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Category:Report
MONTHYEARNRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023 License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis NRC-21-0031, Request for Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2021-05-17017 May 2021 Request for Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic ML21055A3852021-02-0202 February 2021 3 to Updated Final Safety Analysis Report - GE Document 209A4756, Logic Symbols NRC-19-0067, Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval2019-10-0808 October 2019 Submittal of Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval NRC-19-0018, Submittal of 2018 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2019-04-18018 April 2019 Submittal of 2018 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-18-0054, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)2018-12-14014 December 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) NRC-18-0022, Submittal of 2017 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2018-04-19019 April 2018 Submittal of 2017 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML17305A0382017-10-16016 October 2017 Enclosures 1-6: 10CFR50.59 Evaluation Summary Report, Commitment Management Report, Revisions to Technical Requirements Manual and Technical Specifications Bases NRC-17-0052, High Frequency Seismic Confirmation Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-08-30030 August 2017 High Frequency Seismic Confirmation Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident NRC-17-0026, Submittal of 2016 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2017-04-0606 April 2017 Submittal of 2016 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML16231A4432016-08-30030 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) NRC-16-0026, Submittal of 2015 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2016-04-27027 April 2016 Submittal of 2015 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML16057A7592016-02-25025 February 2016 Comments on Advance Notice of Proposed Rulemaking on Regulatory Improvements for Decommissioning Power Reactors NRC-16-0014, Comments on the Nrc'S Safety Evaluation Report with Open Items Related to the License Renewal2016-02-25025 February 2016 Comments on the Nrc'S Safety Evaluation Report with Open Items Related to the License Renewal NRC-15-0085, Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask NRC-15-0043, Submittal of 2014 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2015-04-28028 April 2015 Submittal of 2014 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-14-0058, 10 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the TN-RAM Cask Due to As-Built Discrepancies Identified by Cask Certificate Holder2014-08-13013 August 2014 10 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the TN-RAM Cask Due to As-Built Discrepancies Identified by Cask Certificate Holder NRC-14-0061, Post Accident Monitoring Report Regarding Inoperable Instrumentation2014-08-0707 August 2014 Post Accident Monitoring Report Regarding Inoperable Instrumentation ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14093A7662014-05-0606 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NRC-14-0030, Submittal of 2013 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2014-04-28028 April 2014 Submittal of 2013 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report ML13317A8942013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Fermi Unit 2, TAC No.: MF0770 NRC-13-0052, CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time2013-09-0909 September 2013 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time NRC-13-0026, Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report2013-07-0909 July 2013 Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report NRC-13-0017, Submittal of 2012 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2013-04-26026 April 2013 Submittal of 2012 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-13-0013, DTE Electric Submittal of Flooding Hazard Reevaluation Report in Response to March 12, 2012 Information Request Regarding Flood Protection Evaluations2013-03-0808 March 2013 DTE Electric Submittal of Flooding Hazard Reevaluation Report in Response to March 12, 2012 Information Request Regarding Flood Protection Evaluations NRC-13-0004, Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization.2013-01-31031 January 2013 Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization. ML13043A6552013-01-31031 January 2013 Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization. NRC-12-0076, Detroit Edison'S Response to March 12, 2012 Information Request Regarding Flood Protection Walkdowns2012-11-26026 November 2012 Detroit Edison'S Response to March 12, 2012 Information Request Regarding Flood Protection Walkdowns ML12341A3642012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-43 Through C-149 ML12341A3632012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Cover Through Appendix C, Page C-42 ML12341A3612012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-336 Through C-426 ML12341A3582012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-247 Through C-335 ML12341A3652012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-150 Through C-246 ML12341A3662012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-427 Through C-529 ML12341A3672012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-530 Through C-628 ML12341A3682012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix C, Page C-629 Through Appendix D, Page D-7 ML12341A3692012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-8 Through Page D-108 ML12341A3702012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-109 Through Page D-211 NRC-12-0075, TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-212 Through End2012-11-20020 November 2012 TMPE-12-0294, Rev. 0, Seismic Walkdown Report, 10 CFR 50.54(f) Section 2.3 Seismic Response, Appendix D, Page D-212 Through End NRC-12-0067, Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases2012-11-0505 November 2012 Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases ML13004A1352012-10-31031 October 2012 Enclosure 5 to NRC-12-0037, NEDO-33785, Rev 0, DTE Energy/Enrico Fermi Power Plant 2 Pressure and Temperature Limits Report Up to 24 and 32 Effective Full-Power Years. ML1203704612012-01-30030 January 2012 Theodore Smith Ltr Revised Final Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi Atomic Power Plant, Unit 1, Newport, Michigan ML1131111732011-10-27027 October 2011 Revised Final Report No. 2, Fermi Independent Confirmatory Survey Summary and Results ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants NRC-11-0036, Enrico Fermi Atomic Power Plant, Unit 1 - License Termination Plan, Revision 42011-06-29029 June 2011 Enrico Fermi Atomic Power Plant, Unit 1 - License Termination Plan, Revision 4 NRC-11-0018, Enrico Fermi Atomic Power Plant, Unit 1 - Fermi 1 Groundwater Site Conceptual Model2011-06-29029 June 2011 Enrico Fermi Atomic Power Plant, Unit 1 - Fermi 1 Groundwater Site Conceptual Model ML1029401782010-10-13013 October 2010 B. Watson Ltr. Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi: Atomic Power Plant, Unit 1, Newport, Michigan ML1011004632010-04-0707 April 2010 Technical Requirements Manual, Vol. 1, Revision 97 NRC-09-0080, Impact of Revised Unsaturated Zone Thickness on Fermi 1 Soil Dcgl Values2009-11-30030 November 2009 Impact of Revised Unsaturated Zone Thickness on Fermi 1 Soil Dcgl Values 2023-03-07
[Table view] Category:Technical
MONTHYEARNRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023 License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis ML21055A3852021-02-0202 February 2021 3 to Updated Final Safety Analysis Report - GE Document 209A4756, Logic Symbols NRC-19-0018, Submittal of 2018 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2019-04-18018 April 2019 Submittal of 2018 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-17-0052, High Frequency Seismic Confirmation Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-08-30030 August 2017 High Frequency Seismic Confirmation Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML13317A8942013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Fermi Unit 2, TAC No.: MF0770 NRC-13-0026, Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report2013-07-0909 July 2013 Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report ML13043A6552013-01-31031 January 2013 Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization. NRC-13-0004, Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization.2013-01-31031 January 2013 Fermi 2, Enclosure 9 to NRC-13-0004, NEDO-33578, Rev. 0, Safety Analysis Report for Fermi Generating Station Unit 2 Thermal Power Optimization. NRC-12-0076, Detroit Edison'S Response to March 12, 2012 Information Request Regarding Flood Protection Walkdowns2012-11-26026 November 2012 Detroit Edison'S Response to March 12, 2012 Information Request Regarding Flood Protection Walkdowns ML13004A1352012-10-31031 October 2012 Enclosure 5 to NRC-12-0037, NEDO-33785, Rev 0, DTE Energy/Enrico Fermi Power Plant 2 Pressure and Temperature Limits Report Up to 24 and 32 Effective Full-Power Years. ML1203704612012-01-30030 January 2012 Theodore Smith Ltr Revised Final Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi Atomic Power Plant, Unit 1, Newport, Michigan ML1131111732011-10-27027 October 2011 Revised Final Report No. 2, Fermi Independent Confirmatory Survey Summary and Results NRC-11-0018, Enrico Fermi Atomic Power Plant, Unit 1 - Fermi 1 Groundwater Site Conceptual Model2011-06-29029 June 2011 Enrico Fermi Atomic Power Plant, Unit 1 - Fermi 1 Groundwater Site Conceptual Model ML1029401782010-10-13013 October 2010 B. Watson Ltr. Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi: Atomic Power Plant, Unit 1, Newport, Michigan ML1011004632010-04-0707 April 2010 Technical Requirements Manual, Vol. 1, Revision 97 NRC-09-0064, Submittal of the Inservice Testing Program Relief Requests for Pumps and Valves - Third Ten-Year Interval2009-11-0303 November 2009 Submittal of the Inservice Testing Program Relief Requests for Pumps and Valves - Third Ten-Year Interval ML0912701872009-04-27027 April 2009 Technical Requirements Manual - Volume I ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0615903572006-05-26026 May 2006 Technical Requirements Manual - Vol. I, Revision 82 ML0512304432005-02-28028 February 2005 GE-NE-0000-0031-6254-R1-NP, DTE Energy Fermi-2 Energy Center Neutron Flux Evaluation. ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 NRC-03-0051, ECCS Cooling Performance Evaluation Model Report2003-05-30030 May 2003 ECCS Cooling Performance Evaluation Model Report NRC-03-0019, Additional Information Regarding Proposed License Amendment for a One - Time Deferral of Primary Containment Integrated Leak Rate Test2003-02-27027 February 2003 Additional Information Regarding Proposed License Amendment for a One - Time Deferral of Primary Containment Integrated Leak Rate Test NRC-87-0137, Submittal of Safety/Relief Valve In-Plant Testing Results1987-09-11011 September 1987 Submittal of Safety/Relief Valve In-Plant Testing Results ML19227A0771984-08-31031 August 1984 Report No. DECO-12-2191, Revision 2, Enrico Fermi Atomic Power Plant, Unit 2, Evaluation of Containment Coatings. 2023-03-07
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22325A1242022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Appendix a, Applicable Regulatory Guides ML22325A1252022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22325A1262022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22325A1272022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 14, Initial Tests and Operation ML22325A1292022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Main Page ML22325A1302022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML22325A1312022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML22325A1322022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 15, Accident Analysis ML22325A1332022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22325A1342022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML22325A1352022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML22325A1362022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Appendix B, Aging Management Programs and Activities ML22325A1382022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML22325A1392022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems ML22325A1422022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics ML22325A1432022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22325A1442022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22325A1452022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML22325A1462022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22325A1472022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, List of Effective Sections, Tables, and Figures ML22325A1542022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Figures (for Public Use) NRC-22-0052, Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 20222022-11-17017 November 2022 Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 2022 ML21055A2202021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2230-04, Rev. E, Logic Diagram Reactor Core Isolation Cooling System ML21055A1742021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2796-01, Rev. F, Remote Shutdown System Division I System Diagram ML21055A2192021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6A721-2411, Fire Protection Evaluation Reactor and Auxiliary Buildings Section D-D ML21055A2182021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2431, Reactor Support Sections & Details ML21055A2172021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2200-4, Rev. D, Logic Diagram Residual Heat Removal System ML21055A2162021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2043, Diagram High Press Coolant Injection System Barometric Cndr (HPCI) Reac Building ML21055A2152021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2313, Reactor & Auxiliary Building Foundation Reinforcing Plan ML21055A2142021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6I721-2196-01, Area Radiation Monitor System Diagram Sht 1 of 2 ML21055A2132021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2090-6, Logic Diagram Nuclear Boiler System Document Control No. B21-00 ML21055A2122021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6A721TS-2002, Onsite Technical Support Center Grade Floor Plan ML21055A2112021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721Y-2003, Rev. G, Condensate Storage Tanks Retaining Barrier Details ML21055A2102021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2004-1, Diagram Condensate System ML21055A2092021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2140-01, Rev. B, Logic Diagram Neutron Monitoring System Part 1 ML21055A2082021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2441, Reactor Drywell Framing Plan El. 646-91516 Unit 2 ML21055A2072021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2200-09, Rev. B, Logic Diagram Residual Heat Removal System ML21055A2062021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4I721-2440-08, Logic Diagram Emergency Equipment Cooling Water System Valve - Auto Close Division II ML21055A2052021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2181-06, Rev. O, Diagram Process Radiation Monitoring Subsystems ML21055A2042021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4I721-2440-07, Logic Diagram Emergency Equipment Cooling Water System Valve - Division II ML21055A2032021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2570-01, Functional Logic Diagram Operation of Power Line Feed & Tie Breakers 4160V Buss 64B & 11EA ML21055A2022021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2230-01, Logic Diagram Reactor Core Isolation Cooling System ML21055A2012021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2513, Side Stream Lrwp System P&ID ML21055A2002021-02-0202 February 2021 3 to Final Safety Analysis Report, Drawing No. 6A721-2406, Fire Protection Evaluation Reactor and Auxiliary Buildings Cable Spreading Area Plan El. 630'-6 ML21055A1992021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6I721-2400-03, Diagram of Samples in Turbine Bldg ML21055A1982021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2035, Diagram High Pressure Coolant Injection System (HPCI) Reactor Building ML21055A1792021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2010-1, Rev. a, Diagram General Service Water System ML21055A1852021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2551, Flow Diagram of Floor Drains in the Radwaste Building ML21055A1842021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6M721-2007, Diagram Circulating Water System ML21055A1832021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2029, Rev. H, Process Diagram Information Tables Sheet 1 Radwaste System 2022-11-17
[Table view] |
Text
Enrico Fermi A.P.P. Unit 2 PIS No. -
Location J/{ 10 P.O. Installation B/M -- DECo. File No. - ?O Transmittal Date / 4 Vendor q 5/ -
En ineering Quality Assurance Dir.
Accepted As Noted Not Accepted Accepted As Noted Not Accepted DOCI 0
M System Engineer E 5i r L IC P Proj. Director Operations QI Technical Director Accepted As Noted Not Accepted
/-7 V ARMS INDEXED DTC:D
1 GENERA L ELECTRIC DOCUMENT NO. 209A4756 REV.
NUCLEAR ENERGY DIVISION ATOMIC POWER EQUIPMENT DEPARTMENT APPLICATION ALL PROJECTS Saq. Jose, California 642.-1030
©SPECIFICATION GDRAWING ENRICO FERMI 2 TYPE MPL ITEM NO. ..- /
PART OR GROUP NO.
DOCUMENT TITLE LOGIC SYMBOLS REVISIONS 1 a,?g gl7og l{
GENERAL CHANGES TO SH.1-SH.12
& 14. ADDED SH.16* SH.6, FIG.7 WAS MADE "I NACTI VE". FIG.16&17 SH.10 & 11, WAS MADE "INACTIVE FOR NEW DESIGN" SHOWN ON SH.1 FIG.20. PER ECN NE28185.
ra g / 0/jo 209 A 4756 ED CONT ON SHEET 1 SH N. . 1 REVISION STATUS SHEET N4ED 805 (3-69).-
GENERAL@ ELECTRIC 209 A 4756 CONT ON SHEET SH NO.
REV TITLE 2 NO.
209 A 4756 LOGIC SYMBOLS 2 SH NO. 1 FIRST MADE FOR
+ CONT ON SHEET REVISIONS FIG. 1 THIS BLOCK IS THE COMMAND SWITCHING OR PRIMARY ACTUATING FUNCTION. THIS BLOCK CAN REPRESENT A SWITCH, VALVE PROBE TIMER,0R TRIP CIRCUIT. THIS BLOCK IS NORMALLY THE STARTING POINT OF A FUNCTIONAL SEQUENCE WITH AN OUTPUT ONLY, BUT CAN HAVE'INPUT AND AUX. INPUT DEPENDING ON THE TYPE OF DEVICE. THE SAME DEVICE MAY HAVE A NUMBER OF OUTPUTS, BUT EACH FUNCTIONAL SEQUENCE INITIATED SHALL BE SHOWN BY AN INDIVIDUAL BLOCK SHOWING THE SAME IDFNTIFICATION NUMBER & CROSS REF. (SEE SH.3).
ELECTRICAL POWER IS AVAILABLE BUT THE INPUT IS NORMALLY NOT SHOWN EXCEPT IN CASES SUCH AS AUXILL POWER. BATTERY POWER STANDBY POWER OR POWER FROM COMMAND SWITCHES "UPSTREAM" OF THIS BLOCK. INPUT (IF NOT THE STARTING POINT)
AUX INITIATING DEVICE INPUT ACTtIATED BY CONDI T ION SIGNAL DESCRIBED WITHIN THE BLOCK.
LOCATION SEE SH.2 & SH.3 IDENTIFICATION OR MPL NO. OUTPUT
+ SIGNAL IS PRESENT WHEN CONDITION AS DESCRIBED WITHIN THE BLOCK, IS MET4
+(
PRINTS TO MADE BY Y~t1) q /20 /g APPR VALS A AP'ED DI0 OR 2 09r I77r SUED DP SE S LOCATION CONT ON SHEET 2 SH NO.
N
PRINTED IN U.S.A.
GENERAL ELECTRIC 2' REV 0 1TITLE CONT ON SHEET 3 SH NO. 2 209 A 4756 LOGIC SYMBOLS CONT ON SHEET 3 SH NO. 2 FIRST MADE FOR REVISIONS F I G. 2 INPUT PERMISSIVE DEVICE LOCATION NUMBER AUX I NPUT OR SIGNAL LP = LOCAL PANEL CR = CONTROL ROOM LOCAL = MOUNTED LOCALLY IDENTIFI CATION OR SH.& ZONE = SEE SH.3 MPL_ NO. - /24 = SEE NOTE.
SIGNAL PRESENT OUTPUT WHEN PERMISSIVE O THIS BLOCK DEFINES A PERMISSIVE FUNCTION WHICH MUST BE SATISFIED TO PERMI T THE SIGNAL FLOW TO PASS TO THE NEXT BLOCK. THI S BLOCK HAS INCOMING, OUTGOING,AND MAY HAVE AUXILIARY SIGNALS. THE OUTPUT FROM THIS PERMISSIVE MAY BE SEALED IN.
NOTE:
THE WORD MAY BE USED IF THE LOCATION IS UNKNOWN BUT THE CORRECT LOCATION SHALL BE NOTED ON A FUTURE REVISION.
+P
+ PRINTS TO MADE BY/APPROVLS l JS DE DEPT
. 209 20 A 4756 E LOCATtON CONT ON SHEET 3 SH NO. 2
-- . CODE[ENT NO.
F -W 2-66 )
PRINTED IN U.S.A.~
GENERAL ELECTRIC 209 A 4756 CONT ON SHEET 4 SH NO.
TITLE RE 209 A 4756 LOGIC SYMBOLS SH No. 3 FIRST MADE FOR CONT ON SHEET 4
+ MORE THAN ONE REVISIONS OR A PRIMARY FUNCTION IS SHOWN IN IF A PERMISSIVE TO THE PARENT PLACE ON DRAWINGS, PROVIDE A CROSS REFERENCE LOCATION OF OTHER IN THE FUNCTION. (FORMALLY AN "X" WAS SHOWN INDICATING THAT THEIR BLOCK WERE'AN SWITCH HANDLE POSITION, BUT A DIFFERENT ASSEMBLY, INTRICATE PART OF THE NUMBERED SWITCH IN LOCATION IS INACTIVE THE "X" POSITION OF THE SWITCH HANDLE.
FOR NEW DESIGN.)
FIG. 2A SHEET 1 SHEET 2
+ EG.
r LOCA L FOR F014 SH2-H5 FOR F014-J5 FOR F014 FOR F014 PARENT SH2-K7 A3 (THIS MPL ITEM SH1-J5 SH1-J5 FUNCTION)
NEED NOT BE NOTED IN THIS CASE THE SPACE IF ITS FUNCTION IS IS LEFT BLANK. (TYPICAL)
OBVIOUSLY APPARENT.)
SERVED ADJACENT TO THE SHOW MPL ITEM NUMBER OF THE VALVE OR EQUIPMENT EXAMPLE.
PERMISSIVE OR PRIMARY FUNCTION. SEE FiG. 3 INPUT PERMISSIVE IF GENERAL CONDITION AS DESCRIBED IS MET.
REF. SH & ZONE OUTPUT THIS BLOCK IS A PERMISSIVE CONDITION.
AND NOT IDENTIFIED WITH WHERE THE PERMISSIVE IS A GENERAL CONDITION SHOWN. IT ONLY HAS AN ONLY IS A SINGLE DEVICE, THE OUTER ENCLOSURE PRINTS TO
+ INPUT AND OUTPUT.
MADE BY J.GARCIA 8- Z0-8 PPROVALS APED DIVOR 209 A 4756 UED o GSAN JOSE, CAL. LOCATION CONT ON SHEET 4 SH NO.
CODE 3
IDENT NO.
4.-DET NO PR03D I. ,A PRINTED IN U.S.A.
O/ G.
DEG. P
TIT LE CONT ONSHElT SH N0. 4j RNEV 209 A 4756 LOGIC SYMBOLS CONT ON SHEET 5 SH No. 4 FIRST MADE FOR REVISIONS INPUT CONTROLLED DEVICE OR MECHANISM IDENTIFICATION LOCATION SEE SHEETS OR MPL NO. 2 & 3.
TYP. OF MECH. OUTPUT OR MECH. LINKAGE THIS BLOCK IS A FINAL DEVICE. IT CAN BE A RELAY, VALVE, ELECTRO-MECH. SW., ETC. NORMALLY IT HAS ONLY INPUTS, BUT CAN HAVE MECH.
OUTPUTS OR POSITION SWITCH OUTPUTS.
FIG. 5 RESET SEAL-IN
} {
DEVICE RMS RMS 0 -
AUXI DEVICE LOCATION SEE FORMALLY THIS "BAR" WAS LOCATION SEE SHEETS 2 & 3 NOT SHOWN. THE PLAIN SHEETS 2 & 3 OR OUTLINE IS INACTIVE FOR ANY FINAL DEVICE NEW DESIGN. OUTPUT THIS IS A SEAL-IN WITH A MANUAL RESET DEVICE. THE FUNCTION OF THE SEAL-IN IS TO LATCH IN A SIGNAL AND TO CONTINUE THAT SIGNAL UNTIL IMPLIES
+ MANUALLY RESET. A SEAL-IN SHOWN WITHOUT A RESET DEVICE THAT THE RESET DEVICE"'IS PART OF, AND LOCATED ON THE NEAREST VALVE OR CONTACTOR AND IS AUTOMATICALLY RESET BY BREAKING THE SIGNAL DOWNSTREAM OF THE SEAL-IN SIGNAL. IN ALL OTHER CASES THE RESET DEVICE SHALL BE SHOWN IN CONJUNCTION WITH THE SEAL-IN.
PRINTS TO NADEBYRCI - 8 PPROVALS _ A P_ D DIV OR 209 A 4756 IS ED e //, a GHH SAN JOS E, CAL. LOCATION CONT ON SHEET SH NO.
-CODE (DENT NO.
PRNTED N SA
' l I DPL.
+~R EVISIONSj EXAMPLES OF TYPICAL SEAL-IN BLOCKS.
FIG. 5 (A). 3-POSITION SPRING RETURN TO NORMAL CONTROL SW IN START F TYICALSEA EXAMLES POSITSON SEA L-CKN TYP. SIGNALS IN THl S CASE, ALL SIGNALS AT THIS POINT WOULD BE SEALED IN.
FIG. 5 (B) 3-POSITION SPRING RETURN TO NORMAL CONTROL SW IN START POSITION 72 T CR RMS CR SEAL IN TYP. SIG. 11111 cv ~
KKI E- COTO 96)
SW3W o sa ANJSECL.SOCTONCNTOISETONH COEDN O
O IN THIS CASE, ONLY THE CONTROL SW SIGNAL WOULD BE SEALED IN.
PRINTS TO MAD /G ~ CA ~ 8 APPROVALS _A _PE D_____--"P; 209 A 4756 C D IN PRNTED S A.
SPL
GENERAL ELECTRIC 209 A 4756 REV TITLE CO ON SHEET 7 SH NO. 6 LOGIC SYMBOLS 209 A 4756 CONT ON SHEET 7 SH NO. 6 FIRST MADE FOR REVISIONS FIG. 6 INPUT INPUT
+i EXAMPLE,DESCR I PTI ON OF SW GEAR EQUIP.(SEE NOTE)
THIS BLOCK IS A FINAL DEVICE USED TO REPRESENT MOTOR STARTERS, CIRCUIT BREAKERS, ETC. IT HAS ONLY INPUT SIGNALS. THE INPUT TO THE RIGHT CAUSES AN OPPOSED ACTION TO THE INPUT ON THE LEFT, SUCH AS LEFT-OPEN: RIGHT-CLOSE.
NOTE TO FIG. 6. A FINAL DEVICE MAY HAVE MORE THAN ONE INPUT.
EACH OF THESE INPUTS CAN INITIATE THE BLOCK. THE BLOCK CAN HAVE ELECTRICAL INPUTS TO INDICATING DEVICES. SWITCHGEAR DESCRIPTIONS ARE FOUND IN ANSI SPEC. C37.2.
FlG. 7 ELECTRICAL INPUT SIGNAL (OPTIONAL)
TRIP V' RESET EXAMPLE, GENERATOR L - ELAY OUTPUT OUTPUT OUTPUT THIS BLOCK REPRESENTS AN INTERMEDIATE DEVICE, SUCH AS A LOCK-OUT RELAY. THE OPERATION OF THi S DEVICE INHIBITS, PERMITS, OR CAUSES
+} THE ACTUATION OF FINAL DEVICES. PRINTS TO MADE BY. GARCIA S J'.d.JG1-------------------DEPT.
APPROVALS APED DIVOR 209 A 4756 GH H SAN JOSECAL. LOCATION CONT ON SHEET 7 SH NO. 6 CODE IDENT NO.
' /
-803mWN (9-66)
PRINTED IN U.5.A.
j < : - AP. L
GENERAL & ELECTRIC 209 A 4756 CONT ON SHEET 9 SH NO.
REV TITLE 7 NO. -
LOGIC SYMBOLS 209 A 4756 CONT ON SHEET , SH NO. 7 FIRST MADE FOR REVISIONS FIG.
+ DEVICE TITLE OR CON-TROLLED CONDITION.
INPUT OR OUTPUT INPUT OR OUTPUT AUX AUX INPUT INPUT IDENTIFICATION LOCATION OR MPL NO. SEE SHEET 2 & 3 INPUT OR OUTPUT INPUT OR OUTPUT THI S BLOCK IS A PERMISSIVE OPERATED BY DEVICES SUCH AS VALVE OR PUMP SWITCHGEAR DESIGNATED IN THE INNER BLOCK. THIS COND. OR DEVICE EFFECTS THE OPERATION F, THE FINAL DEVICE. IT HAS ELECT.
INPUTS. MECH INPUTS, AUX. INPUTS (MECH OR ELEC), AND MECH OR ELECT OUTPUTS. THIS DEV1CE IS NORMALLY A VALVE. THIS IS ALSO
+ USED FOR OTHER INPUT/OUTPUT POWER SOURCES SUCH AS AIP OR HYDRAULIC.
A SOLENOID PILOT VALVE FOR AN AIR OPERATED VALVE IS AN EXAMPLE OF THIS TYPE DEVICE (SEE FIG. 16) WHEN THE 2 SIDE BLOCKS ARE THE CONTROLLING BLOCKS THEY HAVE AUX. INPUT SIGNALS.
+ PRINTS TO MADEBY APPROVALS . L DIVOR M .GARC IA & -- 0-0 oes B "' __A _PEED _ _ ___-DEPT. 209 A 4756 E IS ED anc7 >H H - SAN JOSE CA. LOCATION CONT ON SHEET R SH NO. 7 ODE (DENT NO.
I 803-W (^6 P INTER IN U.S.A.
GENERAL E ELECTRIC 209 A 75 RNEV 0/ TITLE CONTON SHEET 9 SH NO. 8 209 A 4756 LOGIC SYMBOLS CONT ON SHEET 9 SH NO. 8 FIRST MADE FOR FG REVISIONS F IG. 9 X
LOCATION LOCAL CR ANNUNCIATOR LEVEL(S) P A = ALARM LOW
+ AL/L= ALARM LOW-LOW AH = ALARM HIGH AH/H= ALARM HIGH-HIGH IDENTI FI CATI ON OR MPL NO. LO C A T ION SEE SHEET 23 THIS BLOCK IS A PRIMARY FUNCTION FOR ANNUNCIATORS.
FIG. 10 LOCATION RED LOCAL / R BLE CR COLOR B = TE LP OF LAMP A = AMBER G = GREEN
+ IDENTIFICATION OR MPL NO. LOCATION SEE SHEET 23 THI S RI OCK >I A PR IMARY FUNCTION FOR INO. I GHTS.
PRINTS TO MADEBY APPRQVALS APED DIEO 209 A 4756 1 ED r /- A SA%,4 5S. LOCATION CONTON SHEET 9 SHNO.
DENT NO.
9WP )CODE PRINTED IN U S A.O
GENERALC() ELECTRIC 209 A 47%5 CONTOff SHEET 1 SH NO. 9 NO I TITLE 209 A 4756 LOGIC SYMBOLS
+/- CONT ON SHEET 1 SH NO. 9 FIRST MADE FOR REVISIONS FIG. 11 THI S LlWNE REPRESENTS AN ELEC FLOW SIGNAL. THIS LINE MAY ACTUATE A FINAL DEVICE AND MAY BE USED TO REPRESENT ACTUATION OF A PERMISSIVE BLOCK.
+
FIG. 12 THIS LINE REPRESENTS AN AUXILIARY SIGNAL SOURCE SUCH AS AIR OR HYDRAULIC, 'AND IS NOT ELECTRICAL.
FIG. 13 THIS LINE REPRESENTS MECHANICAL OUTPUTS AND/OR MECHANICAL LINKAGE.
FIG. 14 START THIS SYMBOL REPRESENTS THE START OF THE PRIMARY INITIATING SIGNAL.
+ FIG. 15 x LETTER DESIGNATION SHEET NO. X )( ZONE OR REF. DWG.
THIS SYMBOL REPRESENTS A MATCH CIRCLE. THE LETTER DESIGNATION ON ONE DWG, MUST MATCH THE LETTER ON THE INTERFACING DWG.
PRINTS TO 2 A 4 GAEIA 512014p APPROV ALS MA DE BY, DV .
41 E DIV OR
-- DEPT. 209 A 4756 UE a :r a
- JosE LOCATION CONT ON SHEET 10 SH NO. 9 CODE (DENT NO.
FB03-WF (2-66) G PRINTED IN U.S. A QPL
GENERAL, ELECTRIC 209 A 4756 CCNT ON SHEET 1 SH NO. 1 TITLE 209 A 4756 LOGIC SYMBOLS CONT ON SHEET 11 SH NO. 10 FIRST MADE FOR _ '._
+ REVISIONS FIG. 16 CONTROL SW.
IN "OPEN" POSITION
+/- RPIS CR.
AIR SUPPLYYXAS DE-ENERGIZE PERMISSI VE SOLENOID PERMISSIVE WHEN SOLENOID PILOT WHEN SOLENOID IS VALVE IS ENERGIZED DE-ENERGIZED SOL.
PILOT LOCAL
+ (CLOSED, FAILS OPEN) SOLENOID DE-ENERGIZED VALVE OPENS EXAMPLE AO F054 LOCAL EXAMPLE OF MPL NO.
TYPICAL A.O. VALVE EXAMPLE
+ PRINTS TO GE RBYCJ 8 - W J. MAGARClA 8-S2-m PPROVALS A P E D DIV OR MADE BY
__-A_--_-___- __D'DE . 209 A 4756 I ED 2 - G14 SA N JOSE, CA. LOCATION CONT ON SHEET 11 SH NO. 1 0 I /ODE r (DENT NO.
F 803-WF (9.66)
PRINTED IN U.S.A.
I ? aPLrf
GENERAL6 ELECTRIC 29A4 CUNT ON SHEET SH NO.
TITLE REVg 209 A 4756 LOGIC SYMBOLS CONT ON SHEET 112 SH NO. 11 FIRST MADE FOR REVISIONS FIG. 17 CONTROL SW.
lN TEST POSI TION PB CR ACTUATOR CONTROL LOGIC LI EXHAUST AIR. SUPPLY EXHAUST OPEN SOLEl CLOSE C01LV PIL ALVE COL SOL. P C LOCAL
\ CR / *CR CR/
R G OP NEUTRAL CLOSE
/ \ VALVE ACTUATOR /r \.,!
\CR/ VALVEC R OPEN CLOSE G AO F054 LOCAL
+ ROCKWELL TYPE, TESTABLE CHECK VALVE PRINTS TO APPROVALS DN OR MADE BY UE9 - AP- LO-ON CEPT. ON A SHNO UED
.93W (-6 9E g ,A,"y^ " Z N jas LOCATION CONT ON SHEET 12 SH NO. 11 CODE DENT NO.
PRINTED IN U.S.A.
HI GH TEM o INITIATING DEVICE ALARMA w
Z0 LOCATI ON C CONTROL SW.
IN "START" ---
POSITION VALVE MO FOO1 VALVE MO F004 PUMP COOLING NOT FULLY NOT FULLY WATER TEMP 71 OPEN OPEN HIGH RMS CR ON ON 1- LIM. SW VALVE LIM. SW. VALVE TIS B-4 N002 LOCAL IDENTI FI CATION PE RMISSIVE WHEN MPL NO. LOCATION VALVE MO FOO1
~ ~_________
F FLYOPEN oy o PUMP -
SW ON SIGNAL PRESENT DISCHARGE ;o
~IM I MVALVE WHEN ABOVE CONDITION FLOW LOW PERMISSIVE EXISTS S I
4 ZDEVICE FSL LOCAL ITrnPUMP COOLING CONTROL SW rm PERMISSIVE WHEN WATER TEMP. IN "STOP" .'
nl VALVE MO FO04 HIGH POSITION FULLY OPEN CONTROL SW, 2 ONTNOT PERMISSIVE I RMS A-1 IN "START" POS.
LIM. SW VLVE N2 LOCAL a uR G RMS A-l r R> G START STOP-AIR CIRCUIT BREAKER (52) o r., ?FIG 1 8U
_z WORK' WITH FIGURE '"A
GENERALS ELECTRIC 209 A 4756 RVTITLE CONT ON SHEET 14 SH NO. a.
209 A 4756 LOGIC SYMBOLS 1 CONT ON SHEET 14 SH NO. 1 3 FIRST MADE FOR T
REVISIONS 2:j 0
/ 0 0Lur I -Q g O
.1 (1)2:
0 -
f-XS U)0d ow 0 0 0 0z:
IL U ~LU
- a. or 0
+ ~L 0' p 0
+
MADE B" '~' ' 'PRINTS TO APPROVALSAPDDVO 0 SE -ET. Q75
'SA 005 LOCATION CONTON SHEET 14 SH NO. 13 SOS -WF (9-86)
PRINTED IN U.S.A. v I CODE IDENT NO.
/e
__v 2
GENERALS ELECTRIC 209 A 37 6 REVN TITLE CONTN SHEET i'3) SHNO. 14 209 A 4756 LOGIC SYMBOLS
+ CONT ON SHEET 15 SH NO. 14 FIRST MADE FOR CR REVISIONS FIG, 19 AL WORK WITH FIG. 19A VALVE CONTROL LOW PRESS HIGH PRESS SWITCH IN UPSTREAM OF DOWN STREAM OF "OPEN" VALVE AO F033 VALVE AO F033
+ POSITION RMC CR NE LOCAL LOCAL
_____N____NO W E/P LOW PRESS HIGH PRESS AIR CONVERTER UPSTREAM -OF DOWN STREAM OF VALVE AO F033 VALVE AO F033 PRES EP PE- p LOCAL K001 LOCAL N013 LOCAL EXHAUST- --
PERMISSIVE DE-ENERGIZE PERMISSIVE WHEN PILOT SOLENOID WHEN PILOT ENERGI ZED PI LOT VALVE DE- ENERGI ZED F028 TLOCAL SOLENOID DE-ENERGIZED VALVE CLOSES AO F033 LOCAL BLEED-OFF FLOW CONTROL VALVE AD F033 F NCTIONAL CONTROL DIAGRAM PRINTS TO MADE B APPROVALS APED DIVDO J7t.I/ ' ",6f ------- AJ DEPT.R 209 A 4756 d / ff,7 VI" 0V LOCATION CONT ON SHEET 15 SH NO. 1L F -803-WF (9-66)
I t CODE (DENT NO.
PRINTED IN U.S.A.
6
__~~~Ae ITT .>
GENERAL@ ELECTRIC 209 A 4 6 REV 1 TITLE CONT ON SHEET 16 SH NO. 15 209 A 4756 LOGIC SYMBOLS CONT ON SHEET 16 SH NO. 15 FIRST MADE FOR REVISIONS N014 _ - - - - -
MA IN FLOW F033 013 F028 ND eA I CR
-- E/P K001 NOTES: 1. AUX. RELAYS &
DEVICES ARE NOT SHOWN ON FCD TYPICAL EXAMPLE OF P&ID FIG. 19A FOR LOGIC SEE SH 14
+ PRINTS TO MADEBY R /i1 jAPPROVALS A.PED IVO APPROVALS--VDEOR. 209 A 475 6 IS ED i e7 IAIN V LOCATION CONT ON SHEET 16 SH NO. 15 iCODE IDENT NO.
P O3.WF (9.66)
PRINTED IN U.S.A. IA
GENERAL ELECTRIC 209 A 4756 E / f TITLE CONTON SHEET F SH NO. 16 209 A 4756 LOGIC SYMBOLS CONT ON SHEET F SH NO. 16 FIRST MADE FOR REVISIONS THE FOLLOWING FIG. REPLACES FIG. 16 & 17.
THIS FIG. IS FOR A TYPICAL TESTABLE CHECK VALVE.
FIG.20
+/-I CONTROL SW IN POSITION OF SW POSITION VARIES TYPE OF SW LOCATION:
"RMS CR, LP, LOCAL COMMAND SIGNAL FOR ANY LOGIC SEE VALVE PURCHASE SPEC.
FOR OPERATION OF VALVE SEE ENGR DESIGN SPEC.
L _.- -- _.--_-_.J TESTABLE CHECK VALVE AO REASON FOR THE ABOVE CHANGE IS TO HAVE ONE STD. LOGIC FOR ALL TESTABLE CHECK VALVES AO REGARDLESS OF MANUFACTURE.
PRINTS TO NA yY/ AP0OALS P E DEPT. 209 A 4756 E '1 SAN JOSE CA L LOCATION CONT ON SHEET F SH NO. 1o
.8c "S Lo CODE IDENTNO.
RINTED IN U.S.A. j I f, P I ITI PL.