ML071450150
From kanterella
Revision as of 18:08, 23 October 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
| ML071450150 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/09/2007 |
| From: | Garrett T J Wolf Creek |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ET 07-0018 | |
| Download: ML071450150 (94) | |
Similar Documents at Wolf Creek | |
|---|---|
Category:- No Document Type Applies
MONTHYEARML22034A3952022-02-16016 February 2022
[Table view]Enclosure 3 - IP 96001 CY2021 - IR 8 Baseline Inspection Completion ML22034A3972022-02-16016 February 2022 Enclosure 2 - IP 92707 CY2021 - IR 8 Baseline Inspection Completion ML22034A3992022-02-16016 February 2022 Enclosure 1 - IP 71130.03 Cy 2021 - IR 8 Baseline Inspection Completion ML18044A1052018-02-0707 February 2018 Summary of Changes to One Procedure and One Form That Implement the Wolf Creek Generating Station (WCGS) Radiological Emergency Response Plan (Rerp). Includes Procedure AP 06-004, Rev. 8 & Form Epf 06-011-01, Rev. 5 ML17284A1852017-10-0505 October 2017 Attachment to RA 17-0110 - Summary of Changes to Two Procedures and Two Forms That Implement the Wolf Creek Generating Station Radiological Emergency Response Plan ML17060A1492017-02-10010 February 2017 FOIA/PA-2017-0110 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed. Part 3 of 6 ML17060A1462017-02-10010 February 2017 FOIA/PA-2017-0110 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed. Part 1 of 6 ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML14258B0892014-09-18018 September 2014 Public Notice, Notice of Consideration of Issuance of Amendment, Revise Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Completion Time Extension (Exigent Circumstances) ML13246A3712013-06-19019 June 2013 Ope Communication on Augmented Inspection - Wolf Creek Generating Station Loss of Offsite Power and Notification of Unusual Event ML13073A2052013-03-15015 March 2013 YT020130045 - Wolf Creek Generating Station - Enclosure - Preliminary Accident Sequence Precursor Analysis of January 2012 Loss of Offsite Power Event ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1013703072010-05-12012 May 2010 Proposed License Amendment Request Regarding Presure Boundary Designation for Pressurizer Power Operated Relief Valves ML0933507512010-01-14014 January 2010 Temporary Instruction 2515/180, Managing Fatigue ML0806704192008-03-0707 March 2008 CDBI Findings ML0804603992008-02-13013 February 2008 Power Reactor Inattentive Officer Findings 2004-Present ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0720000552007-07-17017 July 2007 License Renewal; USAR Information on Liquid, Gaseous, and Solid Radioactive Waste Management Systems ML0714501502007-05-0909 May 2007 Responses A39 - A45 and A48 - A50 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application ML0714501492007-05-0909 May 2007 Responses A11 - A19 and A23 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application ML0717704612007-02-0606 February 2007 Procedure AP 05F-001, Rev. 3, Design Verification. ML0634705992006-12-14014 December 2006 Plant Service List ML0717704602006-07-12012 July 2006 Procedure AP 05-005, Rev. 11A, Design, Implementation & Configuration Control of Modifications. ML0607502682006-03-10010 March 2006 Protection of Safe Shutdown Capabilities ML0606902752006-03-0303 March 2006 Plant Engineering Branch Open Items, Interim Safety Basis ML0606902792006-02-28028 February 2006 Revised Oversight Process - Item List Report ML0606902892005-10-31031 October 2005 PIR 20052757 Information ML0505404692004-02-10010 February 2004 Dynamic Web Page Printout Dated 02/10/2004, ROP PIM Report - All Sites - Event Dates: 01/01/2003 - 02/10/2004 ML0505404642004-02-0909 February 2004 Dynamic Web Page Printout Dated 02/09/2004 Regarding Applied Violations for Nuclear Power Plants ML0329401042003-10-0707 October 2003 Riv Backfit Status ML0606902772003-05-30030 May 2003 Sp - 10 CFR-50 Appendix R - Fire Protection of Safe Shutdown Capability ML0329400982003-03-27027 March 2003 Riv Backfit Status 2022-02-16 Category:Environmental Protection Plan MONTHYEARML0714501532007-05-0909 May 2007
[Table view]Responses A68 - A69 and A71 - A75 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application ML0714501502007-05-0909 May 2007 Responses A39 - A45 and A48 - A50 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application 2007-05-09 Category:Environmental Report MONTHYEARML13127A0842013-04-29029 April 2013
[Table view]2012 Annual Radioactive Effluent Release Report - Report 36 ML13142A3102013-04-24024 April 2013 Operating Corp. - Annual Radiological Environmental Operating Report ML11123A1932011-04-27027 April 2011 Submittal of 2010 Annual Radiological Environmental Operating Report ML11109A0662011-04-11011 April 2011 2010 Annual Environmental Operating Report ML0714304972007-05-0909 May 2007 Responses 39, 41- 44, and 46 - 51, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714303632007-05-0909 May 2007 Responses 2 - 10, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714303672007-05-0909 May 2007 Response 11, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714303722007-05-0909 May 2007 Responses 20 - 29, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714303822007-05-0909 May 2007 Responses 30 - 33, and 38, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714305402007-05-0909 May 2007 Responses 52 - 56, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714305472007-05-0909 May 2007 Responses 58 - 62, 67, 69, and 70, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714305882007-05-0909 May 2007 Responses 12 - 15, 17, and 19, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0714403742007-05-0909 May 2007 Responses 1, 2, 3, 5, 8, 9 & 10 to Environmental Report - References of NRC Request for Additional Information Re License Renewal Application ML0714403772007-05-0909 May 2007 Response 12 to Environmental Report - References of NRC Request for Additional Information Re License Renewal Application ML0714501482007-05-0909 May 2007 Responses A1 - A10 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application ML0714501492007-05-0909 May 2007 Responses A11 - A19 and A23 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application ML0714501502007-05-0909 May 2007 Responses A39 - A45 and A48 - A50 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application ML0714501512007-05-0909 May 2007 Responses A51 - A54 and A61 - A66 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application ML0714501732007-05-0909 May 2007 Responses A24 - A30, A33 and A36 - A37 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application ML0714305932007-05-0909 May 2007 Response 64, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application ML0711501302007-04-19019 April 2007 2006 Annual Radiological Environmental Operating Report for the Period of January 1, 2006 Through December 31, 2006 ML0633803132006-11-30030 November 2006 Transmission Lines Figure 3-2 ML0627703052006-09-27027 September 2006 Applicant'S Environmental Report; Operating License Renewal Stage ML0612301102006-04-27027 April 2006 Annual Radiological Environmental Operating Report ML0511202022005-04-15015 April 2005 2004 Annual Radiological Environmental Operating Report ML0510404282005-04-0808 April 2005 2004 Annual Environmental Operating Report ML0512403392004-12-31031 December 2004 Annual Radioactive Effluent Release Report, Report 28, 01/01/2004 Through 12/31/2004 ML0512403482004-09-29029 September 2004 Attachment I, Wolf Creek Generating Station, Administrative Procedure AP 07B-003, Revision 5, Offsite Dose Calculation Manual. ML0411200432004-04-15015 April 2004 Annual Radiological Environmental Operating Report ML0411200752004-04-14014 April 2004 Annual Environmental Operating Report ML0312605242003-04-29029 April 2003 Annual Environmental Operating Report RA-03-0059, Submittal of Wolf Creek Nuclear Operating Corporation Evaluation of Stress Corrosion Cracking for Component Cooling Water System Piping2003-04-18018 April 2003 Submittal of Wolf Creek Nuclear Operating Corporation Evaluation of Stress Corrosion Cracking for Component Cooling Water System Piping 2013-04-29 Category:Memoranda MONTHYEARML24297A6392024-10-30030 October 2024
[Table view]Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML24268A0722024-09-24024 September 2024 Summary of August 28, 2024, Public Meeting to Discuss Cyber Security Regulatory Issues Regarding Wolf Creeks Implementation of Advanced Remote Monitoring Using Wireless ML23179A2132023-07-0505 July 2023 Approval for Credit for the Wolf Creek Generating Station Operational Safety Review Team to the Baseline Inspection Samples/Hours ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21309A5482021-11-15015 November 2021 NSIR Staff Review of the Wolf Creek Generating Stations Security Plan Training & Qualification Plan & Safeguards Contingency Plan for the Verification of ASM EA 20 091 Incorporation ML21243A4492021-09-0202 September 2021 ISFSI Technical Assistance Request - Review of Physical Security Plan ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML17019A2912017-01-19019 January 2017 Notice of Closed Regulatory Conference with Wolf Creek Generating Station ML17019A2932017-01-19019 January 2017 Notice of Closed Regulatory Conference with Wolf Creek Generating Station ML16064A1872016-03-0404 March 2016 Closed Pre-Decisional Enforcement Conference with Wolf Creek Nuclear Operating Corporation ML15251A0092015-09-11011 September 2015 Review of Revision 28 to the Updated Safety Analysis Report ML15015A1712015-01-0808 January 2015 Focused Baseline Inspection at the Wolf Creek Site for a Major Essential Service Water Modification ML14197A3442014-07-25025 July 2014 Review of Revision 27 to the Updated Safety Analysis Report ML13204A2432013-07-24024 July 2013 Notice of Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13109A2342013-07-12012 July 2013 Safety Evaluation Regarding Wolf Creek Generating Station - Loss of Offsite Power and Augmented Inspection, Issue for Resolution 2012-004 ML13179A1012013-07-0909 July 2013 7/30/13 Notice of Forthcoming Preapplication Meeting with Wolf Creek Nuclear Operating Company to Discuss Proposed Transition to Westinghouse Methodologies for Core Design and Non-LOCA Safety Analyses at Wolf Creek Generating Station ML13093A0592013-04-0202 April 2013 Public Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Performance Assessment Results for Wolf Creek Generating Station for 2012 ML13078A1552013-03-20020 March 2013 License Amendment Request to Change Diesel Generator Surveillance Requirements ML12249A0292012-09-0606 September 2012 9/20/12 Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Transition from Current to NRC-Approved Westinghouse Methodologies for Performing the Core Design and Non-LOCA Safety Wolf Creek Station ML1222602142012-08-16016 August 2012 Iolb Evaluation of Ifr 2012-04 Relating to Wolf Creek Loss of Offsite Power and Notification of Unusual Event ML12011A1012012-01-19019 January 2012 Summary of Meeting with NEI and to Address Di&C Issues ML1101106702011-02-0707 February 2011 Fire Protection Safety Evaluation Input for Wolf Creek Generating Station Regarding License Amendment Request for Deviation from the Fire Protection Program Requirements ML1006010322010-03-0101 March 2010 Cy 2009 Baseline Inspection Completion ML0929300152009-10-20020 October 2009 Revised Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 ML0928003162009-10-16016 October 2009 Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/0209 and 8/27/2009, Respectively ML0925404602009-09-10010 September 2009 Summary of Phone Call with Industry to Issues Related to Eccentricity of the Steam Generator Tube-to-Tubesheet Joints in the Finite Element Model Used for the Technical Basis of the Permanent Alternate Repair Criteria License Amendment Requ ML0920306202009-07-31031 July 2009 Notice of Forthcoming Conference Call with Union Electric Company and Wolf Creek Nuclear Operating Company Re Draft Requests for Additional Information on Generic Letter 2004-02 for Callaway Plant and Wolf Creek Creek Generating Station ML0917002962009-07-30030 July 2009 Issuance of Amendment 183, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to Extend the Surveillance Frequency on ESFAS Slave Relays from 92 Days to 18 Months ML0835705252008-12-24024 December 2008 Meeting Notice, Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Pre-Application of Post-fire Safe Shutdown Issues at Wolf Creek ML0829405182008-11-10010 November 2008 Renewal of Full-Power Operating License for the Wolf Creek Generating Station, Unit 1 ML0813006882008-05-0909 May 2008 03/05/2008 Meeting Minutes of Subcommittee on Plant License Renewal Regarding Wolf Creek Generating Station ML0812001002008-04-29029 April 2008 End of Cycle Meeting with Wolf Creek Nuclear Operation Corporation IR 05000482/20080072008-04-24024 April 2008 IR 05000482-08-007, on 01/15/2008 - 03/13/2008, Wolf Creek Generating Station, NRC Special Inspection ML0810805452008-04-18018 April 2008 05/01/2008-Notice of Forthcoming Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Safety Evaluation Report Open Items Related to Metal Fatigue Analyses for License Renewal ML0807904692008-04-10010 April 2008 Summary of Teleconference with Wolf Creek Nuclear Operating Corporation, Ameren Union Electric Company for Callaway Plant, and Performance Contracting, Inc. Containment Sump Head Loss Testing ML0802500852008-03-26026 March 2008 Summary of Second Conference Call Held on January 16, 2008, with PWR Licensees on New Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0807404192008-03-14014 March 2008 Assessment of Inspections of Dissimilar Metal Butt Welds in a Retired Pressurizer ML0807304562008-03-13013 March 2008 Cy 2007 Baseline Inspection Completion ML0804503232008-03-0303 March 2008 Summary of Third Conference Call Held with Pressurized-Water Reactor Licensees on Status of NRC Review of License Amendment Requests for Steam Generator Tube Inspections ML0807300242008-02-22022 February 2008 Status Report and Proposed Agenda for the ACRS Subcommittee on March 5, 2008 Related to the License Renewal Application of Wolf Creek Generating Stations Unit 1 ML0804504682008-02-19019 February 2008 Federal Register Notice Regarding the Meeting of the ACRS Subcommittee on Wolf Creek Plant License Renewal Application, March 5, 2008 ML0803603712008-02-0707 February 2008 Advisory Sub-Committee on Reactor Safeguards Review of the Wolf Creek Generating Station, License Renewal Application - Safety Evaluation Report with Open Items ML0800901542008-01-22022 January 2008 Summary of Conference Call Held with PWR Licensees on the Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages ML0733103642007-11-27027 November 2007 Revised Notice of Meeting with Wolf Creek Nuclear Operating Corp, to Discuss NRC Staff'S Request for Information on Licensee'S Supplemental Letter Dated September 27, 2007, to the Application Dated February 21, 2006, to Revise TS 5.5.9 ML0733101982007-11-27027 November 2007 Notice of Meeting with Wolf Creek Nuclear Operating Corporation, to Discuss NRC Staff'S Request for Additional Information on Licensee'S Proposed Main Steam and Feedwater Isolation System Modification in Its Application Dated March 14, 2007 ML0732500032007-11-21021 November 2007 Memo to Thomas G. Hiltz Key Issues for Discussion for November 28, 2007 Meeting on Steam Generator Tube Inspection License Amendment (Tac MD0197) 2024-09-24 Category:Updated Final Safety Analysis Report (UFSAR) MONTHYEARML24114A1912024-04-15015 April 2024
[Table view]Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, E-1F9910, Rev. 19, Post-Fire Safe Shutdown Area Analysis ML24114A1602024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, M-663-00017A, Revision W01, Attachment C Through G3C, Fire Protection Evaluations for Unique or Unbounded Fire Wrap Configurations ML24114A1482024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 8, Figures ML24114A1882024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013, Rev. 4-CN007, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1892024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, EQSD-II, Rev. 35, Equipment Qualification Summary Document ML24114A1742024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Drawing E-1F9900, Rev. 10, Post-Fire Safe Shutdown Operator Manual Actions ML24114A1852024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, E-1F9905, Rev. 12, Fire Hazard Analysis ML24114A1862024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Rev. 14. Quality Program Manual ML24114A1782024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013, Rev. 4, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1592024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, M-663-00017A, Fire Protection Evaluations for Unique or Unbounded Fire Barrier Configurations, Rev. 4 ML24114A1362024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Cover Sheet ML24114A1382024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 7, Instrumentation and Controls ML24114A1422024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 12, Radiation Protection ML24114A1312024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 16, Relocated Technical Specifications ML24114A1752024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, E-1F9910, Rev. 18, Post-Fire Safe Shutdown Area Analysis ML24114A1562024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 12, Figures ML24114A1832024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, E-1F9905, Rev. 14, Fire Hazard Analysis ML24114A1802024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, EQSD-I, Rev. 19, Equipment Qualification Design Basis Document ML24114A1572024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 18, Figures ML24114A1402024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 2, Site Characteristics ML24114A1332024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 2, Figures ML24114A1322024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Questions 005.1 Through 031.20 ML24114A1372024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 8, Electric Power ML24114A1272024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 18, Response to NUREG-0737 Clarification of TMI Action Plan Requirements ML24114A1392024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 5, Reactor Coolant System and Connected Systems ML24114A1872024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013, Rev. 4-CN008, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1292024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 14, Initial Test Program ML24114A1532024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 5, Figures ML24114A1842024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013, Rev. 4-CN004, Post-Fire Shutdown (PFSSD) Analysis ML24114A1282024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 13, Conduct of Operating ML24114A1732024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013, Rev. 4-CN011, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1922024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013, Rev. 4-CN002, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1822024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013, Rev. 4-CN009, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1352024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 9, Auxiliary Systems ML24114A1522024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 11, Figures ML24114A1472024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 6, Figures ML24114A1612024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, M-663-00017A, Revision W08, Appendix G3D to H, Structural Steel Fireproofing Data ML24114A1502024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 7, Figures ML24114A1342024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 4, Reactor ML24114A1772024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, E-1F9915, Rev. 16, Design Basis Document for Ofn RP-017, Control Room Evaluation ML24114A1622024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, M-663-00017A, Attachment B7 Through B13, Fire Protection Evaluation for Penetrant Size Exceeding Typical Detail B-1 Limitation ML24114A1242024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 3, Design of Structures, Components, Equipment, and Systems ML24114A1552024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 1, Figures ML24114A1792024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation, XX-E-013, Rev. 4-CN006, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1812024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013, Rev. 4-CN010, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1492024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 9, Figures ML24114A1262024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 11, Radioactive Waste Management ML24114A1512024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 10, Figures ML24114A1762024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Calculation XX-E-013. Rev. 4-CN003, Post-Fire Safe Shutdown (PFSSD) Analysis ML24114A1412024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 6, Engineered Safety Features 2024-04-15 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML071450150&oldid=1129619"