ML12174A096
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| ML12174A096 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/22/2011 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L-12-152 | |
| Download: ML12174A096 (198) | |
Similar Documents at Davis Besse | |
|---|---|
Category:Calculation
MONTHYEARL-20-093, Offsite Dose Calculation Manual, Revision 372019-11-0404 November 2019
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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 Category:Manual MONTHYEARML24269A0632024-09-25025 September 2024
[Table view]Enclosure E: Davis-Besse Nuclear Power Station, Unit 1, Technical Requirements Manual, Revision 24 L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual ML22263A4172022-09-20020 September 2022 Enclosure E - DBNPS Unit 1, Technical Requirements Manual, Rev. 23 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual L-20-093, Offsite Dose Calculation Manual, Revision 372019-11-0404 November 2019 Offsite Dose Calculation Manual, Revision 37 L-19-177, Summary of Changes to the Firstenergy Nuclear Operating Company Quality Assurance Program Manual for Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant2019-10-0808 October 2019 Summary of Changes to the Firstenergy Nuclear Operating Company Quality Assurance Program Manual for Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant ML20142A4012019-02-13013 February 2019 Offsite Dose Calculation Manual, Revision 36 L-17-170, Submittal of 2017 Emergency Preparedness Evaluated Exercise Manual2017-05-15015 May 2017 Submittal of 2017 Emergency Preparedness Evaluated Exercise Manual L-18-092, Offsite Dose Calculation Manual, Revision 332017-03-0909 March 2017 Offsite Dose Calculation Manual, Revision 33 ML17039A6772016-11-21021 November 2016 Quality Assurance Program Manual, Rev 20 ML16208A0692016-07-15015 July 2016 Delinquent Transmittal Report ML18149A2822016-03-29029 March 2016 Offsite Dose Calculation Manual, Revision 32 L-16-134, Offsite Dose Calculation Manual, Revision 312015-06-30030 June 2015 Offsite Dose Calculation Manual, Revision 31 ML16147A0092015-01-14014 January 2015 Offsite Dose Calculation Manual, Revision 30 ML14342A6832014-11-21021 November 2014 Technical Requirements Manual, Revision 14 L-14-135, Offsite Dose Calculation Model, Revision 272013-02-27027 February 2013 Offsite Dose Calculation Model, Revision 27 ML12138A0672012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 4 L-12-152, Offsite Dose Calculation Manual, Revision 262011-11-0202 November 2011 Offsite Dose Calculation Manual, Revision 26 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 ML1014105112009-06-11011 June 2009 Offsite Dose Calculation Manual, Revision 23 L-09-111, Offsite Dose Calculation Manual, Revision 222008-09-0303 September 2008 Offsite Dose Calculation Manual, Revision 22 ML0612304032005-12-22022 December 2005 Offsite Dose Calculation Manual Revision 20.0 ML0533903582005-11-30030 November 2005 Information Request for an NRC Biennial Permanent Modifications and 10CFR 50.59 (MOD/50.59) Baseline Inspection ML0530704352005-11-0808 November 2005 Control Rod Drive Mechanism Instruction Manual ML0512502282004-12-22022 December 2004 Offsite Dose Calculation Manual, Revision 19.0 ML0424504162004-08-0404 August 2004 Submittal of Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Plan for the Davis-Besse Nuclear Power Station ML0411004492004-02-25025 February 2004 IMC 0350 Restart Checklist, Revision 3 ML0411004202004-02-20020 February 2004 0350 Panel Discussion Topics (Open Restart Checklist Items (1) ML0411004082004-02-19019 February 2004 IMC 0350 Panel Process Plan ML0512502232004-01-23023 January 2004 Offsite Dose Calculation Manual, Revision 18.0 ML0323805272003-07-30030 July 2003 Submittal of Revision 5 of Nuclear Operating Business Practice, Restart Readiness Review Extended Plant Outage (DBBP-VP-0002) ML0318304952003-07-0202 July 2003 Letter Dated 07/01/2003 to L. Myers, Firstenergy Nuclear Operating Company Transmittal of Davis-Besse Oversight Panel Restart Checklist, Revision 3 ML0314702122003-04-30030 April 2003 Annual Radiological Environmental Operating Report, January 1, 2002 Through December 31, 2002, Pages 68 Through 81 ML0314702092003-04-30030 April 2003 Annual Radiological Environmental Operating Report, January 1, 2002 Through December 31, 2002, Pages 60 Through 67 ML0314702072003-04-30030 April 2003 Annual Radiological Environmental Operating Report, January 1, 2002 Through December 31, 2002, Pages 46 Through 59 ML0314305042003-04-30030 April 2003 Annual Radiological Environmental Operating Report, Radioactive Effluent Release Report, January 1 Through December 31, 2002 ML0310702912003-04-0606 April 2003 Letter Davis-Besse 2003 Emergency Preparedness Exercise Manual ML0310007392003-04-0606 April 2003 Transmittal of Rev 6 of DB Return to Service Plan, Rev 5 of the DB Restart Action Plan, Rev 5 of DB Prog Compliance Plan, and Rev 3 of the Nuc Operating Business Practice, Restart Readiness Rev Extended Plant Outage (DBBP-VP-0002)/Letter 2024-09-25 |
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