ML110871632: Difference between revisions
From kanterella
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| (2 intermediate revisions by the same user not shown) | |||
| Line 2: | Line 2: | ||
| number = ML110871632 | | number = ML110871632 | ||
| issue date = 03/15/2011 | | issue date = 03/15/2011 | ||
| title = | | title = Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-604, Underground Barrier Trench B, STA 3 + 00 | ||
| author name = | | author name = | ||
| author affiliation = Tennessee Valley Authority | | author affiliation = Tennessee Valley Authority | ||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:DENS/TY | {{#Wiki_filter:DENS/TY TEST 2'057 TEST NUMBER EHS/TY | ||
(/03.@%) % MAX/MUM DRY Of? % | |||
ASW D696 WATER TABLE PO TENT/AL. FAILURE PLANE | |||
-- 1075 CROSHEB STONE AND 100 %PD&~Ax H L L | |||
---- 1075 AND 1032 | |||
- CRUSHED S m N E 10 32 CRUSHED STONE AND ,I00%PDMAXFILL 1 | |||
-/OOPo AND 95%QMAX / | |||
t I | |||
ADDED BY AMENDMENT 5 9 I}} | |||
Latest revision as of 04:39, 11 March 2020
| ML110871632 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 03/15/2011 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML110871632 (1) | |
Similar Documents at Watts Bar | |
|---|---|
Category:Final Safety Analysis Report (FSAR)
MONTHYEARWBL-23-053, Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version2023-11-0808 November 2023
[Table view]Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version ML23312A1462023-11-0808 November 2023 Updated Final Safety Analysis Report (UFSAR) Amendment 5 - Table of Contents ML20323A3182020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Table of Contents WBL-20-047, Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)2020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted) ML20323A3082020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML20323A3142020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Table of Contents to Sec 3.7 ML20323A3192020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML20323A3172020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Division of Responsibility (Dor), Abbreviations ML20323A3112020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML20323A3222020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML21123A2262020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Sections 3.8 to 3.12 (Redacted) ML20323A3152020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20323A3032020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary System ML20323A3052020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems ML20323A3002020-10-29029 October 2020 Submittal of Amendment 3 to Updated Final Safety Analysis Report ML20323A3202020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System ML21123A2252020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Table of Contents to Sec 2.4 (Redacted) ML20323A3012020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML20323A3092020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML20323A3162020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML20323A3102020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Sec 2.5, Geology, Seismology, and Geotechnical Engineering Summary of Foundation Conditions ML20323A3062020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML20323A3122020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML20142A3892020-05-21021 May 2020 Wbnp PSAR, Chapter 12, Conduct of Operations L-19-022, Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted2019-03-18018 March 2019 Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted ML19060A1472019-02-19019 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 2 of 5 ML19060A1762019-02-18018 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 3 of 5 ML19060A1822019-02-18018 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 5 of 5 ML19039A1042019-02-0808 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 1 of 5 ML19060A1492019-02-0808 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 4 of 5 ML17334A1602017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 13, Conduct of Operations ML17334A1732017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 8, Electric Power (Redacted) ML17334A1622017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 14, Initial Test Program ML17334A1692017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 4, Reactor ML17334A1562017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (Redacted) ML17334A1722017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls ML17334A1582017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 11, Radioactive Waste Management ML17334A1592017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 12, Radiation Protection (Redacted) ML17334A1652017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 17, Quality Assurance ML17334A1702017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System ML17334A1632017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 15, Accident Analyses ML17334A1572017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems ML17334A1642017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 16, Technical Specifications ML15279A3042015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 1 of 2 ML15279A3072015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-556 ML15279A3182015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-579 ML15279A3192015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-583 ML15279A3082015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-571. Sheet 1 of 4 ML15279A3052015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 2 of 2 ML15279A3252015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-597 2023-11-08 Category:Graphics incl Charts and Tables MONTHYEARWBL-23-013, 10 CFR 50.46 Annual Report for 20222023-03-29029 March 2023
[Table view]10 CFR 50.46 Annual Report for 2022 WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted CNL-20-058, Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27)2020-08-27027 August 2020 Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27) ML18022A3642018-01-19019 January 2018 Survey Codes_Twra CNL-17-141, Tennessee Valley Authority - Anchor Darling Double Disc Gate Valve Information and Status2017-12-28028 December 2017 Tennessee Valley Authority - Anchor Darling Double Disc Gate Valve Information and Status ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports CNL-15-213, Compliance with Three Mile Island (TMI) Action Plan Requirements for an Operating License2015-10-0707 October 2015 Compliance with Three Mile Island (TMI) Action Plan Requirements for an Operating License ML15238B6672015-09-0303 September 2015 MSFHI Public Table ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T ML13255A3152013-08-14014 August 2013 Final Safety Analysis Report (Fsar), Amendment 110, Table 6.2.4-1 Containment Penetrations and Barriers - Page 1 of 64 - Page 64 of 64 ML13175A1352013-03-0505 March 2013 2-PTI-092-03, Revision 0, Nuclear Instrumentation Source Range Noise Checks During Hot Functional Testing. ML13175A1362012-11-0808 November 2012 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification. ML13175A1342012-11-0101 November 2012 2-PTI-082-02, Revision 0, Rod Control - Non Hft. ML13175A1332012-10-22022 October 2012 2-PTI-085-01, Revision 0, Rod Control Functional Test. ML12157A3042012-07-24024 July 2012 SECY-12-0103 - Enclosure 1 - Statistical Status Report - Sixth Report on the Status of Reactivation of Construction and Licensing for Watts Bar Nuclear Plant, Unit 2 ML12157A4612012-07-24024 July 2012 SECY-12-0103 - Enclosure 2 - Future Activities for Watts Bar Unit 2, Reactivation Project Plan ML11203A0052011-07-21021 July 2011 SECY-11-0102 - Enclosure 2 - Chart of Future Activities - Fourth Report on Status of Reactivation of Construction and Licensing for Watts Bar Nuclear Plant Unit 2 ML11178A1852011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 15.0, Accident Analyses, Through Table 15A-2 Accident Atmospheric Dilution Factors (sec/m3) ML11178A1822011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Content, Section 12.0, Radiation Protection, Through Appendix 12A - Radiation Protection Features for the Tritium Production Program ML11178A1842011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 14.0, Initial Test Program Through Figures 14.2-2 Power Ascension Test Schedule ML11178A1812011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 11.0, Through Table 11A-2 Tritium Release for 1972 from Westinghouse Designed Operating Reactors ML11178A1792011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Section 9.4 Air Conditioning, Heating, Cooling and Ventilation Systems Through Figure 9.5-30 Diesel Exhaust System Piping Schematic ML11178A1782011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 9.0 Auxiliary Systems, Through Figure 9.3-21 Watts Bar Nuclear Plant Boric Acid Tank Limits ML11178A1752011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Section 6.3 Emergency Core Cooling System Through 6.9 Motor-Operated Valve (MOV) Programs ML11178A1772011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 8.0 Electric Power, Through Page 8E-11 ML11178A1722011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 4.0 Reactor, Through Figure 4.4-6, Location of Incore Instrumentation System Fixed Incore Detector Core Exit Thermocouples and Iitas (Unit 2) ML11178A1732011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 5.0, Reactor Coolant System, Through Instrumentation Application 5.6-7 ML11132A1182011-05-0505 May 2011 Bellefonte, Units 1 and 2 - Proposed Regulatory Framework for the Possible Completion of Construction Activities ML1108716282011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-596, Underground Barrier Trench a, STA 5 + 78 ML1108716292011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-597, Underground Barrier Trench a, STA 7 + 78 ML1108716302011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-602 RO, Underground Barrier Trench B, STA 1 + 00 ML1108716312011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-603, Underground Barrier Trench B, STA 2 + 50 ML1108716322011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-604, Underground Barrier Trench B, STA 3 + 00 ML1108716652011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-605, Underground Barrier Trench B, STA 4 + 50 ML12257A0682011-01-0101 January 2011 Tennessee Valley Authority 2012 Watts Bar - Office of Environmental and Research Recreation Area Matrix ML11221A3222010-12-17017 December 2010 Amendment 102 to Final Safety Analysis Report (Fsar), Table 6.2.4-1, Page 1 of 69 - 64 of 69 ML1019703112010-07-16016 July 2010 Request for Additional Information Regarding Fire Protection Program ML1016005052010-06-0303 June 2010 Chapter 14 - Question 4 - Supporting Information ML1016104562010-05-27027 May 2010 Amendment 99 to Final Safety Analysis Report (Fsar), Containment Penetrations and Barriers-Table 6.2.4-1. Pages 1 Through 64 ML1013705382010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 1 of 4 ML1013705392010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 2 of 4 ML1013705372010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-281, Category 1 Conduit Banks Section F-F, Sheet 1 ML1013705342010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-71, Graphic Log & Elastic Moduli Sta. L-61+00 ML1013705312010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-281, Category I Conduit Banks Section F-F, Sheet 2 ML1006302352010-02-25025 February 2010 Yard Holding Pond Wsel Graph Overflow for 2001 ML0935705552009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-281, Category 1 Conduit Banks, Section F-F Sheet 1 of 2 ML0935705562009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-281, Category 1 Conduit Banks, Section F-F, Sheet 1 of 2 ML0935705572009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 1 of 4 ML0935705602009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-71, Graphic Log and Elastic Moduli Sta. L-61+00 ML0935705612009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-222, Borrow Investigation 2023-03-29 |
Text
DENS/TY TEST 2'057 TEST NUMBER EHS/TY
(/03.@%) % MAX/MUM DRY Of? %
ASW D696 WATER TABLE PO TENT/AL. FAILURE PLANE
-- 1075 CROSHEB STONE AND 100 %PD&~Ax H L L
1075 AND 1032
- CRUSHED S m N E 10 32 CRUSHED STONE AND ,I00%PDMAXFILL 1
-/OOPo AND 95%QMAX /
t I
ADDED BY AMENDMENT 5 9 I
Retrieved from "https://kanterella.com/w/index.php?title=ML110871632&oldid=2551441"