual, Revision 25 ML1014004062010-05-11011 May 2010 Areva Calculation 32-9136508-002, DB-1 CRDM Nozzle J-Groove Weld Flaw Evaluation for Idtb Repair, Enclosure B ML1014004072010-05-0707 May 2010 Areva Calculation 32-9135800-001, DB-1 CRDM Nozzle Weld Anomaly Flaw Evaluation of Idtb Repair, Enclosure C ML1014004052010-05-0606 May 2010 Areva Calculation 32-9136884-001, DB-1 CRDM Nozzle Weld Anomaly Flaw Evaluation of Idtb Alternate Repair with Alloy 52M/82, Enclosure a L-10-131, Additional Information Regarding 10 CFR 50.55a Request RR-A34 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles2010-04-21021 April 2010 Additional Information Regarding 10 CFR 50.55a Request RR-A34 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles ML1011101482010-04-0808 April 2010 Calculation 32-91358000-000, DB-1 CRDM Nozzle Weld Anomaly Flaw Evaluation of Idtb Repair. ML0933603302009-11-23023 November 2009 Calculation, 0800368.325, Rev. 0, ASME Code, Section Iii Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair. L-09-268, Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches).2009-11-0202 November 2009 Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches). ML0933603312009-07-20020 July 2009 Calculation, 0800368.326, Rev. 0, Crack Growth Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair. ML0933603292009-07-10010 July 2009 Calculation, 0800368.324, Rev. 0, Residual Stress Analysis of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair. ML1014105112009-06-11011 June 2009 Offsite Dose Calculation Manual, Revision 23 ML0933603262009-05-27027 May 2009 Calculation, 0800368.320, Rev. 1, Optimized Weld Overlay Sizing for the 28 I.D. Outlet/Discharge Reactor Coolant Pump Nozzle. ML0933603282009-05-23023 May 2009 Calculation, 0800368.323, Rev. 1, Thermal and Unit Mechanical Stress Analyses for Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair. ML0933603272009-05-22022 May 2009 Calculation, 0800368.322, Rev. 1, Finite Element Models of the Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair. ML0933603242009-04-21021 April 2009 Calculation, 0800368.301, Rev 0, Material Properties for Davis-Besse Unit 1, RCP Suction, RCP Discharge, Cold Leg Drain and Core Flood Nozzles Preemptive Weld Overlay Repairs. ML0933603252009-04-0808 April 2009 Calculation, 0800368.311, Rev. 0, Design Loads for the 28 I.D. Reactor Coolant Pump (RCP) Suction and Discharge Nozzles. L-09-111, Offsite Dose Calculation Manual, Revision 222008-09-0303 September 2008 Offsite Dose Calculation Manual, Revision 22 L-08-056, Reactor Protection System High Flux Trip Setpoint Calculation2008-02-14014 February 2008 Reactor Protection System High Flux Trip Setpoint Calculation IR 05000124/20280082007-04-12012 April 2007 Enclosure 3, Areva Np Calculation 32-5012428-08, Davis-Besse Heat Balance Uncertainty. ML0710705782007-04-12012 April 2007 Enclosure 3, Areva Np Calculation 32-5012428-08, Davis-Besse Heat Balance Uncertainty. ML0612304032005-12-22022 December 2005 Offsite Dose Calculation Manual Revision 20.0 ML0512502282004-12-22022 December 2004 Offsite Dose Calculation Manual, Revision 19.0 ML0512502232004-01-23023 January 2004 Offsite Dose Calculation Manual, Revision 18.0 ML0310401082003-03-31031 March 2003 Computations on Failure Pressure of as-found Cavity FENOC Cavity Analysis with Handwritten Notes ML0308501852003-02-0505 February 2003 Preliminary Responses to NRC Staff Comments & Questions on Davis Besse Safety Significance Assessment 2019-02-13 |
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