ML16257A153
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ML16257A153 | |
Person / Time | |
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Site: | Waterford ![]() |
Issue date: | 08/25/2016 |
From: | Entergy Operations |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML16256A115 | List:
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References | |
W3F1-2016-0053 | |
Download: ML16257A153 (1) | |
Similar Documents at Waterford | |
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Category:Drawing
MONTHYEARML20258A0922019-09-11011 September 2019
[Table view]11 to Final Safety Analysis Report, Reference Drawings (EPID L-2020-LLA-0164) - Redacted ML20255A2572018-07-25025 July 2018 10 to Final Safety Analysis Report, Reference Drawings (EPID L-2020-LLA-0164) - Redacted ML16344A2932016-08-25025 August 2016 Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Section 5.1, Figures 5.1-1 Through 5.1-4 ML16344A2502016-08-25025 August 2016 Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Appendix 3.6A, Figures 3.6A-1 Through 3.6A-67 W3F1-2016-0053, Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.8, Figures 3.8-1 Through 3.8-472016-08-25025 August 2016 Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.8, Figures 3.8-1 Through 3.8-47 ML16256A2102016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 4, Reactor, Section 4.3, Figures 4.3-1 Through 4.3-60 ML16344A2962016-08-25025 August 2016 Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Section 5.2, Figures 5.2-1 Through 5.2-30 ML16344A2712016-08-25025 August 2016 Redacted - Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 4, Reactor, Appendix 4.3A, Figures 4.3A-1 Through 4.3A-19b ML16256A1842016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.7, Figures 3.7-1 Through 3.7-36 ML16257A1522016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 15, Accident Analyses, Section 2, Figures 15.2-1 Through 15.2-65 ML16256A1962016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Appendix 3.6B, Figures 2.1.1 Through 4.19 ML16256A1982016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.9, Figures 3.9-1 Through 3.9-20 ML16256A1832016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Appendix 3.6C, Figures 3.6C-1 Through 3.6C-9 ML16256A2132016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 4, Reactor, Section 4.4, Figures 4.4-1 Through 4.4-11 ML16357A7602016-08-25025 August 2016 Redacted Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 4, Reactor, Section 4.2, Figures 4.2-1 Through 4.2-12 ML16257A1532016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 15, Accident Analyses, Appendix B, Figure 15B-1 ML16256A1852016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.7A, Figures 3.7A-1 Through 3.7A-4 ML16257A2672015-07-0101 July 2015 09 to Final Safety Analysis Report, Drawing G162, Sh. 2, Rev. 37, Flow Diagram Sampling System ML16257A2692014-11-13013 November 2014 09 to Final Safety Analysis Report, Drawing G162, Sh. 1, Rev. 24, Flow Diagram Sampling System W3F1-2010-0050, Drawing G287, Revision 21, 125 Vdc and 120 Vac One Line Diagram. Sheet 12008-06-0202 June 2008 Drawing G287, Revision 21, 125 Vdc and 120 Vac One Line Diagram. Sheet 1 ML0612801112005-06-0606 June 2005 ER-W3-2004-0122-000, Pressurizer Heater Sleeve and Instrument Nozzle Repair ML0612800912005-02-25025 February 2005 ER-W3-2004-0122-000, Pressurizer Heater Sleeves and Instrument Nozzles Weld Repair ML16257A2702004-01-29029 January 2004 09 to Final Safety Analysis Report, Drawing G162, Sh. 6, Rev. 5, Flow Diagram Sampling System ML0403503142004-01-27027 January 2004 Entergy Operations Waterford 3 S.E.S. Schematic of Water Flow, NPDES Permit No. LA0007374 ML0403503022004-01-27027 January 2004 S.E.S. Unit No. 3, 1165 MW Installation, NPDES Outfall Locations ML0331401672003-11-0404 November 2003 Table, CEDM Nozzle Freespan Lengths ML0223201952002-07-30030 July 2002 Drawing SK-G-M-529, Rwsp Refuel Water Storage Purification System ML0223201422002-07-30030 July 2002 Drawing SK-G-M-528, Rwsp Refuel Water Storage Purification System ML0223202032002-07-30030 July 2002 Drawing SK-G-M-530, Rwsp Refuel Water Storage Purification System 2019-09-11 Category:Final Safety Analysis Report (FSAR) MONTHYEARML20258A0922019-09-11011 September 2019
[Table view]11 to Final Safety Analysis Report, Reference Drawings (EPID L-2020-LLA-0164) - Redacted ML19268A1252019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 04 - Reactor ML19268A1492019-09-11011 September 2019 11 to Final Safety Analysis Report, Instructions ML19268A1412019-09-11011 September 2019 11 to Final Safety Analysis Report, Table of Contents ML19268A1482019-09-11011 September 2019 11 to Final Safety Analysis Report, EC Markups July 2019 W3F1-2019-0064, Submittal of Revision 311 to Final Safety Analysis Report2019-09-11011 September 2019 Submittal of Revision 311 to Final Safety Analysis Report ML20258A0872019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 05 - Reactor Coolant System and Connected Systems (EPID L-2020-LLA-0164) - Redacted ML19268A1282019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 07 - Instrumentation and Controls ML19268A1342019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 13 - Organizational Structure ML19268A1312019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 10 - Steam and Power Conversion System ML20258A0882019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 06 - Engineered Safety Features (EPID L-2020-LLA-0164) - Redacted ML19268A1232019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 18 - Aging Management Programs and Activities ML19268A1292019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 08 - Electric Power ML19268A1352019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 14 - Initial Test Program ML19268A1302019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 09 - Auxiliary Systems ML20258A0912019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 12 - Radiation Protection (EPID L-2020-LLA-0164) - Redacted ML20258A0712019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 01 - Introduction and General Description of Plant - Redacted ML19268A1362019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 15 - Accident Analyses ML19268A1372019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 17 - Quality Assurance ML19268A1322019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 11 - Radioactive Waste Management ML18229A1782018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML20255A2182018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (EPID L-2020-LLA-0164) - Redacted ML20255A2532018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 12, Radiation Protection (EPID L-2020-LLA-0164) - Redacted ML18229A1832018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 13, Organization Structure ML18229A1892018-07-25025 July 2018 10 to Final Safety Analysis Report, List of Effective Pages, Final W3F1-2018-0041, 10 to Final Safety Analysis Report, Table of Contents2018-07-25025 July 2018 10 to Final Safety Analysis Report, Table of Contents ML18229A1722018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 4, Reactor ML18229A1852018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 15, Accident Analyses ML20255A2392018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems (EPID L-2020-LLA-0164) - Redacted ML18229A1862018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 17, Quality Assurance ML18229A1772018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML18229A1762018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 8, Electric Power ML20255A2572018-07-25025 July 2018 10 to Final Safety Analysis Report, Reference Drawings (EPID L-2020-LLA-0164) - Redacted ML18229A1752018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML18229A1802018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20255A2422018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features (EPID L-2020-LLA-0164) - Redacted ML18229A1842018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 14, Initial Test Program W3F1-2017-0078, Final Safety Analysis Report, Revision 3102017-12-0606 December 2017 Final Safety Analysis Report, Revision 310 ML16257A1512016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 15, Accident Analyses, Appendix D, Figures 15D.2-1 Through 15D.2-7 ML16256A1272016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant, Section 1.4 ML16256A4902016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System, Section 10.4.9A, Figure 10.4.9A-1 ML16257A1442016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 15, Accident Analyses, Appendix 15A, Figures 15A.3-1 Through 5A.3-2 ML16256A3262016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 7, Instrumentation and Controls, Appendix 7.7A ML16256A2832016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features, Appendix 6.2B ML16256A1932016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.4 - Water Level (Flood) Design ML16256A1822016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Appendix 3.6C - Bend Force Calculation in a Piping System Using CALPLOTF2421 ML16256A4332016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 8, Table of Contents ML16256A1922016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems, Section 3.10 - Seismic Qualifications of Seismic Category 1 Instrumentation & Electrical Equipment ML16257A0942016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 13, Organizational Structure, Section 13.2 ML16256A1232016-08-25025 August 2016 09 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant, Section 1.0 2019-09-11 |
Text
1 I O -
- 1 1 8
l o -
2 8
9 N O T E S :
- 1. CONTAINMENT SPRAYED VOLUME
- 2. CONTAINMENT UNSPRAYED VOLUME SHIELD BUILDING
- 4. NEGATIVE PRESSURE AREA OF THE REACTOR AUXILIARY BUILDING
- 5. SHIELD BUILDING VENTILATION SYSTEM
- 6. CONTROLLED VENTILATION AREA SYSTEM
- 7. CONTAINMENT SPRAYS 12 6
-t-4
- 8. AIR EXCHANGE BETWEEN REGIONS 1 AND 2
- 9. LEAKAGE INTO THE SHIELD BUILDING
- 10. LEAKAGE INTO THE NEGATIVE PRESSURE AREA OF THE REACTOR AUXILIARY BUILDING
- 11. BYPASS LEAKAGE
- 12. SHIELD BUILDING VENTILATION SYSTEM RECIRCULATION
- 13. SHIELD BUILDING VENTILATION SYSTEM RELEASE
- 14. CONTROLLED VENTILATION AREA SYSTEM RELEASE
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