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| {{#Wiki_filter:SECTION 12 | | {{#Wiki_filter:SECTION 12 |
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| Revision 26USAR 12.1MONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 1 of 1SECTION 12PLANT STRUCTURES AND SHIELDINGI/kab12.1Summary DescriptionThe plant buildings and structures consist of the reactor building, turbine building,radwaste building, administration building, intake structure, off-gas stack, off-gasbuilding, recombiner building, emergency filtration train building and other auxiliary structures. The design requirements contained in this section apply to the plant structures and equipment which are required to prevent the significant release of radioactivity, which are required for safe shutdown or which are required for powergeneration. Plant structures and equipment not discussed in this section aredesigned in accordance with building codes valid at the Monticello Site. The arrangement of the main plant structures on the site is shown in Drawing ND-95209, Section 15.Drawings NF-36054 through NF-36063, Section 15, show the generalarrangement of the reactor building, turbine building, office and control building.01156713 SECTION 1212.212.2.1 | | Revision 26 USAR 12.1MONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 1 of 1SECTION 12PLANT STRUCTURES AND SHIELDING I/kab12.1Summary Description The plant buildings and structures consist of the reactor building, turbine building,radwaste building, administration building, intake structure, off-gas stack, off-gas building, recombiner building, emergency filtration train building and other auxiliary |
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| | structures. The design requirements contained in this section apply to the plant |
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| | structures and equipment which are required to prevent the significant release of radioactivity, which are required for safe shutdown or which are required for power generation. Plant structures and equipment not discussed in this section are designed in accordance with building codes valid at the Monticello Site. The |
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| | arrangement of the main plant structures on the site is shown in Drawing ND-95209, Section 15.Drawings NF-36054 through NF-36063, Section 15, show the generalarrangement of the reactor building, turbine building, office and control building.01156713 SECTION 1212.212.2.1 |
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| 12.2.2 | | 12.2.2 |
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| SECTION 1212.5 | | SECTION 1212.5 |
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| Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 1 of 4SECTION 12PLANT STRUCTURES AND SHIELDINGI/jmrFIGURESFOR ADMINISTRATIVE USE ONLYResp Supv:CNSTPAssoc Ref:SR:2yrsNFreq:USAR-MANARMS:USAR-12.FIGURESDoc Type:Admin Initials:Date:9703 Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 2 of 4I/jmrFigure 12.2-9 Comparison of Actual Earth Quake Spectrum to Recommended Spectrum Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 3 of 4I/jmrFigure 12.2-10 Drywell and Foundation Cross Section Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 4 of 4I/jmrFigure 12.2-11 Main Steam Line Anchor Frame and RestraintsBOT. OF STEELEL. 9371SECTION (OF NF46164)EL. 9360MK1MK2 & MK3MK2MK1BKT30 WF33 WF33 WFMK3SEE MECH. DWGs.GRADE B PIPE10 SCH 80EL. 9440+BOT. OF STEEL80 REF26EL. 9426EL. 9406EL. 9310LU00002usar12.21CSection E-E (of NF-36852) | | Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 1 of 4SECTION 12PLANT STRUCTURES AND SHIELDING I/jmrFIGURESFOR ADMINISTRATIVE USE ONLYResp Supv:CNSTP Assoc Ref: |
| | SR:2yrsNFreq:USAR-MANARMS:USAR-12.FIGURESDoc Type:Admin Initials:Date: |
| | 9703 Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 2 of 4 I/jmrFigure 12.2-9 Comparison of Actual Earth Quake Spectrum to Recommended Spectrum Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 3 of 4 I/jmrFigure 12.2-10 Drywell and Foundation Cross Section Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 4 of 4 I/jmrFigure 12.2-11 Main Steam Line Anchor Frame and RestraintsBOT. OF STEEL EL. 9371SECTION (OF NF46164)EL. 9360MK1MK2 & MK3MK2MK1BKT30 WF33 WF33 WFMK3SEE MECH. DWGs. |
| | GRADE B PIPE 10 SCH 80 EL. 9440+BOT. OF STEEL 80 REF26EL. 9426EL. 9406EL. 9310LU00002usar12.21CSection E-E (of NF-36852) |
| SECTION 12 | | SECTION 12 |
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| Revision 26USAR 12.1MONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 1 of 1SECTION 12PLANT STRUCTURES AND SHIELDINGI/kab12.1Summary DescriptionThe plant buildings and structures consist of the reactor building, turbine building,radwaste building, administration building, intake structure, off-gas stack, off-gasbuilding, recombiner building, emergency filtration train building and other auxiliary structures. The design requirements contained in this section apply to the plant structures and equipment which are required to prevent the significant release of radioactivity, which are required for safe shutdown or which are required for powergeneration. Plant structures and equipment not discussed in this section aredesigned in accordance with building codes valid at the Monticello Site. The arrangement of the main plant structures on the site is shown in Drawing ND-95209, Section 15.Drawings NF-36054 through NF-36063, Section 15, show the generalarrangement of the reactor building, turbine building, office and control building.01156713 SECTION 1212.212.2.1 | | Revision 26 USAR 12.1MONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 1 of 1SECTION 12PLANT STRUCTURES AND SHIELDING I/kab12.1Summary Description The plant buildings and structures consist of the reactor building, turbine building,radwaste building, administration building, intake structure, off-gas stack, off-gas building, recombiner building, emergency filtration train building and other auxiliary |
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| | structures. The design requirements contained in this section apply to the plant |
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| | structures and equipment which are required to prevent the significant release of radioactivity, which are required for safe shutdown or which are required for power generation. Plant structures and equipment not discussed in this section are designed in accordance with building codes valid at the Monticello Site. The |
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| | arrangement of the main plant structures on the site is shown in Drawing ND-95209, Section 15.Drawings NF-36054 through NF-36063, Section 15, show the generalarrangement of the reactor building, turbine building, office and control building.01156713 SECTION 1212.212.2.1 |
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| 12.2.2 | | 12.2.2 |
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| SECTION 1212.5 | | SECTION 1212.5 |
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| Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 1 of 4SECTION 12PLANT STRUCTURES AND SHIELDINGI/jmrFIGURESFOR ADMINISTRATIVE USE ONLYResp Supv:CNSTPAssoc Ref:SR:2yrsNFreq:USAR-MANARMS:USAR-12.FIGURESDoc Type:Admin Initials:Date:9703 Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 2 of 4I/jmrFigure 12.2-9 Comparison of Actual Earth Quake Spectrum to Recommended Spectrum Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 3 of 4I/jmrFigure 12.2-10 Drywell and Foundation Cross Section Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORTPage 4 of 4I/jmrFigure 12.2-11 Main Steam Line Anchor Frame and RestraintsBOT. OF STEELEL. 9371SECTION (OF NF46164)EL. 9360MK1MK2 & MK3MK2MK1BKT30 WF33 WF33 WFMK3SEE MECH. DWGs.GRADE B PIPE10 SCH 80EL. 9440+BOT. OF STEEL80 REF26EL. 9426EL. 9406EL. 9310LU00002usar12.21CSection E-E (of NF-36852)}} | | Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 1 of 4SECTION 12PLANT STRUCTURES AND SHIELDING I/jmrFIGURESFOR ADMINISTRATIVE USE ONLYResp Supv:CNSTP Assoc Ref: |
| | SR:2yrsNFreq:USAR-MANARMS:USAR-12.FIGURESDoc Type:Admin Initials:Date: |
| | 9703 Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 2 of 4 I/jmrFigure 12.2-9 Comparison of Actual Earth Quake Spectrum to Recommended Spectrum Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 3 of 4 I/jmrFigure 12.2-10 Drywell and Foundation Cross Section Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 4 of 4 I/jmrFigure 12.2-11 Main Steam Line Anchor Frame and RestraintsBOT. OF STEEL EL. 9371SECTION (OF NF46164)EL. 9360MK1MK2 & MK3MK2MK1BKT30 WF33 WF33 WFMK3SEE MECH. DWGs. |
| | GRADE B PIPE 10 SCH 80 EL. 9440+BOT. OF STEEL 80 REF26EL. 9426EL. 9406EL. 9310LU00002usar12.21CSection E-E (of NF-36852)}} |
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Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23006A1322022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix H, Revision 29, Reactor Pressure Vessel Design Summary Report L-MT-22-021, 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement2022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement ML23006A1532022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix C, Revision 26, Quality Assurance Program ML23006A1492022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 10, Plant Auxiliary Systems ML23006A1282022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix I, Revision 38, Evaluation of High Energy Line Breaks Outside Containment ML23006A1512022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix F, Containment Vessel Design ML23006A1292022-12-19019 December 2022 0 to Updated Safety Analysis Report, Table of Contents ML23006A1472022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 15, Table of Contents - USAR Drawings ML23006A1482022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 14, Plant Safety Analysis ML23006A1502022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 8, Plant Electrical System ML23006A1452022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 6, Plant Engineered Safeguards ML23006A1432022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 13, Plant Operations ML23006A1412022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 9, Plant Radioactive Waste Control Systems ML23006A1422022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix G, Probable Maximum Flood at Mississippi at Monticello Minnesota May 26, 1969 ML23006A1402022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 11, Plant Power Conversion System ML23006A1302022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 1, Introduction and Summary ML23006A1462022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 12, Plant Structures and Shielding ML23006A1442022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 5, Containment System ML23006A1392022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 2, Site and Environs ML23006A1382022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix J, Revision 40, Fire Protection Program ML23006A1372022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 15-2 Drawing Set ML23006A1362022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix D, Revision 35, Pre-Operational and Startup Tests ML23006A1272022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 7, Plant Instrumentation and Control System ML23006A1522022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 4, Reactor Coolant System ML23006A1552022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 3, Reactor ML23006A1352022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix a, Revision 29, Seismic Design Criteria ML23006A1342022-12-19019 December 2022 0 to Updated Safety Analysis Report, List of Effective Pages ML23006A1562022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix E, Revision 35, Plant Comparative Evaluation with the Proposed AEC 70 Design Criteria ML23006A1332022-12-19019 December 2022 Submittal of Revision 40 to Updated Safety Analysis Report ML21070A1112021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 3, Reactor ML21070A1202021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix D, Pre-Operational and Startup Tests ML21070A1062021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 12, Plant Structure and Sheilding ML21070A1092021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 8, Plant Electrical Systems ML21070A1332021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 9, Plant Radioactive Waste Control Systems ML21070A1252021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix J, Fire Protection Program ML21070A1342021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 10, Plant Auxiliary Systems ML21070A1182021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 2, Site and Environs ML21070A1222021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix H, Reactor Pressure Vessel Design Summary Report ML21070A1322021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 13, Plant Operations ML21070A1102021-02-11011 February 2021 8 to Updated Safety Analysis Report, Drawings ML21070A1242021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 15, Drawings ML21070A1142021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix F, Containment Vessel Design Summary Design ML21070A1162021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix I, Evaluation of High Energy Line Breaks Outside Containment ML21070A1262021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 7, Plant Instrumentation and Control Systems ML21070A1072021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix C, Quality Assurance Program ML21070A1042021-02-11011 February 2021 8 to the Updated Safety Analysis Report ML21070A1292021-02-11011 February 2021 8 to Updated Safety Analysis Report, Drawings ML21070A1312021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 1, Introduction and Summary L-MT-21-004, 8 to Updated Safety Analysis Report, Section 11, Plant Conversion Systems2021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 11, Plant Conversion Systems ML21070A1212021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 6, Plant Engineered Safeguards 2022-12-19
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Text
SECTION 12
Revision 26 USAR 12.1MONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 1 of 1SECTION 12PLANT STRUCTURES AND SHIELDING I/kab12.1Summary Description The plant buildings and structures consist of the reactor building, turbine building,radwaste building, administration building, intake structure, off-gas stack, off-gas building, recombiner building, emergency filtration train building and other auxiliary
structures. The design requirements contained in this section apply to the plant
structures and equipment which are required to prevent the significant release of radioactivity, which are required for safe shutdown or which are required for power generation. Plant structures and equipment not discussed in this section are designed in accordance with building codes valid at the Monticello Site. The
arrangement of the main plant structures on the site is shown in Drawing ND-95209, Section 15.Drawings NF-36054 through NF-36063, Section 15, show the generalarrangement of the reactor building, turbine building, office and control building.01156713 SECTION 1212.212.2.1
12.2.2
12.2.3
12.2.412.2.5
SECTION 1212.312.3.1
12.3.2
12.3.3 SECTION 1212.412.4.1
12.4.212.4.3
SECTION 1212.5
Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 1 of 4SECTION 12PLANT STRUCTURES AND SHIELDING I/jmrFIGURESFOR ADMINISTRATIVE USE ONLYResp Supv:CNSTP Assoc Ref:
SR:2yrsNFreq:USAR-MANARMS:USAR-12.FIGURESDoc Type:Admin Initials:Date:
9703 Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 2 of 4 I/jmrFigure 12.2-9 Comparison of Actual Earth Quake Spectrum to Recommended Spectrum Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 3 of 4 I/jmrFigure 12.2-10 Drywell and Foundation Cross Section Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 4 of 4 I/jmrFigure 12.2-11 Main Steam Line Anchor Frame and RestraintsBOT. OF STEEL EL. 9371SECTION (OF NF46164)EL. 9360MK1MK2 & MK3MK2MK1BKT30 WF33 WF33 WFMK3SEE MECH. DWGs.
GRADE B PIPE 10 SCH 80 EL. 9440+BOT. OF STEEL 80 REF26EL. 9426EL. 9406EL. 9310LU00002usar12.21CSection E-E (of NF-36852)
SECTION 12
Revision 26 USAR 12.1MONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 1 of 1SECTION 12PLANT STRUCTURES AND SHIELDING I/kab12.1Summary Description The plant buildings and structures consist of the reactor building, turbine building,radwaste building, administration building, intake structure, off-gas stack, off-gas building, recombiner building, emergency filtration train building and other auxiliary
structures. The design requirements contained in this section apply to the plant
structures and equipment which are required to prevent the significant release of radioactivity, which are required for safe shutdown or which are required for power generation. Plant structures and equipment not discussed in this section are designed in accordance with building codes valid at the Monticello Site. The
arrangement of the main plant structures on the site is shown in Drawing ND-95209, Section 15.Drawings NF-36054 through NF-36063, Section 15, show the generalarrangement of the reactor building, turbine building, office and control building.01156713 SECTION 1212.212.2.1
12.2.2
12.2.3
12.2.412.2.5
SECTION 1212.312.3.1
12.3.2
12.3.3 SECTION 1212.412.4.1
12.4.212.4.3
SECTION 1212.5
Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 1 of 4SECTION 12PLANT STRUCTURES AND SHIELDING I/jmrFIGURESFOR ADMINISTRATIVE USE ONLYResp Supv:CNSTP Assoc Ref:
SR:2yrsNFreq:USAR-MANARMS:USAR-12.FIGURESDoc Type:Admin Initials:Date:
9703 Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 2 of 4 I/jmrFigure 12.2-9 Comparison of Actual Earth Quake Spectrum to Recommended Spectrum Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 3 of 4 I/jmrFigure 12.2-10 Drywell and Foundation Cross Section Revision 22USAR 12.FIGURESMONTICELLO UPDATED SAFETY ANALYSIS REPORT Page 4 of 4 I/jmrFigure 12.2-11 Main Steam Line Anchor Frame and RestraintsBOT. OF STEEL EL. 9371SECTION (OF NF46164)EL. 9360MK1MK2 & MK3MK2MK1BKT30 WF33 WF33 WFMK3SEE MECH. DWGs.
GRADE B PIPE 10 SCH 80 EL. 9440+BOT. OF STEEL 80 REF26EL. 9426EL. 9406EL. 9310LU00002usar12.21CSection E-E (of NF-36852)