ML21201A155
Text
MILLSTONE POWER STATION UNIT 2 FINAL SAFETY ANALYSIS REPORT Revision 3906/30/21
Revision 3906/30/21 MPS-2 FSAR 1 of 14 Revision Summary Revision 3906/30/21 Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes 39 03/31/21 MP2-UCR-2020-011 7.11, 12.10 Addition of 50.69 Program P3 Technical Specification Amendment 337 Risk-Informed Categorization and Treatment of Structure, Systems, and Components of Nuclear Power Reactors 39 03/31/21 MP2-UCR-2021-001 14.6.1.4, 14.6.1.15, 14.6.1.6, 14.6.6, 14.6.7, Tables 14.6-1 and 14.6.1-2 Removal of Inadvertent Opening of a Power Operated Relief Valve in Mode 2 from the Millstone Unit 2 FSAR ETE-NAF-2020-0118 39 03/31/21 MP2-UCR-2021-003 1.10, 12.8 Incorporating Quality Assurace Program Description by Reference CA8102163 38.02 03/31/21 MP2-UCR-2016-011 8.1.2.2.c MP2 FSAR Update To Document The Addition Of The Open Phase Detection Relay Schemes On The High Voltage Side Of The Generator Step-up And Rsst Transformers.
MP2-15-01026, MP2-17-00156 38.02 03/31/21 MP2-UCR-2016-013 1.2.12.d, 11.1.3.1, 11.1.3.2, 11.1.5.1, Table 11.1-1, Figures 1.2-9, 9.12-1, 10.3-1, 11.1-4, 11.1-3, 11.2-5 Update the affected sections due to the removal of demineralizers T141A, T141B, T141C, and the installation of the Energy Solutions ALPS/AIM and SEDS systems.
MP2-14-01169, MP2-15-01044, DC MP2-15-01045 38.02 03/31/21 MP2-UCR-2016-014 Table 11.1-1 Update Liquid and Aerated Waste Valve information to allow other stainless steel material grads and other ANSI ratings.
MP2-14-01169
Revision 3906/30/21 MPS-2 FSAR 2 of 14 38.02 03/31/21 MP2-UCR-2018-015 Appendix 5.E.VI Add NUPIPE II computer code to UFSAR Appendix 5E.VI MP2-17-00178 38.02 03/31/21 MP2-UCR-2019-001 14.1.5.3, 14.6.3.6.2, Table 14.1.5.3-1, 14.1.5.3-2, 14.6.3-4 through 14.6.3-6 Updated Main Steam Line Break and Steam Generator Tube Rupture Dose Consequences.
ETE-NAF-2019-0010, CR 1094790, CR 1103271 38.02 03/31/21 MP2-UCR-2019-007 9.8.2.2.3.5 Permanently Bypass RFM Aux. Hoist Load Cell Interlock, M2H12.
MP2-19-01136 38.02 03/31/21 MP2-UCR-2020-001 Figure 8.1-1D 345kV Switch 15G-18T-8 Replacement.
MP3-18-01094 38.02 03/31/21 MP2-UCR-2020-008 5.2.8.4.1, 5.2.8.4.2 Revision of "MP2 Tendon Surveillance Program Description".
LBDCR 19-MP2-009 38.02 03/31/21 MP2-UCR-2020-010 7.8.3 Replacing ENRS (ARCOS) with DEENS (Everbridge)
MP-20-04 EP-AA-101-Attachment 2, 50.54(q),
for change from Emergency Notification & Response System (ENRS) to Dominion Energy Emergency Notification System (DEENS) 38.01 09/30/20 MP2-UCR-2015-010 8.6.2.2, 5.6.4.1 Reflects replacement of inverters (INV 2, INV4, INV6).
MP2-14-01158 38.01 09/30/20 MP2-UCR-2015-020 Figure 8.1-1D Reflects revised discussion regarding piping weld examination method(s).
LBDCR 14-MP2-019 Revision 3906/30/21 Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 3 of 14 38.01 09/30/20 MP2-UCR-2016-005 7.2.3.2.2 Delete the word "reed" in the first paragraph in MP2 FSAR section 7.2.3.2.2.
MP2-15-01097 38.01 09/30/20 MP2-UCR-2020-004 6.7.2 Update Unit 2 FSAR to reflect changes for License Amendment No. 338.
License Amendment No. 338 Revision 3806/30/20 Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes 38 06/30/20 MP2-UCR-2019-030 8.3 Increasing the TRM required Diesel Fuel Oil Storage for T-148.
ETE-MP-2020-1002 38 06/30/20 MP2-UCR-2020-002 3.3.1.1.2, 3.3.4, 3.5.2.2.1, 3.5.5, Figure 14.0.7-1, Figure 14.0.7-5, Figure 14.0.7-6, Table 14.1.5.2-6 Millstone Unit 2 Cycle 27 Updates to Millstone Unit 2 Final Safety Analysis Report.
EVAL-ENG-RSE-M2C27 38 06/30/20 MP2-UCR-2020-003 5.2.6.1.1, 8.7.1.2, 8.7.2.2 Update the MP2 FSAR to reflect IEEE Standard 317-1976 as applicable to replacement medium voltage electrical containment penetration modules.
MP2-19-01025 37.03 03/31/20 MP2-UCR-2019-006 9.2.4.1 Interm Retirement of MP2 Boric Acid Heat Tracing Circuits.
ETE-MP-2019-1081 Revision 3906/30/21 Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 4 of 14 37.03 03/31/20 MP2-UCR-2018-010 1.2.5, 1.4.3.1, 4.3.2, Table 4.3-2, Table 10.2-1 Updating The FSAR to Accurately Reflect The New Unit 2 Main Steam Moisture Content.
MP2-19-01066 37.03 03/31/20 MP2-UCR-2019-011 8.5.1.2 Changing of the Unit 2 Vital Battery Discharge Testing and Battery Charger Load Testing frequencies.
ETE-MP-2019-1055 37.02 12/30/19 MP2-UCR-2017-017 Figure 14.0.7-5 Departure from Nucleate Boiling Limiting Condition for Operation Verification Results.
ETE-NAF-2017-0169 Revision 3806/30/20 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes 37.02 12/3019 MP2-UCR-2019-005 4.3.8.1.1, 4.3.8.3.1, 7.5.1.2.1.1.a, 7.5.1.2.1.1.c, 7.5.1.2.2, 7.5.5.1, 7.5.5.3, 7.5.5.4, 7.5.6.2.2.2.6, 7.5.6.3.2.1.8, 7.5.6.3.2.2.7, 7.6.2.2.2 Trend Recorder Description.
MP2-17-00101, DCR M2-96064, M2-05003 37.01 09/30/19 MP2-UCR-2017-010 2.5.4.2.1 AOP 2560 - Actions Due to Intake Water Level Elevation Approaching 16-6 Revision 3806/30/20 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 5 of 14 37.01 09/3019 MP2-UCR-2019-002 7.3.4.2.3 SAR section 7.3.4.2.3 not consistent with Specification 7604-M-480, Specification For Engineered Safety Actuation Systems for The Millstone Point Company Millstone Nuclear Power Station Unit 2 Waterford Connecticut.
STI-M2-2018-001 Revision 3706/27/19 Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes 36.2 12/31/18 MP2-UCR-2018-001 8.6.2.2 Unit 2 inverter replacement.
MP2-14-01130 36.2 12/31/18 MP2-UCR-2018-005 7.4.7.2.2 Millstone Unit 2 Main Control Room Recorders Replacement on panel C-05.
MP2-17-00171 36.2 12/31/18 MP2-UCR-2018-011 8.1.2.2 Generator Backup Audio-Tone Equipment Replacement.
MP2-18-00102 36.2 12/31/18 MP2-UCR-2018-012 Table 11.1-1 Correction of Volume of Waste Gas Surge Tank in FSAR Table 11.1.-1.
CR1078780, CR1091106 36.2 12/31/18 MP2-UCR-2018-014 14.0.7.2, 14.0.7-5, Figure 14.0.7-6, Table 14.1.5.2-6 Millstone Unit 2 Cycle 26 Updates to Millstone Unit 2 Final Safety Analysis Report.
EVAL-ENG-RESE-M2C26 Revision 3806/30/20 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 6 of 14 36.2 12/31/18 MP2-UCR-2018-016 Table 14.6.3-5 Specification of the Basis for the Steam Generator Partition Factor for Particulates.
ETE-NAF-2018-0099 36.1 09/27/18 MP2-UCR-2015-017 8.4.2.1, 8.5.1.1, 8.5.2.1, 8.5.2.2, 8.5.3.1, 8.5.3.2 Reflects removal of 125 VDC lighting loads from Vital Station Batteries & installation of LED lighting.
MP2-14-01185 36.1 09/27/18 MP2-UCR-2018-007 14.1.5.2.5.1.4, 14.1.5.2.5.1.6, 14.1.5.2.6.2.1, 14.1.5.2.6.2.3, Table 14.1.5.2-5, Table 14.1.5.2-6, Table 14.1.5.2-8, Figure 14.1.5.2.-9, Figure 14.1.5.2.-10, Figure 14.1.5.2.-11, Figure 14.1.5.2.-12, Figure 14.1.5.2.-13, Figure 14.1.5.2.-14, Figure 14.1.5.2.-15, Figure 14.1.5.2.-16 MPS2 FSAR Update for Post-Scram Main Steam Line Break with Decreased MTC and Revised AFW Flow Distribution.
ETE-NAF-2018-0019 36.1 09/27/18 MP2-UCR-2018-009 14.6.5.2, Table 14.6.5.2-7 MPS3 FSAR Update to the Small Break Loss of Coolant Accident (SBLOCA) Results Due to Error Correction.
ETE-NAF-2018-0060 Revision 3706/27/19 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 7 of 14 Revision 3606/28/18 Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes 36 06/28/18 MP2-UCR-2017-005 10.4.5.5 Update FSAR Section 10.4.5.5 to read as follows: "The plant can carry 55 percent load with one-half of the feedwater heaters out of service and isolated from the system, with only one condensate pump in operation and with only one SGFP in service".
LA3022214 36 06/28/18 MP2-UCR-2018-002 Table 1.3-1, Table 11.1-1 Correction of Volume of Waste Gas Test Tank in FSAR table 11.1-1 CR1078780 and CR1080672 36 06/28/18 MP2-UCR-2018-006 Table 4.6-2 Update to MPS2 Pressurizer RTNDT values determined through Drop Weight Testing.
AREVA CR 2017-2164 35.3 03/29/18 MP2-UCR-2017-017 Table 14.0.7-5, Figure 14.0.7-5 Departure from Nucleate Boiling Limiting Condition for Operation Verification Results.
ETE: ETE-NAF-2017-0169 CA3060853 35.3 03/29/18 MP2-UCR-2018-003 Table 9.11-2 Change Pressure Values on Table 9.11-2 for Instrument Air Receiver Tanks T-51E and T-51F.
DC: MP2-17-00175 35.2 12/28/17 MP2-UCR-2017-013 9.2.3.3, 11.1.3.1 Modify U3 FSAR to correct item related to previous degasifier related FSAR change.
FSARCR: 98-MP2-167 35.2 12/28/17 MP2-UCR-2017-014 9.2.2.1 Modify U2 FSAR to correct item related to VCT level controls related to a previous FSAR change.
FSARCR: 97-MP2-66
Revision 3906/30/21 MPS-2 FSAR 8 of 14 35.1 09/28/17 MP2-UCR-2016-001 1.A, 8.1.2.2, 8.1.2.3 Eversource 15G Breaker Failure Relay Replacement.
ETE-MP-2015-1186 35.1 09/28/17 MP2-UCR-2016-018 8.1.1.2, 8.1.2.1, 8.1.2.2, Fig 8.1-1B, Fig 8.1-1C, Fig 8.1-1D Eversource Energy proposes to reconfigure the 345 kV Millstone - Haddam - Besesk 348 line. ETE-MP-2016-1135 35.1 09/28/17 MP2-UCR-2016-019 7.6.5.4.1 App R fire panel door lock removal.
CR1045068 35.1 09/28/17 MP2-UCR-2016-020 7.5.5.3 Plant Process Computer Data Diode Installation.
MP2-16-01035 35.1 09/28/17 MP2-UCR-2017-001 Figure 6.5-1, Table 6.5-2 Replacement of C CAR Fan M2F14C.
MP2-17-01004 Revision 3606/28/18 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 9 of 14 35.1 09/28/17 MP2-UCR-2017-002 1.4.2, 3.1, 3.2.3, 3.3.1, 3.3.1.1, 3.3.1.1.1, 3.3.1.1.2, 3.3.1.3.1, 3.3.1.3.2, 3.3.4 Refs, Table 3.3-1, Figure 3.3-1A, Figure 3.3-1B, 3.4.2, 3.4.3.2.3, 3.5.1.1, 3.5.2.1.2, 3.5.2.1.3, 3.5.3.3.1, 3.5.3.3.4, Table 3.5-1, 9.5.2.1, 9.5.3.1, 9.5.4.1, 14.0.2, 14.0.7.1, 14.0.10, Table 14.0.2-2, Table 14.0.7-4, Table 14.0.7-5, Figure 14.0.7-1, Figure 14.0.7-2, Figure 14.0.7-5, Figure 14.0.7-6, 14.1.5.1.6.1, 14.1.5.1.6.1.3, 14.1.5.1.7, 14.1.5.2.5.1.4, 14.1.5.2.5.1.6, 14.1.5.2.6.1.1, 14.1.5.2.6.1.2, 14.1.5.2.6.1.3, Table 14.1.5.1-5, Table 14.1.5.1-6, able 14.1.5.1-7, Figure 14.1.5.1-1, Figure 14.1.5.1-2 This SAR Change Request updates the Millstone Unit 2 FSAR for the Cycle 25 core design and supporting safety analyses.
ETE-NAF-2017-0001, EVAL-ENG-RSE-M2C25 Revision 3606/28/18 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 10 of 14 35.1 09/28/17 MP2-UCR-2017-002 (cont)
Figure 14.1.5.1-3, Figure 14.1.5.1-4, Figure 14.1.5.1-5, Figure 14.1.5.1-6, Table 14.1.5.2-4, Table 14.1.5.2-5, Table 14.1.5.2-6, Table 14.1.5.2-7, Figure 14.1.5.2-2, Figure 14.1.5.2-3, Figure 14.1.5.2-4, Figure 14.1.5.2-5, Figure 14.1.5.2-6, Figure 14.1.5.2-7, Figure 14.1.5.2-8, Figure 14.1.5.2-9, Table 14.2.4-3, Figure 14.2.4-1, Figure 14.2.4-2, Figure 14.2.4-3, Figure 14.2.4-4, Figure 14.2.4-5, 14.4.6.5, 14.4.6.6, 14.4.10 Refs, Table 14.4.6-2, Table 14.4.6-3, Table 14.4.6-4, 14.6.5, 14.6.5.1 through 14.6.5.8, 14.6.5.4 through 14.6.5.4.8 (new)
This SAR Change Request updates the Millstone Unit 2 FSAR for the Cycle 25 core design and supporting safety analyses.
ETE-NAF-2017-0001, EVAL-ENG-RSE-M2C25 Revision 3606/28/18 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 11 of 14 35.1 09/28/17 MP2-UCR-2017-002 (cont) 14.6.6 Refs, Table 14.6.5.1-3, Table 14.6.5.1-4, Table 14.6.5.1-5, Table 14.6.5.1-6, Table 14.6.5.1-7, Table 14.6.5.1-8, Figures 14.6.5.1-1 through Figure 14.6.5.1-17, Tables 14.6.5.4-1 through Table 14.6.5.4-7, Figures 14.6.5.4-1 through Figures 14.6.5.4-19 This SAR Change Request updates the Millstone Unit 2 FSAR for the Cycle 25 core design and supporting safety analyses.
ETE-NAF-2017-0001, EVAL-ENG-RSE-M2C25 35.1 09/28/17 MP2-UCR-2017-006 4.3.8.5.11 Update to reflect that during normal operation, strainers for the B and C RCPs are operated with their strainer baskets removed and the A and D RCPs do not have strainers.
MP2-17-01033 35.1 09/28/17 MP2-UCR-2017-007 7.3.1.2.8 Engineered Safety Feature Actuation UFSAR Response Time Change.
ETE-MP-2015-1030 35.1 09/28/17 MP2-UCR-2017-008 4.3.2, 4.3.5 MP2 Plant Process Computer Replacement additional FSAR changes missed during the initial project.
MP2-13-01067 35.1 09/28/17 MP2-UCR-2017-009 8.3.3.1 Implementation of Revised Combustible Gas (Hydrogen) Control Requirements in Containment additional FSAR changes missed during the initial project.
M2-04009 Revision 3606/28/18 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 12 of 14 35.1 09/28/17 MP2-UCR-2017-011 9.10.2.1 Editorial correction to MP2 FSAR. Change last 2 sentences of 4th paragraph of 9.10.2.1 on page 9.10-2 Pump Running and trouble signals for pump P-82 are available in the Unit 2 (Should be Unit 3) Control Room.
DM3-01-0064-00 35.1 09/28/17 MP2-UCR-2017-012 14.8.2.1.2 Modify FSAR sections 10.4.5.5 and 14.8.2.1.2 to correct editorial errors.
LA3022214, CR1047811 Revision 3506/29/17 Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes 35 06/29/17 Administrative As identified in the 2017 NRC Submittal List of Changed Pages and submitted Summary of Change.
Major Revision issued for the purpose of 2017 NRC Submittal. Updated footer on all pages to reflect Revision 35.
35 06/29/17 MP2-UCR-2017-004 10.3.4.2, Table 10.3-1 LA3022214 - Modify FSAR Section 10.3.4.2 Tests and Inspection to read See Section 5.2.7.4.1 in lieu of 5.2.8.4.2.
35 06/29/17 MP2-UCR-2015-025 14.0.11, 14.6.1.1, 14.6.1.6 Confirmatory Order EA-13-188, AREVA analysis ANP-3406, Rev. 0 - Remove credit for charging from the long-term portion of the inadvertent opening of the PORV (IOPORV) event.
Revision 3606/28/18 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 13 of 14 34.3 03/30/17 MP2-UCR-2016-008 9.5.1.1, 9.5.2.1, 9.5.3.1 The NRC requested additional information be provided in the FSAR to describe the procedural controls in place to maintain the Millstone 2 Spent Fuel Pool temperature below 150°F. LAR 15-571 34.2 12/22/16 MP2-UCR-2016-016 14.6.5.2, 14.6.5.2.5, 14.6.5.2.5.1, 14.6.5.2.5.2, 14.6.5.2.5.3, 14.6.5.2.5.4, 14.6.5.2.5.5, 14.6.5.2.5.8, 14.6.5.2.5.9, 14.6.5.2.6, 14.6.5.2.7, 14.6.5.2.8, Figures 14.6.5.2-1, 14.6.5.2-2, 14.6.5.2-3, 14.6.5.2-4, 14.6.5.2-5, 14.6.5.2-6, 14.6.5.2-7, 14.6.5.2-8, 14.6.5.2-9, 14.6.5.2-10, 14.6.5.2-11, 14.6.5.2-12, 14.6.5.2-13, 14.6.5.2-14, 14.6.5.2-15, 14.6.5.2-16, 14.6.5.2-17, 14.6.5.2-18, 14.6.5.2-19, 14.6.5.2-20, 14.6.5.2-21, 14.6.5.2-22, Tables 14.6.5.2-3, 14.6.5.2-4, 14.6.5.2-5, 14.6.5.2-6, 14.6.5.2-7 This SAR change request updates the Small Break Loss of Coolant Accident (SBLOCA) analysis presented in FSAR Section 14.6.5.2.
34.2 12/22/16 MP2-UCR-2016-012 15.2.1.21 MP3 HVK Chiller Service Water Thermal Performance Testing Elimination.
34.2 12/22/16 MP2-UCR-2016-010 15.2.1.2 Cancellation of Millstone 2 Boraflex Monitoring Program.
Revision 3506/29/17 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR 14 of 14 34.2 12/22/16 MP2-UCR-2016-009 11.E.1 RM-8123 and RM-8262 are described incorrectly in the FSAR. This change removes the reference to a gamma geiger muller detector chamber type and replace it with the correct beta scintillator type detector.
34.2 12/22/16 MP2-UCR-2016-003 9.3.2.3 Update Subsection 9.3.2.3 to reflect changes made by DCN DM2-00-0166-07 that eliminated the packing leak-off lines on M22-SI-306.
34.2 12/22/16 MP2-UCR-2015-007 1.2.10.4, 1.A, 9.8.2.1.1, 9.8.2.1.2, 9.8.2.2.2, Figure 9.8-7, Figure 9.8-8A, Figure 9.8-8B, Figure 9.8-8C, 14.7.4.1 Reflects changes associated with LBDCR 12-MP2-008.
34.2 12/22/16 MP2-UCR-2013-017 Table 6.7-1, Table 9.9-11 Reflects correction of technical value in the respective tables.
34.1 9/29/16 MP2-UCR-2016-007 Chapter 1 section 1.A; Chapter 8 List of Figures; Chapter 8 Section 8.1.1.4, 8.1.2.1; 8.1.2.2; 8.1.2.3 and Figure 8.1-1A; 8.1-1B Unit 2 SLOD Removal (LBDCR 15-MP2-006) 34.1 9/29/16 MP2-UCR-2016-006 Section 14.8.2.2.4 Millstone 2 NRC License Amendment 326, Millstone Power Station Unit 2 - Issuance of Amendment to Revise Technical Specifications for Containment Leak Rate Testing (CAC No. MF5838), March 31, 2016 (ADAMS Accession Number ML16068A312).
34.1 9/29/16 MP2-UCR-2016-004 Table 11.2-1 Correct typo identified by CR1017686.
Revision 3506/29/17 (Continued)
Revision Revision Release Date Change Activity Document Elements Affected (Sections, Tables, Figures)
Summary Description of Changes
Revision 3906/30/21 MPS-2 FSAR LOA 1 of 3 LIST OF ABBREVIATIONS Abbreviation ADH Aerated Drain Header AEAS Auxiliary Exhaust Actuation Signal AES Auxiliary Exhaust System ATWS Anticipated Transient Without Scram BOL Beginning of Life BWR Boiling Water Reactor CEA Control Element Assembly CEDM Control Element Drive Mechanism CEDS Control Element Drive System CFR Code of Federal Regulations CIAS Containment Isolation Actuation Signal CRFS Control Room Filtration System CSAS Containment Spray Actuation Signal CSS Containment Spray System CVCS Chemical and Volume Control System CVH Containment Vent Header DBA Design Basis Accident DBE Design Basis Earthquake DNB Departure from Nucleate Boiling DNBR Departure from Nucleate Boiling Ratio DRL Division of Reactor Licensing EB Enclosure Building EBFR Enclosure Building Filtration Region EBFS Enclosure Building Filtration System
Revision 3906/30/21 MPS-2 FSAR LOA 2 of 3 List of Abbreviations (Continued)
Abbreviation ECCS Emergency Core Cooling System EOL End of Life ESCS Engineered Safety Features Control System F
Degrees Fahrenheit FPS Fire Protection System FT Fuel Transfer FW Feed Water HMP High Mechanical Performance HPSI High Pressure Safety Injection HTP High Thermal Performance IA Instrument Air ID Inside Diameter LOCA Loss of Coolant Accident LPSI Low Pressure Safety Injection MPC Maximum Permissible Concentration MSL Mean Sea Level MSS Main Steam System MTU Metric Tons Uranium MWD Megawatt Days NDT Non-Destructive Testing NDTT Nil Ductility Transition Temperature NS Nitrogen Supply NSSS Nuclear Steam Supply System OBE Operating Basis Earthquake
Revision 3906/30/21 MPS-2 FSAR LOA 3 of 3 List of Abbreviations (Continued)
Abbreviation OD Outside Diameter PA Purge Air PDH Primary Drain Header PDT Primary Drain Tank PPM Parts Per Million PVMP Preoperational Vibration Monitoring Program PWR Pressurized Water Reactor RBCCW Reactor Building Closed Cooling Water RBCCWS Reactor Building Closed Cooling Water System RCS Reactor Coolant System RWS Radioactive Waste System RWST Refueling Water Storage Tank SA Station Air SGBS Steam Generator Blowdown System SIAS Safety Injection Actuation Signal SIS Safety Injection System SRAS Sump Recirculation Actuation Signal SRST Spent Resin Storage Tank SS Sampling System TBCCWS Turbine Building Closed Cooling Water System WGH Waste Gas Header WREC Westinghouse Rector Evaluation Center WTR Westinghouse Test Reactor
Revision 3906/30/21 MPS-2 FSAR TOC 1 of 9 Section Title Page CHAPTER 1: INTRODUCTION AND
SUMMARY
Table of Contents List of Tables List of Figures 1.1 Introduction....................................................................................................... 1.1-1 1.2 Summary Description....................................................................................... 1.2-1 1.3 Comparison with Other Plants.......................................................................... 1.3-1 1.4 Principal Architectural And Engineering Criteria for Design.......................... 1.4-1 1.5 Research and Development Requirements....................................................... 1.5-1 1.6 Identification of Contractors............................................................................. 1.6-1 1.7 General Design Changes Since Issuance of Preliminary Safety Analysis Report.....
1.7-1 1.8 Advisory Committee on Reactor Safeguards Special Interest Items [This Section Provides Historical Information Provided to the ACRS at the Time of Initial Licensing and Was Not Intended to Be Updated.]........................................... 1.8-1 1.9 Topical Reports................................................................................................. 1.9-1 1.10 Material Incorporated by Reference............................................................... 1.10-1 1.A AEC General Design Criteria for Nuclear Power Plants................................. 1.A-1 CHAPTER 2: SITE AND ENVIRONMENT Table of Contents List of Tables List of Figures 2.1 General Description.......................................................................................... 2.1-1 2.2 Population, Land Use and Water Use............................................................... 2.2-1 2.3 Meteorology...................................................................................................... 2.3-1 2.4 Geology............................................................................................................. 2.4-1 2.5 Hydrology......................................................................................................... 2.5-1 TABLE OF CONTENTS
Revision 3906/30/21 MPS-2 FSAR TOC 2 of 9 Table of Contents (Continued)
Section Title Page 2.6 Seismology........................................................................................................ 2.6-1 2.7 Subsurface and Foundations............................................................................. 2.7-1 2.8 Environmental Monitoring Program................................................................. 2.8-1 2.9 Environmental Radiation Monitoring Program................................................ 2.9-1 CHAPTER 3: REACTOR Table of Contents List of Tables List of Figures 3.1 Summary Description....................................................................................... 3.1-1 3.2 Design Bases..................................................................................................... 3.2-1 3.3 Mechanical Design........................................................................................... 3.3-1 3.4 Nuclear Design and Evaluation........................................................................ 3.4-1 3.5 Thermal-Hydraulic Design............................................................................... 3.5-1 3.A Analysis of Reactor Vessel Internals............................................................... 3.A-1 CHAPTER 4: REACTOR COOLANT SYSTEM Table of Contents List of Tables List of Figures 4.1 General System Description............................................................................. 4.1-1 4.2 Design Basis..................................................................................................... 4.2-1 4.3 System Component Design............................................................................... 4.3-1 4.4 Materials Compatibility.................................................................................... 4.4-1 4.5 System Design Evaluation................................................................................ 4.5-1 4.6 Tests and Inspections........................................................................................ 4.6-1
Revision 3906/30/21 MPS-2 FSAR TOC 3 of 9 Table of Contents (Continued)
Section Title Page 4.A Seismic Analysis of Reactor Coolant System.................................................. 4.A-1 CHAPTER 5: STRUCTURES Table of Contents List of Tables List of Figures 5.1 General.............................................................................................................. 5.1-1 5.2 Containment General Description.................................................................... 5.2-1 5.3 Enclosure Building........................................................................................... 5.3-1 5.4 Auxiliary Building............................................................................................ 5.4-1 5.5 Turbine Building............................................................................................... 5.5-1 5.6 Intake Structure................................................................................................. 5.6-1 5.7 External Class I Tanks...................................................................................... 5.7-1 5.8 Seismic Design................................................................................................. 5.8-1 5.9 Construction Practice and Quality Assurance.................................................. 5.9-1 5.A Description of Finite Element Method Used in Containment Analysis.......... 5.A-1 5.B Justification For Load Factors and Load Combinations Used in Design Equations of Containment.................................................................................................5.B-1 5.C Justification For Capacity Reduction Factors () Used in Determining Capacity of Containment......................................................................................................5.C-1 5.D Expanded Spectrum of Tornado Missiles........................................................ 5.D-1 5.E Computer Program List and Descriptions........................................................5.E-1 5.E.1 Computer Program Applicability and Validation..........................................5.E.1-1 5.E.2 Computer Program Test Problem Solutions..................................................5.E.2-1 5.E.3 Computer Program Test Problem Similarities...............................................5.E.3-1 5.F Containment Water Intrusion Into Tendon Gallery During Construction (1)...5.F-1
Revision 3906/30/21 MPS-2 FSAR TOC 4 of 9 Table of Contents (Continued)
Section Title Page CHAPTER 6: ENGINEERED SAFETY FEATURES SYSTEMS Table of Contents List of Tables List of Figures 6.1 General.............................................................................................................. 6.1-1 6.2 Refueling Water Storage Tank and Containment Sump................................... 6.2-1 6.3 Safety Injection System.................................................................................... 6.3-1 6.4 Containment Spray System............................................................................... 6.4-1 6.5 Containment Air Recirculation and Cooling System....................................... 6.5-1 6.6 Containment Post-Accident Hydrogen Control System................................... 6.6-1 6.7 Enclosure Building Filtration System............................................................... 6.7-1 CHAPTER 7: INSTRUMENTATION AND CONTROL Table of Contents List of Tables List of Figures 7.1 Introduction....................................................................................................... 7.1-1 7.2 Reactor Protective System................................................................................ 7.2-1 7.3 Engineered Safety Features Actuation System................................................. 7.3-1 7.4 Regulating Systems........................................................................................... 7.4-1 7.5 Instrumentation System.................................................................................... 7.5-1 7.6 Operating Control Stations............................................................................... 7.6-1 7.7 Control Room Annunciation............................................................................. 7.7-1 7.8 Communication Systems.................................................................................. 7.8-1 7.9 Anticipated Transients Without Scram Circuitry............................................. 7.9-1
Revision 3906/30/21 MPS-2 FSAR TOC 5 of 9 Table of Contents (Continued)
Section Title Page 7.10 Auxiliary Steam Line Break Detection/isolation System............................... 7.10-1 7.11 Environmental Qualification of Electrical Equipment Important to Safety... 7.11-1 CHAPTER 8: ELECTRICAL SYSTEMS Table of Contents List of Tables List of Figures 8.0 Electrical Drawings Submitted to AEC for Review......................................... 8.0-1 8.1 Electric Power................................................................................................... 8.1-1 8.2 4160-Volt and 6900-Volt Systems................................................................... 8.2-1 8.3 Emergency Generators...................................................................................... 8.3-1 8.4 480 Volt System................................................................................................ 8.4-1 8.5 Battery System.................................................................................................. 8.5-1 8.6 Alternating Current Instrumentation and Control............................................. 8.6-1 8.7 Wire, Cable and Raceway Facilities................................................................. 8.7-1 CHAPTER 9: AUXILIARY SYSTEMS Table of Contents List of Tables List of Figures 9.1 General.............................................................................................................. 9.1-1 9.2 Chemical and Volume Control System............................................................ 9.2-1 9.3 Shutdown Cooling System................................................................................ 9.3-1 9.4 Reactor Building Closed Cooling Water System............................................. 9.4-1 9.5 Spent Fuel Pool Cooling System...................................................................... 9.5-1 9.6 Sampling System.............................................................................................. 9.6-1
Revision 3906/30/21 MPS-2 FSAR TOC 6 of 9 Table of Contents (Continued)
Section Title Page 9.7 Cooling Water Systems.................................................................................... 9.7-1 9.8 Fuel and Reactor Component Handling Equipment......................................... 9.8-1 9.9 Plant Ventilation Systems................................................................................. 9.9-1 9.10 Fire Protection System.................................................................................... 9.10-1 9.11 Compressed Air System.................................................................................. 9.11-1 9.12 Water Treatment System................................................................................ 9.12-1 9.13 Auxiliary SteamSystem................................................................................. 9.13-1 CHAPTER 10: STEAM AND POWER CONVERSION SYSTEM Table of Contents List of Tables List of Figures 10.1 Summary Description..................................................................................... 10.1-1 10.2 Turbine Generator........................................................................................... 10.2-1 10.3 Main Steam Supply System........................................................................... 10.3-1 10.4 Other Features of Steam and Power Conversion System............................... 10.4-1 CHAPTER 11: RADIOACTIVE WASTE PROCESSING AND RADIATION PROTECTION SYSTEMS Table of Contents List of Tables List of Figures 11.1 Radioactive Waste Processing Systems.......................................................... 11.1-1 11.2 Radiation Protection....................................................................................... 11.2-1 11.A Source Terms for Radioactive Waste Processing and Releases to the Environment 11.A-1 11.B Radioactive Waste Processing of Releases to Environment...............................................................................................11.B-1
Revision 3906/30/21 MPS-2 FSAR TOC 7 of 9 Table of Contents (Continued)
Section Title Page 11.C Doses From Radioactive Releases and Cost-Benefit Analysis..........................................................................................................11.C-1 11.D Expected Annual Inhalation Doses and Estimated Air Concentrations of Radioactive Isotopes for MP2 Facilities.......................... 11.D-1 11.E Airborne Activity Sampling System for Containment, Spent Fuel and Radwaste Atmospheres...................................................................................................11.E-1 CHAPTER 12: CONDUCT OF OPERATIONS Table of Contents 12.1 Organizational Structure................................................................................. 12.1-1 12.2 Training Program............................................................................................ 12.2-1 12.3 Emergency Planning....................................................................................... 12.3-1 12.4 Review and Audit........................................................................................... 12.4-1 12.5 Plant Procedures............................................................................................. 12.5-1 12.6 Records........................................................................................................... 12.6-1 12.7 Physical Security Plans................................................................................... 12.7-1 12.8 Quality Assurance Program............................................................................ 12.8-1 12.9 Deleted by Pkg FSC MP2-UCR-2011-014..................................................... 12.9-1 CHAPTER 13: INITIAL TESTS AND OPERATION Table of Contents List of Tables List of Figures 13.1 Description of the Startup Test Program........................................................ 13.1-1 13.2 Startup Test Program Organization and Responsibilities............................................................................................... 13.2-1 13.3 Administrative Conduct of the Startup Test Program.................................... 13.3-1 13.4 Millstone Startup Group Training Program.................................................... 13.4-1
Revision 3906/30/21 MPS-2 FSAR TOC 8 of 9 Table of Contents (Continued)
Section Title Page 13.5 Initial Inspection and Component Testing Phase........................................... 13.5-1 13.6 Preoperational and Acceptance Test Program................................................ 13.6-1 13.7 Hot Functional Test Program.......................................................................... 13.7-1 13.8 Initial Fuel Loading........................................................................................ 13.8-1 13.9 Initial Criticality.............................................................................................. 13.9-1 13.10 Low Power Physics Testing.......................................................................... 13.10-1 13.11 Power Ascension Testing.............................................................................. 13.11-1 13.12 Piping Operational Testing........................................................................... 13.12-1 13.13 Active Valves Operational Testing............................................................... 13.13-1 13.A Preoperational Test Descriptions................................................................... 13.A-1 CHAPTER 14: SAFETY ANALYSIS Table of Contents List of Tables List of Figures 14.0 General............................................................................................................ 14.0-1 14.1 Increase in Heat Removal By the Secondary System..................................... 14.1-1 14.2 Decrease in Heat Removal by the Secondary System.................................... 14.2-1 14.3 Decrease in Reactor Coolant System Flow..................................................... 14.3-1 14.4 Reactivity and Power Distribution Anomalies............................................... 14.4-1 14.5 Increases in Reactor Coolant System Inventory............................................. 14.5-1 14.6 Decreases in Reactor Coolant Inventory........................................................ 14.6-1 14.7 Radioactive Releases From a Subsystem or Component................................ 14.7-1 14.8 Millstone Unit 2 FSAR Events Not Contained in the Standard Review Plan 14.8-1
Revision 3906/30/21 MPS-2 FSAR TOC 9 of 9 Table of Contents (Continued)
Section Title Page CHAPTER 15: LICENSE RENEWAL Table of Contents List of Tables 15.0 Introduction..................................................................................................... 15.0-1 15.1 Overview of Aging Management Programs................................................... 15.1-1 15.2 Programs That Manage The Effects of Aging on Structures and Components Within the Scope of License Renewal................................ 15.2-1 15.3 Time-Limited Aging Analysis........................................................................ 15.3-1 15.4 TLAA Support Programs................................................................................ 15.4-1 15.5 Exemptions..................................................................................................... 15.5-1 15.6 License Renewal Commitments..................................................................... 15.6-1
Revision 3906/30/21 MPS-2 FSAR LOT 1 of 19 Number Title Table1.1-1 Licensing History Table1.2-1 Summary of Codes and Standards for Components of Water-Cooled Nuclear Power Units (1)
Table1.3-1 Comparison with Other Plants Table1.4-1 Seismic Class I Systems and Components Table1.8-1 Comparison of Preoperational Vibration Monitoring Program Design Parameters Table1.9-1 Topical Reports Table2.3-1 Distances from Release Point to Receptors Table2.3-2 (Deleted)
Table 2.5-1 Effect of Hurricane Generated Surge and Waves on Unit Number 2 Structures Table 2.5-2 Design Wave Conditions Table 2.5-3 Roof Surface Area and Number and Size of Roof Drains Table 2.5-4 All Catch Basins for Elevation Area Draining Into and Runoff Flowing In and Out of a Catch Basin Table3.2-1 Stress Limits for Reactor Vessel Internal Structures Table3.3-1 Mechanical Design Parameters
- Table3.3-2 Pressurized Water Reactor Primary Coolant Water Chemistry Recommended Specifications Table3.4-1 Fuel Characteristics for a Representative Reload Core Table3.4-2 Neutronics Characteristics for a Representative Reload Core Table3.4-3 Representative Shutdown Margin Requirements Table3.5-1 Nominal Reactor and Fuel Design Parameters Table3.5-2 Design Operating Hydraulic Loads on Vessel Internals Table3.5-3 Uncertainty Sources for DNBR Calculations (Deleted)
LIST OF TABLES
Revision 3906/30/21 MPS-2 FSAR LOT 2 of 19 List of Tables (Continued)
Number Title Table3.A-1 Natural Frequencies for Vertical Seismic Analysis Mathematical Model Table3.A-2 Seismic Stresses in Critical Reactor Internals Components for the Design Basis Earthquake Table 4.1-1 Reactor Coolant System Volumes Table4.2-1 Principal Design Parameters of Reactor Coolant System Table 4.2-2A Table of Loading Combinations and Primary Stress Limits Table 4.2-2B Table of Loading Combinations and Primary Stress Limits for the Replace-ment Reactor Vessel Head and Replacement pressurizer Table4.2-3 Reactor Coolant System Code Requirements Table4.2-4 Comparison with Safety Guide 26 Table4.3-1 Reactor Vessel Parameters Table4.3-2 Steam Generator Parameters Table4.3-3 Main Steam Safety Valve Parameters Table4.3-4 Tech Pub Review PKG for T4.3-4Reactor Coolant Pump Parameters Table4.3-5 Reactor Coolant Piping Parameters Table4.3-6 Pressurizer Parameters Table4.3-7 Quench Tank Parameter Table4.3-8 Pressurizer Spray (RC-100E, RC-100F) Valve Parameters Table4.3-9 Power-Operated Relief Valve Isolation Valve Parameters (RC-403, RC-405)
Table4.3-10 Pressurizer Power-Operated Relief Valve Parameters (RC-402, RC-404)
Table4.3-11 Pressurizer Safety Valve Parameters (RC-200, RC-201)
Table4.3-12 Active and Inactive Valves in the Reactor Coolant System Boundary Table4.4-1 Materials Exposed to Coolant
Revision 3906/30/21 MPS-2 FSAR LOT 3 of 19 List of Tables (Continued)
Number Title Table4.4-2 Reactor Coolant Chemistry Table4.5-1 Reactor Coolant System Component Nozzles, Nozzle Sizes and Nozzle Materials Table4.5-2 Reactor Coolant System Heatup and Cooldown Limits Table4.6-1 RTNDT Determination for Reactor Vessel Base Metal Millstone Unit Number 2 Table4.6-2 Charpy V-Notch and Drop Weight Test Values - Pressurizer Millstone Unit Number 2 Table4.6-3 Charpy V-notch and Drop Weight Test Values - Steam Generator Table4.6-4 Charpy V-notch Values - Piping Table4.6-5 Plate and Weld Metal Chemical Analysis Table4.6-6 Beltline Mechanical Test Properties - Reactor Vessel Surveillance Materials Table4.6-7 Tensile Test Properties - Reactor Vessel Surveillance Materials Table4.6-8 Summary of Specimens Provided for Each Exposure Location Table4.6-9 Capsule Removal Schedule Table4.6-10 Inspection of Reactor Coolant System Components During Fabrication and Construction Table4.6-11 Reactor Coolant System Inspection C-E Requirements Table4.6-12 Reactor Coolant System Inspection C-E Requirements (Continued)
Table4.6-13 RTPTS Values at 54 EFPY Table4.6-14 Adjusted Reference Temperatures (ART) Projections Table4.A-1 Natural Frequencies and Dominant Degrees of Freedom Table4.A-2 Seismic Loads on Reactor Coolant System Components for Operational Basis Earthquake Table5.2-1 Containment Structure Analysis Summary
Revision 3906/30/21 MPS-2 FSAR LOT 4 of 19 List of Tables (Continued)
Number Title Table5.2-2 Containment Structure Analysis Summary - Dead Load, Initial Prestress and Live Load (D+KF+L)
Table5.2-3 Containment Structure Analysis Summary - Dead Load, Initial Prestress and Live Load (D+F+L+1.15P)
Table5.2-4 Containment Structure Analysis Summary - Dead Load, Initial Prestress and Live Load, Operating Temperature and OBE (D+F+L+T0+E)
Table5.2-5 Containment Structure Analysis Summary - Dead Load, Prestress, Live Load, 100% Accident Pressure and Accident Temperature (D+F+L+1.0P+T1)
Table5.2-6 Containment Structure Analysis Summary - Dead Load, Prestress, Operating Temperature, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE (D+F+T0+H+R+E1)
Table 5.2-6A Deleted by FSARCR 04-MP2-016 Table5.2-7 Containment Structure Analysis Summary - Dead Load, Prestress, 100%
Accident Pressure, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE (D+F+1.0P+H+T1+E1)
Table5.2-8 Containment Structure Analysis Summary - Dead Load, Prestress, 125%
Accident Pressure, 125% Thermal Expansion Forces of Pipes, Accident Temperature and 125% DBE (D+F+1.25P+1.25H+T1+1.25E)
Table5.2-9 Containment Structure Analysis Summary - Dead Load, Prestress, 150%
Accident Pressure, and Accident Temperature (D+F+1.5P+T1)
Table5.2-10 Spectrum of Potential Missiles From Inside the Containment Table5.2-11 Containment Structure Isolation Valve Information Table5.2-12 Containment Penetration Piping Table5.2-13 Major(1) Containment Isolation Valves Table5.2-14 Typical Leak Rate Measurement System Instrumentation
Revision 3906/30/21 MPS-2 FSAR LOT 5 of 19 List of Tables (Continued)
Number Title Table5.2-15 Typical Containment Resistance Temperature Detectors and Dewcell Sensor Volume Weight Fractions Table5.5-1 Maximum Actual Stresses - Turbine Building Table5.8-1 Material Damping Values Table5.9-1 Aggregate Tests Table5.9-2 Cement Tests Table5.9-3 Fly Ash Tests Table5.9-4 Typical Chemical Analysis of Fly Ash Used Table5.9-5 Allowable Void Limits for Cadwelding Table5.D-1 Impactive Velocities (fps) of Missiles of Different CdA/W Factors as Picked from the Ground by the Design Tornado Table5.D-2 Kinetic Energy per Ft2 of Impact Area Table5.D-3 Radius vs. Velocity FPS/MPH (D=0.882 psi/V1 = 27 mph)
Table5.D-4 Radius vs. Velocity FPS/MPH (D=3 psi/V1 = 60 mph)
Table5.D-5 Velocities of Various Missiles Table5.D-6 Test Data Summary Table 5.D.A-1A Relative Conservatism in Steps A, B, and C Table 5.D.A-2A Table 5.D.A-3A Table6.1-1 Pipe Rupture Protection Requirements Table6.1-2 Omitted Table6.1-3 Design Non-Seismic Category I Components Located Inside Containment and Enclosure Building
Revision 3906/30/21 MPS-2 FSAR LOT 6 of 19 List of Tables (Continued)
Number Title Table6.1-4 Pipe Rupture Criteria Applicability (Outside Containment) Based on Normal Operating Plant Conditions Table6.2-1 Refueling Water Storage Tank and Containment Sump Table6.3-1 Omitted Table6.3-2 Principal Design Parameters of the Safety Injection System Table6.3-3 Shutdown Cooling Heat Exchanger Data Table6.3-4 Omitted Table6.3-5 Internal Dimensions of Containment Sump Recirculation Piping and Valves Table6.3-6 Safety Injection System Failure Mode Analysis High Pressure Safety Injection Table6.3-7 Administrative Error Analysis-Safety Injection System Valves Table6.3-8 Failure Modes and Effects Analysis for Boron Precipitation Control Table6.4-1 Containment Spray System Component Design Parameters Table6.4-2 Containment Spray System Failure Mode Analysis Table6.5-1 Containment Air Recirculation and Cooling Units Materials of Construction Table6.5-2 Containment Air Recirculation and Cooling Units Performance Data Table6.5-3 Containment Air Recirculation and Cooling System Table6.6-1 Containment Post Accident Hydrogen Control Systems Component Description Table6.6-2 Deleted by FSARCR 04-MP2-018 Table6.6-3 Omitted Table6.6-4 Post-Incident Recirculation System Failure Mode Analysis Table6.7-1 Enclosure Building Filtration System Component Description Table6.7-2 Enclosure Building Filtration System Failure Mode Analysis
Revision 3906/30/21 MPS-2 FSAR LOT 7 of 19 List of Tables (Continued)
Number Title Table7.2-1 Reactor Trip and Pretrip Set Points Table 7.2.1.1-I Parameters Affecting Fuel Design Limit Table 7.2.1.1-II Pertinent NSSS parameters and Monitored Variables Table 7.2.1.1-III Trip Functions Table 7.2.1.1-IV Trip Variable Monitored Table 7.3.2.2-1 ESAS Failure Mode Analysis for Containment Pressure Channels Table7.4-1 Prohibits on CEAs Table7.5-1 Major Process Instrumentation Table7.5-2 Omitted Table7.5-3 Regulatory Guide 1.97 (Rev. 2) Accident Monitoring Instrumentation Table7.5-4 Area Radiation Monitors Table7.5-5 Liquid Process/Effluent Radiation Monitors Table7.5-6 Airborne Process/Effluent Radiation Monitors Table 7.5-6A Process Radiation Monitors (Steam)
Table7.5-7 CEA Position Light Matrix Table7.6-1 Major Equipment Normally Used for Hot Shutdown Table7.6-2 Major Equipment Normally Used for Cold Shutdown Table8.3-1 Diesel Fuel Oil System Mode Analysis Table8.3-2 A Emergency Diesel Generator Loading Table8.3-3 B Emergency Diesel Generator Loading Table8.5-1 Battery Service Profile for Batteries 201A and 201B Table8.7-1 Cable Characteristics Table8.7-2 Omitted
Revision 3906/30/21 MPS-2 FSAR LOT 8 of 19 List of Tables (Continued)
Number Title Table8.7-3 Omitted Table8.7-4 Facility Identification Table9.2-1 Chemical and Volume Control System Parameters Table9.2-2 Reactor Coolant and Demineralized Water Chemistry Table9.2-3 Regenerative Heat Exchanger Table9.2-4 Letdown Control Valves Table9.2-5 Letdown Heat Exchanger Table9.2-6 Ion Exchangers Table9.2-7 Letdown Filters Table9.2-8 Volume Control Tank Table9.2-9 Charging Pumps Table9.2-10 Concentrated Boric Acid Preparation and Storage Table9.2-11 Boric Acid Pumps and Strainers Table9.3-1 Shutdown Cooling Heat Exchangers Design Basis Parameters Table9.3-2 Shutdown Cooling System Design Parameters Table9.4-1 Reactor Building Closed Cooling Water System Components Table9.4-2 Reactor Building Closed Cooling Water System Failure Mode Analysis Table9.4-3 Minimum Required RBCCW Flow to Essential Safety-Related Loads LOCA Injection and Recirculation Operations Table9.5-1 Spent Fuel Pool Monitoring Equipment Table9.5-2 Components of Spent Fuel Pool Cooling System Table9.7-1 Circulating Water System Components Table9.7-2 Service Water System Components
Revision 3906/30/21 MPS-2 FSAR LOT 9 of 19 List of Tables (Continued)
Number Title Table9.7-3 Turbine Building Closed Cooling Water System Components Table9.7-4 Service Water Cooling System Table9.8-1 Transfer Tube Isolation Valve Table9.8-2 Spent Fuel Pool Platform Crane Table9.8-3 Spent Fuel Cask Crane Table9.8-4 Failure Mode Analysis Table9.8-5 Radiation Levels from Heated Junction Thermocouple (R/Hr)
Table9.9-1 Control Element Drive Mechanism Cooling System Table9.9-2 Containment and Enclosure Building Purge System Table9.9-3 Containment Auxiliary Circulation System Table9.9-4 Containment Penetration Cooling System Table9.9-5 Penetration Air Cooling Requirements Table9.9-6 Radwaste Ventilation System Table9.9-7 Nonradioactive Ventilation System Table9.9-8 Engineered Safety Features Room Air Recirculation System Table9.9-9 Fuel Handling Ventilation System Table9.9-10 Main Exhaust System Table9.9-11 Control Room Air Conditioning System Table9.9-12 Diesel Generator Ventilation Systems Table9.9-13 Turbine Building Ventilation System Table9.9-14 Access Control Area Air Conditioning System Table9.9-15 Balance of Unit Ventilation System
Revision 3906/30/21 MPS-2 FSAR LOT 10 of 19 List of Tables (Continued)
Number Title Table9.9-16 Engineered Safety Features Room Air Recirc. System Failure Mode Analysis Table9.9-17 Control Room Air Conditioning System Failure Mode Analysis Table9.9-18 Diesel Generator Ventilation System Failure Mode Analysis Table9.9-19 Vital Switchgear Ventilation System Component Description Table9.9-20 Auxiliary Chilled Water System Component Description Table9.9-21 Vital Chilled Water System Component Description Table9.9-22 Indoor Design Temperatures for Significant Plant Areas Table9.11-1 Compressed Air System Component Description Table9.11-2 Gas Receiver Tanks Safety Evaluation Table9.12-1 Water Treatment System Components Table10.1-1 Deleted Table10.2-1 Turbine Generator Component Description Table10.3-1 Major Components of Main Steam System Table10.3-2 Omitted Table10.3-3 Operating Details for Valve Systems Protecting Steam Generations of Overpressure Table10.4-1 Major Components of the Condensate and Feedwater System Table10.4-2 Failure Analysis of Steam Generator Blowdown System Components Table11.1-1 Radioactive Waste Processing System Component Description Table11.1-2 Sources and Expected Volumes of Solid Wastes Table11.1-3 Radioactivity levels of solid wastes (See Note)
Table11.1-4 Curie Inventory of Solid Waste Shipped from Millstone Unit 2 (See Note)
Revision 3906/30/21 MPS-2 FSAR LOT 11 of 19 List of Tables (Continued)
Number Title Table11.1-5 Assumptions for Waste Gas Decay Tank Accident Table11.2-1 Source Terms for Shielding Design Table11.A-1 Design-Basis and Expected Primary Coolant Activity Concentrations Table11.A-2 Calculated Reactor Core Activities Table11.A-3 Expected Annual Effluent Releases (Curies Per Year), by Radionuclide, from Each Release Point Table11.A-4 Expected Annual Liquid Effluent Activity Releases (Curies/Year), by Radionuclide, from Each Waste Stream Table11.A-5 Expected Annual Liquid Effluent Concentrations (Diluted and Undiluted),
by Radionuclide, from Each Waste System Table11.A-6 Design Basis Radionuclide Concentrations in Liquid Effluent, in Fractions of 10CFRPart 20 Concentration Limits Table11.A-7 Design-Basis Radionuclide Airborne Concentrations at the Site Boundary From All Gaseous Effluent Release Points Combined, in Fractions of 10CFRPart 20 Concentration Limits Table11.A-8 Total Annual Design-Basis and Expected Releases of Radioactive Liquid Waste to the Environment From All Sources Combined, in Curies Per Year Table11.A-9 Total Annual Design Basis and Expected Releases of Airborne Radioactive Waste to the Environment From All Release Points Combined, in Curies Per Year Table11.A-10 Basis for Reactor Coolant System Activity NUREG-0017 gale Code Input Table11.B-1 Inputs to PWR-GALE Code Table11.C-1 Comparison of Calculated Annual Maximum Individual Doses with 10CFRPart 50 AppendixI Design Objectives Table11.C-2 Annual Total Body and Thyroid Doses to the Population Within 50 Miles of the Millstone Site, In Man-Rem, From Expected Liquid and Airborne Effluent Releases
Revision 3906/30/21 MPS-2 FSAR LOT 12 of 19 List of Tables (Continued)
Number Title Table 11.D-1 Containment Building Airborne Concentrations Table 11.D-2 Auxiliary Building Airborne Concentrations Table 11.D-3 Turbine Building Airborne Concentrations Table13.12-1 Seismic Category I-ASME SectionIII Classes 1 and 2 Piping Systems Table14.0-1 Reactor Operating Modes For Millstone Unit 2 Table14.0-2 Disposition of Events Summary Table14.0.1-1 Accident Category Used For Each Analyzed Event Table14.0.2-1 Plant Operating Conditions Table14.0.2-2 Nominal Fuel Design Parameters Table14.0.3-1 Core Power Distribution (Table Deleted)
Table14.0.4-1 Range of Key Initial Condition Operating Parameters Table14.0.5-1 Reactivity Parameters (Table Deleted)
Table14.0.7-1 Analytical Trip Setpoints Table14.0.7-2 Uncertainties Applied at HFP Condition in Local Power Density Limiting Safety System Settings Calculations Table14.0.7-3 Uncertainties Applied at HFP Condition in the Thermal Margin/Low Pressure Limiting Safety System Settings Calculations Table14.0.7-4 Uncertainties Applied at HFP Condition in the Local Power Density Limiting Condition for Operation Calculations Table14.0.7-5 Uncertainties Applied in Departure from Nucleate Boiling Limiting Condition for Operation Calculations Table14.0.8-1 Component Capacities and Setpoints Table14.0.9-1 Overview of Plant Systems and Equipment Available for Transient and Accident Conditions Table14.0.12-1 Nomenclature Used in Plotted Results
Revision 3906/30/21 MPS-2 FSAR LOT 13 of 19 List of Tables (Continued)
Number Title Table14.1.1-1 Available Reactor Protection for the Decrease in Feedwater Temperature Event Table14.1.1-2 Disposition of Events for the Decrease in Feedwater Temperature Event Table14.1.2-1 Available Reactor Protection for the Increase in Feedwater Flow Event Table14.1.2-2 Disposition of Events for the Increase in Feedwater Flow Event Table14.1.3-1 Available Reactor Protection for the Increase in Steam Flow Event Table14.1.3-2 Disposition of Events for the Increase in Steam Flow Event Table14.1.3-3 Initial Conditions for the Increase in Steam Flow Event Table14.1.3-4 Event Summary for the Increase in Steam Flow Event Table14.1.3-5 Peak Reactor Power Levels for Increase in Steam Flow Event Table14.1.4-1 Available Reactor Protection for the Inadvertent Opening of a Steam Generator Relief or Safety Valves Table14.1.4-2 Disposition of Events for the Inadvertent Opening of a Steam Generator Relief or Safety Valve Event Table14.1.5.1-1 Available Reactor Protection for Steam System Piping Failures Inside and Outside of Containment Table14.1.5.1-2 Disposition of Events for Steam System Piping Failures Inside and Outside Containment Table14.1.5.1-3 S-RELAP5 Thermal-Hydraulic Input (Pre-Scram Steam Line Break)
Table14.1.5.1-4 Actuation Signals and Delays (Pre-Scram Steam Line Break)
Table14.1.5.1-5 S-RELAP5 Neutronics Input and Assumptions (Pre-Scram Steam Line Break)
Table14.1.5.1-6 MDNBR and Peak Reactor Power Level Summary (Pre-Scram Steam Line Break)
Table14.1.5.1-7 LHGR-Limiting Pre-Scram Steam Line Break Sequence of Events: HFP 0.20ft2 Asymmetric Break Inside Containment with Offsite Power Available
Revision 3906/30/21 MPS-2 FSAR LOT 14 of 19 List of Tables (Continued)
Number Title Table14.1.5.1-8 MDNBR-Limiting Pre-Scram Steam Line Break Sequence of Events: HFP 3.51ft2 Asymmetric Break Inside Containment with Loss of Offsite Power Table14.1.5.2-1 Available Reactor Protection for Steam System Piping Failures Inside and Outside of Containment, Post-Scram Analysis Table14.1.5.2-2 Disposition of Events for Steam System Piping Failures Inside and Outside of Containment, Post-Scram Analysis Table14.1.5.2-3 SRELAP5 -Thermal-Hydraulic Input (Post-Scram Steam Line Break)
Table14.1.5.2-4 Actuation Signals and Delays (Post-Scram Steam Line Break)
Table14.1.5.2-5 S-RELAP5 Neutronics Input and Assumptions (Post-Scram Steam Line Break)
Table14.1.5.2-6 Post-Scram Steam Line Break Analysis Summary Table14.1.5.2-7 LHGR-Limiting Sequence of Events - HZP Offsite Power Available Table14.1.5.2-8 MDNBR-Limiting Post-Scram Steam Line Break Analysis Summary Table14.1.5.3-1 Assumptions Used in Main Steam Line Break Analysis Table14.1.5.3-2 Summary of Millstone 2 MSLB Accident Doses Table14.1.5.3-3 Deleted by FSARCR PKG FSC 07-MP2-006 Table14.2.1-1 Available Reactor for the Loss of External Load Event Table14.2.1-2 Disposition of Events for the Loss of External Load Event Table14.2.1-3 Event Summary for the Loss of External Load Event (Primary Overpressurization Case)
Table14.2.1-4 Event Summary for the Loss of External Load Event (Secondary Overpressurization Case)
Table14.2.1-5 Event Summary for the Loss of External Load Event (Minimum Departure from Nucleate Boiling Ratio Case)
Table14.2.2-1 Available Reactor Protection for the Turbine Trip Event Table14.2.2-2 Disposition of Events for the Turbine Trip Event
Revision 3906/30/21 MPS-2 FSAR LOT 15 of 19 List of Tables (Continued)
Number Title Table14.2.4-1 Available Reactor Protection for the Closure of the Main Steam Isolation Valves Events Table14.2.4-2 Disposition of Events for the Closure of the Main Steam Isolation Valves Events Table14.2.4-3 Event Summary for the Main Steam Isolation Valve Closure Event (Lower Steam Flow Case)
Table14.2.7-1 Available Reactor Protection for the Loss of Normal Feedwater Flow Event Table14.2.7-2 Disposition of Events for the Loss of Normal Feedwater Flow Event Table14.2.7-3 Sequence of Events for Minimum Steam Generator Inventory Case: One Motor-Driven AFW Pump Fails to Start with Offsite Power and Steam Dumps Table14.2.7-4 Sequence of Events for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start Table14.3.1-1 Available Reactor Protection for the Loss of Forced Reactor Coolant Flow Event Table14.3.1-2 Disposition of Events for the Loss of Forced Reactor Coolant Flow Event Table14.3.1-3 Event Summary for the Loss of Forced Reactor Coolant Flow Table14.3.3-1 Available Reactor Protection for the Reactor Coolant Pump Rotor Seizure Event Table14.3.3-2 Disposition of Events for the Reactor Coolant Pump Rotor Seizure Event Table14.3.3-3 Event Summary for the Reactor Coolant Pump Rotor Seizure Table14.4.1-1 Available Reactor Protection for the Uncontrolled Control Rod/Bank Withdrawal from a Subcritical or Low-Power Startup Condition Event Table14.4.1-2 Disposition of Events for the Uncontrolled Control Rod/Bank Withdrawal from a Subcritical or Low-Power Startup Condition Event Table14.4.1-3 Event Summary for the Uncontrolled Bank Withdrawal from Low-Power Event
Revision 3906/30/21 MPS-2 FSAR LOT 16 of 19 List of Tables (Continued)
Number Title Table14.4.2-1 Available Reactor Protection for the Uncontrolled Control Rod/Bank Withdrawal at Power Event Table14.4.2-2 Disposition of Events for the Uncontrolled Control Rod/Bank Withdrawal at Power Event Table14.4.2-3 Event Summary for the Uncontrolled Rod/Bank Withdrawal Event for the Limiting 100% Power Case Table14.4.3.1-1 Available Reactor Protection for the Dropped Control Rod/Bank Event Table14.4.3.1-2 Disposition of Events for the Dropped Control Rod/Bank Event Table14.4.3.1-3 Event Summary for the Limiting Dropped Control Rod/Bank Case Table14.4.3.5-1 Available Reactor Protection for the Single Control Rod Withdrawal Event Table14.4.3.5-2 Disposition of Events for the Single Control Rod Withdrawal Event Table14.4.4-1 Available Reactor Protection Table14.4.4-2 Disposition of Events for the Startup of an Inactive Loop Event Table14.4.6-1 Available Reactor Protection for Chemical and Volume Control System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant Event Table14.4.6-2 Disposition of Events for the Chemical and Volume Control System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant Event Table14.4.6-3 Summary of Results for the Boron Dilution Event Asymmetric Dilution Front Model Table14.4.6-4 Summary of Results for the Boron Dilution Event Instantaneous Mixing Mode Table14.4.8-1 Available Reactor Protection for the Spectrum of Control Rod Ejection Accidents Table14.4.8-2 Disposition of Events for the Spectrum of Control Rod Ejection Accidents Table14.4.8-3 Event Summary for a Control Rod Ejection (Maximum Pressurization Case)
Revision 3906/30/21 MPS-2 FSAR LOT 17 of 19 List of Tables (Continued)
Number Title Table14.4.8-4 Event Summary for a Control Rod Ejection Minimum Departure from Nucleate Boiling Ratio Case Table14.4.8-5 dnBounding Beginning of Cycle/End of Cycle Ejected Rod Analysis Table14.4.8-6 CREA Radiological Analysis Assumptions Table14.4.8-7 Radiological Consequences of a CREA Table14.6.1-1 Available Reactor Protection for the Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve Event Table14.6.1-2 Disposition of Events for the Inadvertent Opening of a Pressurized Water Reactor Pressurizer Relief Valve Event Table14.6.1-3 Event Summary for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve Table14.6.3-1 Available Reactor Protection for the Radiological Consequences of Steam Generator Tube Rupture Event Table14.6.3-2 Disposition of Events for the Radiological Consequences of Steam Generator Tube Rupture Event Table14.6.3-3 Sequence of Events for the Steam Generator Tube Rupture Event Table14.6.3-4 Mass Releases for the Steam Generator Tube Rupture Accident Table14.6.3-5 Assumptions for the Radiological Evaluation for the Steam Generator Tube Rupture Event Table14.6.3-6 Summary - Radiological Consequences of the Steam Generator Tube Rupture Event Table14.6.5.1-1 Available Reactor Protection for the Large Break Loss of Coolant Accident Table14.6.5.1-2 Disposition of Events for the Large Break Loss of Coolant Accident Table14.6.5.1-3 Millstone Unit 2 Realistic Large Break Loss of Coolant Accident Analysis
- Plant Parameter Values and Ranges Table14.6.5.1-4 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis -
Statistical Distribution Used for Process Parameters
Revision 3906/30/21 MPS-2 FSAR LOT 18 of 19 List of Tables (Continued)
Number Title Table14.6.5.1-5 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis - Passive Heat Sinks and Material Properties In Containment Geometry Table14.6.5.1-6 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis -
Compliance with 10 CFR 50.46(b)
Table14.6.5.1-7 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis -
Summary of Major Parameters for the Demonstration Case Table14.6.5.1-8 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis -
Calculated Event Times for the Demonstration Case*
Table14.6.5.2-1 Available Reactor Protection for the Small Break Loss of Coolant Accident Table14.6.5.2-2 Disposition of Events for the Small Break Loss of Coolant Accident Table14.6.5.2-3 Millstone Unit 2 Small Break Loss of Coolant Accident System Analysis Parameters Table14.6.5.2-4 Deleted by FSCR MPS-UCR-2016-016 Table14.6.5.2-5 Calculated Event Times for Small Break Loss-of-Coolant Accident Table14.6.5.2-6 Analysis Results for Small Break Loss-of-Coolant Accident Table14.6.5.2-7 Peak Clad Temperature Including All Penalties and Benefits - Small Break LOCA Table14.6.5.3-1 Core and System Parameters Used in the LTC Analysis Table14.6.5.4-1 Available Reactor Protection for the Large Break Loss of Coolant Accident Table14.6.5.4-2 Disposition of Events for the Large Break Loss of Coolant Accident Table14.6.5.4-3 Millstone Unit 2 System Analysis Parameters (Large Break Loss of Coolant Accident Analysis)
Table14.6.5.4-4 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis Table14.6.5.4-5 Millstone Unit 2 Large Break LOCA Analysis Table14.6.5.4-6 Millstone Unit 2 Large Break LOCA Analysis
Revision 3906/30/21 MPS-2 FSAR LOT 19 of 19 List of Tables (Continued)
Number Title Table14.6.5.4-7 Peak Clad Temperature Including All Penalties and Benefits - Large Break LOCA Table14.7.1-1 Deleted by FSARCR PKG FSC 07-MP2-006 Table14.7.4-1 Assumption for Fuel Handling Accident in the Spent Fuel Pool Table14.7.4-2 Assumption for Fuel Handling Accident in Containment Table14.7.4-3 Deleted by FSARCR 02-MP2-015 Table14.7.5-1 Assumptions for Spent Fuel Cask Tip Accident Table14.8.2-1 Containment Design Parameters Table14.8.2-2 Initial Conditions for Pressure Analyses Table14.8.2-3 Minimum Containment Heat Sink Data Table14.8.2-4 Sequence of Events, MP2-MSLB: Loss of Offsite Power and the Failure of Vital Bus VA-10 or VA-20 from 102% Power Table14.8.2-5 Engineered Safety Features Performance for MSLB Containment Analysis Table14.8.4-1 Loss of Coolant Accident (Off site Assumptions)
Table14.8.4-2 Summary of Doses for Loss of Coolant Accident Table14.8.4-3 Loss of Coolant Accident (Control Room Assumptions)
Table14.8.4-4 Atmospheric Dispersion Data for Millstone Unit 2 Control Room Table14.8.4-5 Dose to Millstone Unit 2 Control Room Operators Table15.3-1 Containment Tendon Prestress Table15.6-1 License Renewal Commitments
Revision 3906/30/21 MPS-2 FSAR Page 1 of 47 LIST OF EFFECTIVE FIGURES Figure Number Figure Label Title Drawing Number Sheet 1.2-1 FIGURE 1.2-1 Site Layout N/A 1.2-2 FIGURE 1.2-2 Plot Plan 25203-10003 (a) 1.2-3 FIGURE 1.2-3 General Arrangement, Turbine Building Plan at Operating Floor Elevation 54 Feet 6 Inches 25203-27011 (a) 1.2-5 FIGURE 1.2-5 General Arrangement, Turbine Building Plan at Ground Floor Elevation 14 Feet 6 Inches 25203-27012 (a) 1.2-5 FIGURE 1.2-5 General Arrangement, Turbine Building Plan at Ground Floor Elevation 14 Feet 6 Inches 25203-27013 (a) 1.2-6 FIGURE 1.2-6 General Arrangement Containment Plan at Floor Elevation 14 feet 6 inches and Elevation 36 feet 6 inches 25203-27014 (a) 1.2-7 FIGURE 1.2-7 General Arrangement Auxiliary Building Plan at Elevation 36 feet 6 inches and Elevation 38 feet 6 inches 25203-27015 (a) 1.2-8 FIGURE 1.2-8 General Arrangement Auxiliary Building Sections G-G and H-H 25203-27016 (a) 1.2-9 FIGURE 1.2-9 General Arrangement Auxiliary Building Ground Floor Elevation 14 feet 6 inches and Cable Vault Elevation 25 feet 6 inches 25203-27017 (a) 1.2-10 FIGURE 1.2-10 General Arrangement Containment and Auxiliary Building Plan at Elevation (-)5 feet 0 inches and Elevation (-)3 feet 6 inches 25203-27018 (a) 1.2-11 FIGURE 1.2-11 General Arrangement Containment and Auxiliary Building Plan at Elevation (-)25 feet 6 inches and Elevation (-)22 feet 6 inches 25203-27019 (a) 1.2-12 FIGURE 1.2-12 General Arrangement Containment and Auxiliary Building Plan at Elevation (-)45 feet 6 inches 25203-27020 (a) 1.2-13 FIGURE 1.2-13 General Arrangement Containment and Auxiliary Building Section A-A 25203-27021 (a)
Revision 3906/30/21 MPS-2 FSAR Page 2 of 47 1.2-14 FIGURE 1.2-14 General Arrangement Containment and Auxiliary Building Section B-B 25203-27022 (a) 1.2-15 FIGURE 1.2-15 General Arrangement Turbine Building Sections C-C and E-E 25203-27023 (a) 1.2-16 FIGURE 1.2-16 General Arrangement Turbine Building Sections D-D and F-F 25203-27024 (a) 1.2-17 FIGURE 1.2-17 General Arrangement Intake Structure Auxiliary Steam Boiler Room Plan and Section 25203-27025 (a) 2.4-1 FIGURE 2.4-1 Geological Features N/A 2.4-2a FIGURE 2.4-2a Boring Plan N/A 2.4-2b FIGURE 2.4-2b Test Borings N/A 2.4-2c FIGURE 2.4-2c Boring Logs N/A 2.4-2d FIGURE 2.4-2d Boring Logs N/A 2.4-3 FIGURE 2.4-3 Seismic Line Location Map N/A 2.4-4 FIGURE 2.4-4 Seismic Profiles N/A 2.5-1 FIGURE 2.5-1 Topography in the Vicinity of Millstone Point N/A 2.5-2 FIGURE 2.5-2 Bore Hole and Test Pit Locations N/A 2.5-3 FIGURE 2.5-3 Test Pit Number 1 N/A 2.5-4 FIGURE 2.5-4 Test Pit Number 2 N/A 2.5-5 FIGURE 2.5-5 Relationship Between Hurricane Wind Direction and Plant Layout N/A 2.5-6 FIGURE 2.5-6 Section Through Plant N/A 2.5-7 FIGURE 2.5-7 Profiles of Plant N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 3 of 47 2.5-8 FIGURE 2.5-8 Surge Hydrograph for PMH N/A 2.5-9 FIGURE 2.5-9 Bottom Profile for Surge Traverse Line N/A 2.5-10 FIGURE 2.5-10 Storm Tracker for Probable Maximum Hurricane N/A 2.5-11 FIGURE 2.5-11 Location of the Center of the Storm Within the Critical Area N/A 2.5-12 FIGURE 2.5-12 Shore Protection N/A 2.5-13 FIGURE 2.5-13 Shore Protection N/A 2.5-14 FIGURE 2.5-14 Wave Force Diagrams For The Three Zones And Their Corresponding Bottom Profiles Near The Walls N/A 2.5-15 FIGURE 2.5-15 Typical Anchorage Detail N/A 2.5-16 FIGURE 2.5-16 Filter System and the Gradation of the Filter Materials N/A 2.5-17 FIGURE 2.5-17 Scour Protection N/A 2.5-18 FIGURE 2.5-18 Flood Protection N/A 2.5-19 FIGURE 2.5-19 General Roof Plan N/A 2.5-20 FIGURE 2.5-20 Drainage Plan N/A 2.5-21 FIGURE 2.5-21 Turbine and Auxiliary Building Plans at Elevation 14 Feet 6 Inches N/A 2.5-22 FIGURE 2.5-22 Auxiliary Building Basement Plans N/A 2.5-23 FIGURE 2.5-23 Intake Structure N/A 2.5-24 FIGURE 2.5-24 Louver Protection - Intake Structure N/A 2.7-1 FIGURE 2.7-1 Excavation Plan N/A 2.7-2 FIGURE 2.7-2 Backfill and Compaction Requirements N/A 3.1-1 FIGURE 3.1-1 Reactor Vertical Arrangement N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 4 of 47 3.1-2 FIGURE 3.1-2 Reactor Core Cross Section N/A 3.3-1A FIGURE 3.3-1A Fuel Rod Assembly (Batch DD and Prior)
N/A 3.3-2A FIGURE 3.3-2A AREVA - Reload Fuel Assembly Batch S and Prior N/A 3.3-2B FIGURE 3.3-2B AREVA - Reload Fuel Assembly Batch T and Later N/A 3.3-3A FIGURE 3.3-3A AREVA - Reload Fuel Assembly Components Batch S and Prior N/A 3.3-3B FIGURE 3.3-3B AREVA - Reload Fuel Assembly Components Batch T and Later N/A 3.3-4A FIGURE 3.3-4A Bi-Metallic Fuel Spacer Assembly N/A 3.3-4B FIGURE 3.3-4B HTP Fuel Space Assembly N/A 3.3-5 FIGURE 3.3-5 Fuel Assembly Hold Down Device N/A 3.3-6 FIGURE 3.3-6 Control Element Assembly N/A 3.3-7 FIGURE 3.3-7 Control Element Assembly Materials N/A 3.3-8 FIGURE 3.3-8 Control Element Assemblies Group and Number Designation N/A 3.3-9 FIGURE 3.3-9 Core Orientation N/A 3.3-11 FIGURE 3.3-11 Reactor Internals Assembly N/A 3.3-12 FIGURE 3.3-12 Pressure Vessel-Core Support Barrel Snubber Assembly N/A 3.3-13 FIGURE 3.3-13 Core Shroud Assembly N/A 3.3-14 FIGURE 3.3-14 Upper Guide Structure Assembly N/A 3.3-15 FIGURE 3.3-15 Control Element Drive Mechanism (Magnetic Jack)
N/A 3.3-16 FIGURE 3.3-16 (Left Blank Intentionally)
N/A 3.3-17 FIGURE 3.3-17 Heated Junction Thermocouple Probe Pressure Boundary Installation N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 5 of 47 3.3-18 FIGURE 3.3-18 Typical Heated Junction Thermocouple Probe Assembly Installation N/A 3.3-19 FIGURE 3.3-19 Placement of Natural Uranium Replacement Fuel Rods and Fuel Assembly Orientation Relative to the Core Baffle for Cycle 19 N/A 3.4-1 FIGURE 3.4-1 Representative Full Core Loading Pattern N/A 3.4-2 FIGURE 3.4-2 Representative Quarter Core Loading Pattern N/A 3.4-3 FIGURE 3.4-3 Representative BOC and EOC Exposure Distribution N/A 3.4-4 FIGURE 3.4-4 Representative Boron Letdown, HFP, ARO N/A 3.4-5 FIGURE 3.4-5 Representative Normalized Power Distributions, Hot Full Power, Equilibrium Xenon, 150 MWD/MTU N/A 3.4-6 FIGURE 3.4-6 Representative Normalized Power Distribution, Hot Full Power, Equilibrium Xenon, 18,020 MWD/MTU N/A 3.A-1 FIGURE 3.A-1 Representative Node Locations - Horizontal Mathematical Model N/A 3.A-2 FIGURE 3.A-2 Mathematical Model - Horizontal Seismic Analysis N/A 3.A-3 FIGURE 3.A-3 Mathematical Model - Vertical Seismic Analysis N/A 3.A-4 FIGURE 3.A-4 Core Support Barrel Upper Flange - Finite Element Model N/A 3.A-5 FIGURE 3.A-5 Core Support Barrel Lower Flange - Finite Element Model N/A 3.A-6 FIGURE 3.A-6 Lateral Seismic Model - Mode 1, 3.065 CPS N/A 3.A-7 FIGURE 3.A-7 Lateral Seismic Model - Mode 2, 5.118 CPS N/A 3.A-8 FIGURE 3.A-8 Lateral Seismic Model - Mode 2, 5.118 CPS N/A 3.A-9 FIGURE 3.A-9 Reactor Vessel Flange Vertical Response Spectrum (1%
Damping)
N/A 3.A-10 FIGURE 3.A-10 ASHSD Finite Element Model of the Core Support Barrel/
Thermal Shield System N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 6 of 47 3.A-11 FIGURE 3.A-11 Vertical Shock Model N/A 3.A-12 FIGURE 3.A-12 Lateral Shock Mode N/A 3.A-13 FIGURE 3.A-13 SAMMSOR DYNASOR Finite Element Model of Core Support Barrel N/A 4.1-1 FIGURE 4.1-1 P&ID for Reactor Coolant System & Pump (Sheet 1) 25203-26014 (a)
Sheet 1 of 3 4.1-1 FIGURE 4.1-1 P&ID for Reactor Coolant System & Pump (Sheet 2) 25203-26014 (a)
Sheet 2 of 3 4.1-1 FIGURE 4.1-1 P&ID for Reactor Coolant System & Pump (Sheets 3) 25203-26014 (a)
Sheet 3 of 3 4.1-2 FIGURE 4.1-2 Reactor Coolant System Arrangement-Elevation N/A 4.1-3 FIGURE 4.1-3 Reactor Coolant System Arrangement-Plan N/A 4.3-1 FIGURE 4.3-1 Reactor Vessel N/A 4.3-2 FIGURE 4.3-2 Steam Generator N/A 4.3-3 FIGURE 4.3-3 Reactor Coolant Pump N/A 4.3-4 FIGURE 4.3-4 P&ID Reactor Coolant Pump 25203-26014 (a)
Sheet 3 of 3 4.3-5 FIGURE 4.3-5 Reactor Coolant Pump Seal Area N/A 4.3-6 FIGURE 4.3-6 Reactor Coolant Pump Predicted Performance N/A 4.3-7 FIGURE 4.3-7 Pressurizer N/A 4.3-8 FIGURE 4.3-8 Temperature Control Program N/A 4.3-9 FIGURE 4.3-9 Pressurizer Level Setpoint Program N/A 4.3-10 FIGURE 4.3-10 Pressurizer Level Control Program N/A 4.3-11 FIGURE 4.3-11 Quench Tank N/A 4.3-12 FIGURE 4.3-12 Permanent Reactor Cavity Seal Plate N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 7 of 47 4.5-1 FIGURE 4.5-1 Reactor Coolant System Pressure Temperature Limitations for 7 Full Power Years N/A 4.5-2 FIGURE 4.5-2 Reactor Coolant System Pressure - Temp Limitations During Plant Heatup/Cooldown After 7 Years Integrated Neutron Flux N/A 4.5-3 FIGURE 4.5-3 Reactor Coolant System Pressure Temperature Limitations For 0 to 2 Years of Full Power N/A 4.5-4 FIGURE 4.5-4 Reactor Coolant System Heatup Limitations for 54 EFPY N/A 4.5-5 FIGURE 4.5-5 Reactor Coolant System Cooldown Limitations for 54 EFPY N/A 4.6-1 FIGURE 4.6-1 Location of Surveillance Capsule Assemblies N/A 4.6-2 FIGURE 4.6-2 Typical Surveillance Capsule Assembly N/A 4.6-3 FIGURE 4.6-3 Typical Charpy Impact Compartment Assembly N/A 4.6-4 FIGURE 4.6-4 Typical Tensile-Monitor Compartment Assembly N/A 4.6-5 FIGURE 4.6-5 Base Metal - WR (Transverse) Plate C-506-1 Impact Energy vs Temperature N/A 4.6-6 FIGURE 4.6-6 Base Metal - WR (Transverse) Plate C-506-1 Lateral Expansion versus Temperature N/A 4.6-7 FIGURE 4.6-7 Base Metal - RW (Longitudinal) Plate C-506-1 Impact Energy versus Temperature N/A 4.6-8 FIGURE 4.6-8 Base Metal - RW (Longitudinal) Plate C-506-1 Lateral Expansion vs Temperature N/A 4.6-9 FIGURE 4.6-9 Weld Metal Plate C-506-2/C-506-3 Impact Energy vs Temperature N/A 4.6-10 FIGURE 4.6-10 Weld Metal, Plate C-506-2/C-506-3 Lateral Expansion vs Temperature N/A 4.6-11 FIGURE 4.6-11 HAZ Metal, Plate C-506-1 Impact Energy versus Temperature N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 8 of 47 4.6-12 FIGURE 4.6-12 HAZ Metal, Plate C-506-1 Lateral Expansion versus Temperature N/A 4.6-13 FIGURE 4.6-13 SRM (HSST Plate 01MY - Longitudinal) Impact Energy versus Temperature N/A 4.6-14 FIGURE 4.6-14 SRM (HSST Plate 01MY - Longitudinal) Lateral Expansion versus Temperature N/A 4.A-1 FIGURE 4.A-1 Reactor Coolant System Seismic Analysis Model MS2 N/A 4.A-1A FIGURE 4.A-1A Reactor Coolant System - Seismic Analysis Model MS2 and RV14 N/A 4.A-2 FIGURE 4.A-2 RV14 Reactor and Internals Seismic Analysis Model N/A 4.A-3 FIGURE 4.A-3 Pressurizer Seismic Analysis Model N/A 4.A-4 FIGURE 4.A-4 Surge Line Seismic Analysis Model N/A 5.2-1 FIGURE 5.2-1 Containment Structure Details N/A 5.2-2 FIGURE 5.2-2 Containment Structure Details N/A 5.2-3 FIGURE 5.2-3 Design Thermal Gradient N/A 5.2-4 FIGURE 5.2-4 Equipment Hatch Details N/A 5.2-5 FIGURE 5.2-5 Personnel Lock Details N/A 5.2-6 FIGURE 5.2-6 Liner Plate N/A 5.2-7 FIGURE 5.2-7 Leak Chase Channels N/A 5.2-8 FIGURE 5.2-8 Typical Penetrations N/A 5.2-9 FIGURE 5.2-9 Bracket Details N/A 5.2-10 FIGURE 5.2-10 Liner Plate Details N/A 5.2-11 FIGURE 5.2-11 Reactor Vessel Support Details N/A 5.2-12 FIGURE 5.2-12 Lower Steam Generator Support Details N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 9 of 47 5.2-13 FIGURE 5.2-13 Upper Steam Generator Support Details N/A 5.2-14 FIGURE 5.2-14 Primary and Secondary Shield Wall N/A 5.2-15 FIGURE 5.2-15 Detail - Seismic Restraint N/A 5.2-16 FIGURE 5.2-16 Finite Element Mesh of Bottom of Containment Shell N/A 5.2-17 FIGURE 5.2-17 Finite Element Mesh of Top of Containment Shell N/A 5.2-18 FIGURE 5.2-18 Finite Element Mesh of Containment Shell for Stressing Sequence N/A 5.2-19 FIGURE 5.2-19 Containment Structure Stress Analysis Summary, Dead Load and Initial Prestress, Live Load N/A 5.2-20 FIGURE 5.2-20 Containment Structure Stress Analysis Summary, Dead Load, Live Load, Prestress and Test Pressure N/A 5.2-21 FIGURE 5.2-21 Containment Structure Stress Analysis Summary, Dead Load, Live Load, Prestress, Operating Temperature and DBE N/A 5.2-22 FIGURE 5.2-22 Containment Structure Stress Analysis Summary, Dead Load, Live Load, Prestress, 100% Accident Pressure and Accident Temperature N/A 5.2-23 FIGURE 5.2-23 Containment Structure Stress Analysis Summary, Dead Load, Prestress, Operating Temperature, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE N/A 5.2-24 FIGURE 5.2-24 Containment Structure Stress Analysis Summary, Dead Load, Prestress, 100% Accident Pressure, Thermal Expansion Forces of Pipes, Accident Temperature and DBE N/A 5.2-25 FIGURE 5.2-25 Containment Structure Stress Analysis Summary, Dead Load, Prestress, 125% Accident Pressure, 125% Thermal Expansion Forces of Pipes, Accident Temperature and 125% OBE N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 10 of 47 5.2-26 FIGURE 5.2-26 Containment and Structure Stress Analysis Summary, Dead Load, Prestress, 150% Accident Pressure and Accident Temperature N/A 5.2-27 FIGURE 5.2-27 Isolation Valve Arrangements N/A 5.2-28 FIGURE 5.2-28 Isolation Valve Arrangements N/A 5.2-29 FIGURE 5.2-29 Isolation Valve Arrangements N/A 5.2-30 FIGURE 5.2-30 Isolation Valve Arrangements N/A 5.2-31 FIGURE 5.2-31 Isolation Valve Arrangements N/A 5.2-32 FIGURE 5.2-32 Isolation Valve Arrangements N/A 5.2-33 FIGURE 5.2-33 Isolation Valve Arrangements N/A 5.2-34 FIGURE 5.2-34 Isolation Valve Arrangements N/A 5.2-35 FIGURE 5.2-35 Reactor Coolant System Plan N/A 5.2-36 FIGURE 5.2-36 Reactor Coolant System Elevation N/A 5.2-37 FIGURE 5.2-37 Deleted by FSARCR 04-MP2-016 N/A 5.3-1 FIGURE 5.3-1 Enclosure Building N/A 5.3-2 FIGURE 5.3-2 Enclosure Building Layout N/A 5.3-3 FIGURE 5.3-3 Waterproof Membrane Details N/A 5.3-4 FIGURE 5.3-4 Waterproof Membrane Details N/A 5.3-5 FIGURE 5.3-5 Spent Fuel Cask Travel Limits N/A 5.4-1 FIGURE 5.4-1 Probable Missile Trajectories Inside Auxiliary Building N/A 5.4-2 FIGURE 5.4-2 Missile Resistant Siding Detail N/A 5.4-3 FIGURE 5.4-3 Location of Missile Resistant Siding N/A 5.5-1 FIGURE 5.5-1 Joint Detail at Turbine Pedestal N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 11 of 47 5.5-2 FIGURE 5.5-2 Joint Detail at Col. Line E N/A 5.6-1 FIGURE 5.6-1 Intake Structure Layout N/A 5.6-2 FIGURE 5.6-2 C. W. System - Plan N/A 5.8-1 FIGURE 5.8-1 Recommended Damped Response Spectra 9%g Acceleration, Operating Basis Earthquake N/A 5.8-2 FIGURE 5.8-2 Recommended Damped Response Spectra 17%g Acceleration, Design Basis Earthquake N/A 5.8-3 FIGURE 5.8-3 Recommended Damped Response Spectra 9%g Acceleration, Operating Basis Earthquake (Soil Surface)
N/A 5.8-4 FIGURE 5.8-4 Recommended Damped Response Spectra, 17%g Acceleration, Design Basis Earthquake (Soil Surface)
N/A 5.8-5 FIGURE 5.8-5 Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Critical Damping = 0.5%)
N/A 5.8-6 FIGURE 5.8-6 Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Critical Damping = 1%)
N/A 5.8-7 FIGURE 5.8-7 Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Critical Damping = 2%)
N/A 5.8-8 FIGURE 5.8-8 Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Critical Damping = 5%)
N/A 5.8-9 FIGURE 5.8-9 Response Spectra from the Time History Design Earthquake with Various Frequency Intervals N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 12 of 47 5.8-10 FIGURE 5.8-10 Comparison of Response Spectra with 1952 Taft and 1940 El Centro Earthquake N/A 5.8-11 FIGURE 5.8-11 Foundation Outline N/A 5.8-12 FIGURE 5.8-12 Sections A-A & B-B N/A 5.8-13 FIGURE 5.8-13 Auxiliary Bay of Turbine Building N/A 5.8-14 FIGURE 5.8-14 Containment Mass Model N/A 5.8-15 FIGURE 5.8-15 Mode Shapes for the Containment Building N/A 5.8-16 FIGURE 5.8-16 Containment Building Design Earthquake 9% Ground Acceleration N/A 5.8-17 FIGURE 5.8-17 Containment Building Design Earthquake 17% Ground Acceleration N/A 5.8-18 FIGURE 5.8-18 Containment Structure Elevation 53 feet 0 inches N/A 5.8-19 FIGURE 5.8-19 Containment Structure Elevation 97 feet 0 inches N/A 5.8-20 FIGURE 5.8-20 Containment Structure Elevation 152 feet 6 inches N/A 5.8-21 FIGURE 5.8-21 Containment Internals Model N/A 5.8-22 FIGURE 5.8-22 Mode Shapes & Frequencies Containment Internals - North-South N/A 5.8-23 FIGURE 5.8-23 Mode Shapes & Frequencies Containment Internals - North-South OBE (DBE)
N/A 5.8-24 FIGURE 5.8-24 Mode Shapes & Frequencies Containment Internals - East-West N/A 5.8-25 FIGURE 5.8-25 Containment Internals - East-West OBE (DBE)
N/A 5.8-26 FIGURE 5.8-26 Containment Internals Elevation 0 feet 0 inches - OBE (North-South) Reactor Vessel Support N/A 5.8-27 FIGURE 5.8-27 Containment Internals Elevation 0 feet 0 inches - OBE (East-West) Reactor Vessel Support N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 13 of 47 5.8-28 FIGURE 5.8-28 Containment Internals Elevation 14 feet 6 inches - OBE (North-South) Pressurizer Support N/A 5.8-29 FIGURE 5.8-29 Containment Internals Elevation 14 feet 6 inches - OBE (East-West) Pressurizer Support N/A 5.8-30 FIGURE 5.8-30 Containment Internals Elevation 38 feet 6 inches - OBE (North-South) Safety Injection Tank Support N/A 5.8-31 FIGURE 5.8-31 Containment Internals Elevation 38 feet 6 inches - OBE (East-West) Safety Injection Tank Support N/A 5.8-32 FIGURE 5.8-32 Containment Internals Elevation 43 feet 0 inches - OBE (North-South) Steam Generator Upper Support (Snubbers)
N/A 5.8-33 FIGURE 5.8-33 Containment Internals Elevation 43 feet 0 inches - OBE (East-West) Steam Generator Upper Support (Snubbers)
N/A 5.8-34 FIGURE 5.8-34 Containment Internals Elevation 50 feet 0 inches - OBE (North-South) Steam Generator Upper Support (Shear Keys)
N/A 5.8-35 FIGURE 5.8-35 Containment Internals Elevation 50 feet 0 inches - OBE (East-West) Steam Generator Upper Support (Shear Keys)
N/A 5.8-36 FIGURE 5.8-36 Containment Internals Elevation0 feet 0 inches - OBE (North-South) Steam Generator Lower Support N/A 5.8-37 FIGURE 5.8-37 Containment Internals Elevation 0 feet 0 inches - OBE (East-West) Steam Generator Lower Support N/A 5.8-38 FIGURE 5.8-38 Auxiliary Building Model N/A 5.8-39 FIGURE 5.8-39 Mode Shapes & Frequencies Auxiliary Building - North-South N/A 5.8-40 FIGURE 5.8-40 Auxiliary Building - North-South OBE (DBE)
N/A 5.8-41 FIGURE 5.8-41 Mode Shapes & Frequencies Auxiliary Building - East-West N/A 5.8-42 FIGURE 5.8-42 Auxiliary Building - East-West OBE (DBE)
N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 14 of 47 5.8-43 FIGURE 5.8-43 Auxiliary Building Elevation 14 feet 6 inches N/A 5.8-44 FIGURE 5.8-44 Auxiliary Building Elevation 38 feet 6 inches N/A 5.8-45 FIGURE 5.8-45 Auxiliary Building Elevation 71 feet 6 inches N/A 5.8-46 FIGURE 5.8-46 Warehouse Model N/A 5.8-47 FIGURE 5.8-47 Mode Shapes & Frequencies Warehouse Bldg. - East-West N/A 5.8-48 FIGURE 5.8-48 Mode Shapes & Frequencies Warehouse Bldg. - North-South N/A 5.8-49 FIGURE 5.8-49 Warehouse Bldg. - OBE (DBE)
N/A 5.8-50 FIGURE 5.8-50 Warehouse Elevation 38 feet 6 inches N/A 5.8-51 FIGURE 5.8-51 Turbine Building Model N/A 5.8-52 FIGURE 5.8-52 Mode Shapes & Frequencies Turbine Bldg. - North-South N/A 5.8-53 FIGURE 5.8-53 Turbine Bldg. OBE (DBE) East-West N/A 5.8-54 FIGURE 5.8-54 Mode Shapes & Frequencies Turbine Bldg. - East-West N/A 5.8-55 FIGURE 5.8-55 Turbine Bldg. OBE (DBE) North-South N/A 5.8-56 FIGURE 5.8-56 Turbine Building Elevation 31 feet 6 inches N/A 5.8-57 FIGURE 5.8-57 Turbine Building Crane - OBE N/A 5.8-58 FIGURE 5.8-58 Intake Structure Model N/A 5.8-59 FIGURE 5.8-59 Intake Structure OBE (DBE)
N/A 5.8-60 FIGURE 5.8-60 Mode Shapes & Frequencies Intake Structure N/A 5.8-61 FIGURE 5.8-61 Intake Structure Elevation 14 feet 0 inches OBE N/A 5.A-1 FIGURE 5.A-1 Thick Walled Cylinder With Internal Pressure N/A 5.D-1 FIGURE 5.D-1 Tangential Velocities as Derived from Hoecker's Pressure - Time Profile N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 15 of 47 5.D-2 FIGURE 5.D-2 Monthly Weather Review - Hoecker N/A 5.D-3 FIGURE 5.D-3 Test Data Summary N/A 5.D.A-1 FIGURE 5.D.A-1 Plan of Spent Fuel Area N/A 5.D.A-2 FIGURE 5.D.A-2 Spent Fuel Pool Section View N/A 5.D.A-3 FIGURE 5.D.A-3 Missile Strike Angle to Missile Proof Siding N/A 6.1-1 FIGURE 6.1-1 Safety Injection P&ID (Sheet 1) 25203-26015 (a)
Sheet 1 of 3 6.1-1 FIGURE 6.1-1 Safety Injection P&ID (Sheet 2) 25203-26015 (a)
Sheet 2 of 3 6.1-1 FIGURE 6.1-1 Safety Injection P&ID (Sheet 3) 25203-26015 (a)
Sheet 3 of 3 6.1-2 FIGURE 6.1-2 Main Steam Pipe Whip Restraint N/A 6.1-3 FIGURE 6.1-3 Pipe Restraint Design N/A 6.1-4 FIGURE 6.1-4 Fluid Jet Expansion Model N/A 6.3-1 FIGURE 6.3-1 Safety Injection and Containment Spray Pumps Suction Piping N/A 6.3-2 FIGURE 6.3-2 High Pressure Safety Injection Pump Performance N/A 6.3-3 FIGURE 6.3-3 Low Pressure Safety Injection Pump Performance N/A 6.4-1 FIGURE 6.4-1 Area 5 Piping Containment Spray and Hydrogen Purge N/A 6.4-2 FIGURE 6.4-2 Containment Spray Nozzles Spray Patterns (1713A Nozzle Spraying Horizontally)
N/A 6.4-3 FIGURE 6.4-3 Containment Spray Nozzles Spray Patterns (1713A Nozzle Spraying Downward on 45°)
N/A 6.4-4 FIGURE 6.4-4 Containment Spray Nozzles Spray Patterns (1713A Nozzle Spraying Vertically Downward)
N/A 6.4-4A FIGURE 6.4-4A Typical Spray Coverage Patterns N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 16 of 47 6.4-5 FIGURE 6.4-5 Not Used N/A 6.4-6 FIGURE 6.4-6 Not Used N/A 6.4-7 FIGURE 6.4-7 Containment Spray Nozzle Performance Characteristics N/A 6.4-8 FIGURE 6.4-8 Containment Spray Pump Performance Characteristics.
N/A 6.4-9 FIGURE 6.4-9 Containment Heat Removal Systems Sink Schematic N/A 6.5-1 FIGURE 6.5-1 Containment Air Recirculation and Cooling Unit Fan Performance Curve N/A 6.5-2 FIGURE 6.5-2 Containment Air Recirculation and Cooling Unit Coil Performance Characteristics N/A 6.6-1 FIGURE 6.6-1 Post-Incident Recirculation Fan Performance Characteristics N/A 6.7-1 FIGURE 6.7-1 Enclosure Building Filtration System Fan Performance Curve N/A 7.2-1 FIGURE 7.2-1 Reactor Protective System Block Diagram 7.2-2 FIGURE 7.2-2 Reactor Protective System Functional Diagram 25203-29193 (a)
Sheet 1 7.2-3 FIGURE 7.2-3 Nuclear Instrumentation System Functional Diagram 7.2-4 FIGURE 7.2-4 Low Flow Protective System Functional Diagram 7.2-5 FIGURE 7.2-5 Low Steam Generator Pressure Reactor Trip Bypass Functional Diagram 7.2-6 FIGURE 7.2-6 Block Diagram Core Protection Trips 7.2-7 FIGURE 7.2-7 Neutron Flux Monitoring System Logarithmic Range Channels 7.2-8 FIGURE 7.2-8 Neutron Flux Monitoring System Power Range Channels 7.2-9 FIGURE 7.2-9 Not Used 7.2-10 FIGURE 7.2-10 Reactor Coolant Pump Underspeed Block Diagram 7.2-11 FIGURE 7.2-11 Variable High Power Trip Operation LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 17 of 47 7.2-12 FIGURE 7.2-12 Thermal Margin Trip 7.2-13 FIGURE 7.2-13 DT Power Calculation 7.2-14 FIGURE 7.2-14 Local Power Density Trip 7.3-1 FIGURE 7.3-1 Engineered Safety Logic 25203-28150 (a)
Sheet 1 7.3-2A FIGURE 7.3-2A Engineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a)
Sheet 2A 7.3-2B FIGURE 7.3-2B Engineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a)
Sheet 2B 7.3-2C FIGURE 7.3-2C Engineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a)
Sheet 2C 7.3-2D FIGURE 7.3-2D Engineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a)
Sheet 2D 7.3-3 FIGURE 7.3-3 Engineered Safety Logic Sequencer & Channel 5 Output 25203-28150 (a)
Sheet 3 7.3-4 FIGURE 7.3-4 Engineered Safety Logic 25203-28150 (a)
Sheet 4 7.4-1 FIGURE 7.4-1 Deleted by FSARCR 05-MP2-026 N/A 7.4-2 FIGURE 7.4-2 CEA Position Setpoints N/A 7.4-3 FIGURE 7.4-3 CEDS Functional Block Diagram 25203-29155 (a)
Sheet 9 7.4-4 FIGURE 7.4-4 Pressure Control Program N/A 7.4-5 FIGURE 7.4-5 Steam Dump to Condensers and Turbine Bypass System N/A 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 1) 25203-39220 (a)
Sheet 7A 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 2) 25203-39220 (a)
Sheet 7B 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 3) 25203-39220 (a)
Sheet 8A 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 4) 25203-39220 (a)
Sheet 8B 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 5) 25203-39220 (a)
Sheet 9A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 18 of 47 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 6) 25203-39220 (a)
Sheet 9B 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 7) 25203-39220 (a)
Sheet 10A 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 8) 25203-39220 (a)
Sheet 10B 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 9) 25203-39220 (a)
Sheet 11A 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 10) 25203-39220 (a)
Sheet 11B 7.4-7 FIGURE 7.4-7 Feedwater Regulating System Block Power Distribution N/A 7.4-8 FIGURE 7.4-8 Reactivity Control System N/A 7.4-9 FIGURE 7.4-9 Motion Inhibit Circuit Interconnection Simplified Diagram N/A 7.5-1 FIGURE 7.5-1 Pressurizer Pressure Measurement Channel Functional Diagram N/A 7.5-2 FIGURE 7.5-2 Out-Of-Core Nuclear Detector Location N/A 7.5-3 FIGURE 7.5-3 In-Core Nuclear Detector Assembly N/A 7.5-4 FIGURE 7.5-4 In-Core Detector/Core Exit Thermocouple and RVLM Sensor Locations N/A 7.5-5 FIGURE 7.5-5 Process Radiation Monitor Schematic N/A 7.5-6 FIGURE 7.5-6 Heated Junction Thermocouple Probe Assembly N/A 7.5-7 FIGURE 7.5-7 ICCMS Functional Block Diagram N/A 7.5-8 FIGURE 7.5-8 ICCMS Data Processing N/A 7.5-9 FIGURE 7.5-9 ICCMS Display Hierarchy N/A 7.6-1 FIGURE 7.6-1 General Arrangement Control Room Plan Elevation 35 feet 6 inches 25203-27027 (a) 7.6-2 FIGURE 7.6-2 C01, CRP, Front View Arrangement Safeguards Section (Sheet 1) 25203-30208 (a)
Sheet 1 of 4 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 19 of 47 7.6-2 FIGURE 7.6-2 C01, CRP, Front View Arrangement Safeguards Section (Sheet 2) 25203-30208 (a)
Sheet 2 of 4 7.6-2 FIGURE 7.6-2 C01, CRP, Front View Arrangement Safeguards Section (Sheet 3) 25203-30208 (a)
Sheet 3 of 4 7.6-2 FIGURE 7.6-2 C01, CRP, Front View Arrangement Safeguards Section (Sheet 4) 25203-30208 (a)
Sheet 4 of 4 7.6-3 FIGURE 7.6-3 CRP Front View Arrangements (Sheet 1) 25203-30209 (a)
Sheet 1 of 2 7.6-3 FIGURE 7.6-3 CRP Front View Arrangements (Sheet 2) 25203-30209 (a)
Sheet 2 of 2 7.6-3 FIGURE 7.6-3 CRP Front View Arrangements (Sheet 3) 25203-30210 (a)
Sheet 1 of 2 7.6-3 FIGURE 7.6-3 CRP Front View Arrangements (Sheet 4) 25203-30210 (a)
Sheet 2 of 2 7.6-4 FIGURE 7.6-4 C04 CRP, Front View Arrangement Reactivity Control System (Sheet 1) 25203-30211 (a)
Sheet 1 7.6-4 FIGURE 7.6-4 C04 CRP, Front View Arrangement Reactivity Control System (Sheet 2) 25203-30211 (a)
Sheet 2 7.6-4 FIGURE 7.6-4 C04 CRP, Front View Arrangement Reactivity Control System (Sheet 3) 25203-30211 (a)
Sheet 3 7.6-4 FIGURE 7.6-4 C04 CRP, Front View Arrangement Reactivity Control System (Sheet 4) 25203-30211 (a)
Sheet 4 7.6-5 FIGURE 7.6-5 C05, CRP, Front View Arrangement Steam Generator &
Feedwater Control (Sheet 1) 25203-30212 (a)
Sheet 1 7.6-5 FIGURE 7.6-5 C05, CRP, Front View Arrangement Steam Generator &
Feedwater Control (Sheet 2) 25203-30212 (a)
Sheet 2 7.6-5 FIGURE 7.6-5 C05, CRP, Front View Arrangement Steam Generator &
Feedwater Control (Sheet 3) 25203-30212 (a)
Sheet 3 7.6-5 FIGURE 7.6-5 C05, CRP, Front View Arrangement Steam Generator &
Feedwater Control (Sheet 4) 25203-30212 (a)
Sheet 4 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 20 of 47 7.6-6 FIGURE 7.6-6 C06, CRP. Front View Arrangement Plant Auxiliary (Sheet 1) 25203-30213 (a)
Sheet 1 of 2 7.6-6 FIGURE 7.6-6 C06, CRP. Front View Arrangement Plant Auxiliary (Sheet 2) 25203-30213 (a)
Sheet 2 of 2 7.6-7 FIGURE 7.6-7 C07, Control Room Panel, Front View Arrangement Turbine-Generator (Sheet 1) 25203-30214 (a)
Sheet 1 of 4 7.6-7 FIGURE 7.6-7 C07, Control Room Panel, Front View Arrangement Turbine-Generator (Sheet 2) 25203-30214 (a)
Sheet 2 of 4 7.6-7 FIGURE 7.6-7 C07, Control Room Panel, Front View Arrangement Turbine-Generator (Sheet 3) 25203-30214 (a)
Sheet 3 of 4 7.6-7 FIGURE 7.6-7 C07, Control Room Panel, Front View Arrangement Turbine-Generator (Sheet 4) 25203-30214 (a)
Sheet 4 of 4 7.6-8 FIGURE 7.6-8 C08, CRP Front View Arrangement Station Service Electric (Sheet 1) 25203-30215 (a)
Sheet 1 of 4 7.6-8 FIGURE 7.6-8 C08, CRP Front View Arrangement Station Service Electric (Sheet 2) 25203-30215 (a)
Sheet 2 of 4 7.6-8 FIGURE 7.6-8 C08, CRP Front View Arrangement Station Service Electric (Sheet 3) 25203-30215 (a)
Sheet 3 of 4 7.6-8 FIGURE 7.6-8 C08, CRP Front View Arrangement Station Service Electric (Sheet 4) 25203-30215 (a)
Sheet 4 of 4 7.6-9 FIGURE 7.6-9 Local Control Panels (C60) & (C61) 25203-28006 (a)
Sheet 1 of 3 7.6-10 FIGURE 7.6-10 Local Control Panels (C63) & (C21) 25203-28006 (a)
Sheet 2 of 3 7.6-11 FIGURE 7.6-11 Engineered Safety Equipment Status Panel Layout (C01X) 25203-30071 (a) 7.6-12 FIGURE 7.6-12 Condensate Demineralizer Waste Treating Panel CDX N/A 7.6-13 FIGURE 7.6-13 Condensate Demineralizer Waste Treating Panel CDX N/A 7.6-14 FIGURE 7.6-14 Condensate Demineralizer Waste Treating Panel CDX N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 21 of 47 7.6-15 FIGURE 7.6-15 Condensate Demineralizer Waste Treating Panel CDX N/A 7.9-1 FIGURE 7.9-1 Logic Diagram - Anticipated Transient Without Scram 25203-28105 (a)
Sheet 36 7.9-2 FIGURE 7.9-2 Block Diagram Diverse SCRAM System (ATWS) 25203-37005 (a)
Sheet 105 7.9-3 FIGURE 7.9-3 Schematic Diagram Diverse SCRAM System ATWS 25203-32012 (a)
Sheet 48 7.10-1 FIGURE 7.10-1 Piping and Instrumentation Diagram Auxiliary Steam and Condensate 25203-26026 (a)
Sheet 2 of 5 8.1-1A FIGURE 8.1-1A Deleted by FSARCR MP2-UCR-2016-007 N/A 8.1-1B FIGURE 8.1-1B Hunts Brook Junction N/A 8.1-1C FIGURE 8.1-1C 345 kV Transmission Map of Connecticut and Western Massachusetts N/A 8.1-1D FIGURE 8.1-1D 345 kV Switchyard N/A 8.2-3 FIGURE 8.2-3 Main Single Line Diagram 25203-30001 (a) 8.3-4 FIGURE 8.3-4 Logic Diagrams Diesel Generators (Sheet A) 25203-30034 (a)
Sheet 1 8.3-4 FIGURE 8.3-4 Logic Diagrams Diesel Generators (Sheet B) 25203-30034 (a)
Sheet 2 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 0A) 25203-32041 (a)
Sheet A 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 1) 25203-32041 (a)
Sheet 1 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 1A) 25203-32041 (a)
Sheet 1A 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 2) 25203-32041 (a)
Sheet 2 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 2A) 25203-32041 (a)
Sheet 2A 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 3) 25203-32041 (a)
Sheet 3 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 22 of 47 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 4) 25203-32041 (a)
Sheet 4 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 5) 25203-32041 (a)
Sheet 5 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 6) 25203-32041 (a)
Sheet 6 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 7) 25203-32041 (a)
Sheet 7 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 8) 25203-32041 (a)
Sheet 8 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 9) 25203-32041 (a)
Sheet 9 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 10) 25203-32041 (a)
Sheet 10 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 11) 25203-32041 (a)
Sheet 11 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 12) 25203-32041 (a)
Sheet 12 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 13) 25203-32041 (a)
Sheet 13 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 14) 25203-32041 (a)
Sheet 14 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 15) 25203-32041 (a)
Sheet 15 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 16) 25203-32041 (a)
Sheet 16 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 17) 25203-32041 (a)
Sheet 17 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 18) 25203-32041 (a)
Sheet 18 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 19) 25203-32041 (a)
Sheet 19 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 20) 25203-32041 (a)
Sheet 20 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 21) 25203-32041 (a)
Sheet 21 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 22) 25203-32041 (a)
Sheet 22 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 23 of 47 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 23) 25203-32041 (a)
Sheet 23 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 24) 25203-32041 (a)
Sheet 24 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 25) 25203-32041 (a)
Sheet 25 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 26) 25203-32041 (a)
Sheet 26 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 27) 25203-32041 (a)
Sheet 27 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 28) 25203-32041 (a)
Sheet 28 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 29) 25203-32041 (a)
Sheet 29 8.3-5 FIGURE 8.3-5 Diesel Generator Related (Sheet 30) 25203-32041 (a)
Sheet 30 8.3-6 FIGURE 8.3-6 Not Used 8.3-7 FIGURE 8.3-7 Diesel Generator Fuel Oil System/Auxiliary Steam Condensate and Heater Index (Sheets 1) 25203-26010 (a)
Sheet 1 of 1 8.3-7 FIGURE 8.3-7 Diesel Generator Fuel Oil System/Auxiliary Steam Condensate and Heater Index (Sheet 2) 25203-26026 (a)
Sheet 3 of 5 8.3-7 FIGURE 8.3-7 Diesel Generator Fuel Oil System/Auxiliary Steam Condensate and Heater Index (Sheet 3) 25203-26026 (a)
Sheet 4 of 5 8.3-8 FIGURE 8.3-8 Diesel Generators' Ancillary Systems (Sheet 1A) 25203-26018 (a)
Sheet 4 of 5 8.3-8 FIGURE 8.3-8 Diesel Generators' Ancillary Systems (Sheet 1B) 25203-26018 (a)
Sheet 5 of 5 8.3-8 FIGURE 8.3-8 Diesel Generators' Ancillary Systems (Sheet 2) 25203-26018 (a)
Sheet 2 of 5 8.3-8 FIGURE 8.3-8 Diesel Generators' Ancillary Systems (Sheet 3) 25203-26018 (a)
Sheet 3 of 5 8.4-1 FIGURE 8.4-1 Charging Pump - Power Supply Crossover P18B 25203-32009 (a)
Sheet 42 8.4-2 FIGURE 8.4-2 Service Water Strainer ML1B Power Supply Crossover Scheme 25203-32013 (a)
Sheet 39 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 24 of 47 8.5-1 FIGURE 8.5-1 Single Line Diagram 125 VDC / VAC Systems (Sheet 1) 25203-30024 (a) 8.5-1 FIGURE 8.5-1 Single Line Diagram 125 VDC / VAC Systems (Sheet 2) 25203-30023 (a) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 1) 25203-32045 (a)
Sheet 1 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 2) 25203-32045 (a)
Sheet 2 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 3) 25203-32045 (a)
Sheet 3 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 4) 25203-32045 (a)
Sheet 4 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 5) 25203-32045 (a)
Sheet 5 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 6) 25203-32045 (a)
Sheet 6 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 7) 25203-32045 (a)
Sheet 7 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 8) 25203-32045 (a)
Sheet 8 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 9) 25203-32045 (a)
Sheet 9 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 10A) 25203-32045 (a)
Sheet 10A 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 10B) 25203-32045 (a)
Sheet 10B LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 25 of 47 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 10C) 25203-32045 (a)
Sheet 10C 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 10D) 25203-32045 (a)
Sheet 10D 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 11) 25203-32045 (a)
Sheet 11 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 12) 25203-32045 (a)
Sheet 12 8.7-1 FIGURE 8.7-1 Raceway Plans (Sheet 1) 25203-34060 (a) 8.7-1 FIGURE 8.7-1 Raceway Plan Cable Vault Area -6, Elevation 25 Feet 6 Inches (Sheet 2) 25203-34031 (a) 8.7-1 FIGURE 8.7-1 Raceway Plan Cable Vault Area -7, Elevation 25 Feet 6 Inches (Sheet 3) 25203-34032 (a) 8.7-1 FIGURE 8.7-1 Raceway Plan Containment Area Elevation 14 Feet 6 Inches (Sheets 4) 25203-34042 (a) 9.0-1 FIGURE 9.0-1 P&ID Legend 25203-26001 (a)
Sheet 1 of 3 9.0-2 FIGURE 9.0-2 P&ID Legend 25203-26001 (a)
Sheet 2 of 3 9.0-3 FIGURE 9.0-3 General Legend Notes N/A 9.2-1 FIGURE 9.2-1 Chemical and Volume Control System Flow Schematic (Normal Operation)
N/A 9.2-2 FIGURE 9.2-2 P&IDs: Charging; Deborating; Purification; Boric Acid Systems (Sheet 1) 25203-26017 (a)
Sheet 1 of 3 9.2-2 FIGURE 9.2-2 P&IDs: Charging; Deborating; Purification; Boric Acid Systems (Sheet 2) 25203-26017 (a)
Sheet 2 of 3 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 26 of 47 9.2-2 FIGURE 9.2-2 P&IDs: Charging; Deborating; Purification; Boric Acid Systems (Sheet 3) 25203-26017 (a)
Sheet 3 of 3 9.3-1 FIGURE 9.3-1 Shutdown Cooling Flow Diagram N/A 9.4-1 FIGURE 9.4-1 P&ID RBCCW System RBCCW Pumps and Heat Exchangers 25203-26022 (a)
Sheet 1 of 6 9.4-2 FIGURE 9.4-2 RBCCW System Spent Fuel Pool and Shutdown Heat Exchangers 25203-26022 (a)
Sheet 2 of 6 9.4-3 FIGURE 9.4-3 P&ID RBCCW. System Containment Spray Pump and Safety Injection Pump Seal Coolers 25203-26022 (a)
Sheet 3 of 6 9.4-4 FIGURE 9.4-4 P&ID RBCCW. System Reactor Coolant Pump, Thermal Barriers and Lube Oil Coolers 25203-26022 (a)
Sheet 4 of 6 9.4-5 FIGURE 9.4-5 P&ID RBCCW. System Containment Air Recirculation and Coolant Unit 25203-26022 (a)
Sheet 5 of 6 9.4-6 FIGURE 9.4-6 P&ID Diagram RBCCW. System Reactor Vessel Support Concrete Cooling Coils 25203-26022 (a)
Sheet 6 of 6 9.4-7 FIGURE 9.4-7 Reactor Building Closed Cooling Water Pump Performance Curve N/A 9.5-1 FIGURE 9.5-1 P&ID Spent Fuel Pool Cleaning and Cleanup System (Sheet 1) 25203-26023 (a)
Sheet 1 of 2 9.5-1 FIGURE 9.5-1 P&ID Spent Fuel Pool Cleaning and Cleanup System (Sheet 2) 25203-26023 (a)
Sheet 2 of 2 9.5-2 FIGURE 9.5-2 Spent Fuel Pool Pump Performance Curve N/A 9.6-1 FIGURE 9.6-1 P&ID Diagram Sampling System 25203-26025 (a)
Sheet 1 of 4 9.6-2 FIGURE 9.6-2 P&ID Diagram Sampling System 25203-26025 (a)
Sheet 2 of 4 9.6-3 FIGURE 9.6-3 P&ID Diagram Sampling System 25203-26025 (a)
Sheet 3 of 4 9.6-4 FIGURE 9.6-4 P&ID Post Accident Sampling System Reactor Coolant Sample 25203-26074 (a)
Sheet 1 of 2 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 27 of 47 9.6-5 FIGURE 9.6-5 P&ID Post Accident Sampling System Containment Air Sample 25203-26074 (a)
Sheet 2 of 2 9.7-1 FIGURE 9.7-1 P&IDs - Circulating Water, Service Water, Screen Wash, Sodium Hypochlorite (Sheet 1) 25203-26008 (a)
Sheet 1 of 4 9.7-1 FIGURE 9.7-1 P&IDs - Circulating Water, Service Water, Screen Wash, Sodium Hypochlorite (Sheet 2) 25203-26008 (a)
Sheet 2 of 4 9.7-1 FIGURE 9.7-1 P&IDs - Circulating Water, Service Water, Screen Wash, Sodium Hypochlorite (Sheet 3) 25203-26008 (a)
Sheet 3 of 4 9.7-1 FIGURE 9.7-1 P&IDs - Circulating Water, Service Water, Screen Wash, Sodium Hypochlorite (Sheet 4) 25203-26008 (a)
Sheet 4 of 4 9.7-2 FIGURE 9.7-2 P&ID TBCCW System (Sheet 1) 25203-26007 (a)
Sheet 1 of 3 9.7-2 FIGURE 9.7-2 P&ID TBCCW System (Sheet 2) 25203-26007 (a)
Sheet 2 of 3 9.7-2 FIGURE 9.7-2 P&ID TBCCW System (Sheet 3) 25203-26007 (a)
Sheet 3 of 3 9.7-3 FIGURE 9.7-3 Typical Service Water Pump Certified Test Curve N/A 9.7-4 FIGURE 9.7-4 Deleted by FSARCR 03-MP2-011 N/A 9.8-1 FIGURE 9.8-1 Plan of New Fuel Storage Racks N/A 9.8-2 FIGURE 9.8-2 New Fuel Storage Racks - Section A-A N/A 9.8-3 FIGURE 9.8-3 New Fuel Storage Rack Assembly (8 Rack Module) 25203-13013 (a)
Sheet 14 9.8-4 FIGURE 9.8-4 New Fuel Storage Rack Assembly (4 Rack Module) 25203-13013 (a)
Sheet 19 9.8-5 FIGURE 9.8-5 Storage Rack N/A 9.8-6 FIGURE 9.8-6 Closure Bar New Fuel Storage Racks 25203-13013 (a)
Sheet 10 9.8-7 FIGURE 9.8-7 Fuel Pool Arrangement - Four Region N/A 9.8-8A FIGURE 9.8-8A Typical Spent Fuel Rack Module/Poison Box - Regions 1 and 2 N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 28 of 47 9.8-8B FIGURE 9.8-8B Typical Spent Fuel Rack Module/Regions 3 and 4 N/A 9.8-8C FIGURE 9.8-8C Poison Box (Boraflex poison no longer credited)
N/A 9.8-8D FIGURE 9.8-8D Adjustable Foot N/A 9.8-9 FIGURE 9.8-9 Collector Leak Channel Plan at Base of Walls N/A 9.8-10 FIGURE 9.8-10 Refueling Equipment Arrangement N/A 9.8-11 FIGURE 9.8-11 Refueling Machine N/A 9.8-12 FIGURE 9.8-12 Deleted by PKG FSC MP2-UCR-2009-006 N/A 9.8-13 FIGURE 9.8-13 Reactor Vessel Head Lifting Rig N/A 9.8-14 FIGURE 9.8-14 Core Support Barrel Lifting Rig N/A 9.8-15 FIGURE 9.8-15 Upper Guide Structure Lifting Rig N/A 9.8-16 FIGURE 9.8-16 Surveillance Capsule Retrieval Tool N/A 9.8-17 FIGURE 9.8-17 Spent Fuel Pool Platform Crane N/A 9.8-18 FIGURE 9.8-18 Spent Fuel Pool Platform Crane Travel Limits N/A 9.8-19 FIGURE 9.8-19 Spent Fuel Cask Crane 25203-29022 (a) 169 9.8-20 FIGURE 9.8-20 Heated Junction Thermocouple Handling Canister N/A 9.9-1 FIGURE 9.9-1 P&ID Containment and Enclosure Building Ventilation 25203-26028 (a)
Sheet 1 of 6 9.9-2 FIGURE 9.9-2 Ventilation P&IDs (Sheet 1) 25203-26028 (a)
Sheet 2 of 6 9.9-2 FIGURE 9.9-2 Ventilation P&IDs (Sheet 2) 25203-26028 (a)
Sheet 3 of 6 9.9-2 FIGURE 9.9-2 Ventilation P&IDs (Sheet 3) 25203-26028 (a)
Sheet 4 of 6 9.9-2 FIGURE 9.9-2 Ventilation P&IDs (Sheet 4) 25203-26028 (a)
Sheet 5 of 6 9.9-3 FIGURE 9.9-3 P&ID Auxiliary Building Ventilation System (Sheet 1) 25203-26029 (a)
Sheet 1 of 7 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 29 of 47 9.9-3 FIGURE 9.9-3 P&ID Auxiliary Building Ventilation System (Sheet 2) 25203-26029 (a)
Sheet 2 of 7 9.9-3 FIGURE 9.9-3 P&ID Auxiliary Building Ventilation System (Sheet 3) 25203-26029 (a)
Sheet 3 of 7 9.9-4 FIGURE 9.9-4 P&ID HVAC System Turbine Building, Intake Structure, Warehouse and Diesel Generator Rooms 25203-26027 (a)
Sheet 1 9.9-4A FIGURE 9.9-4A P&ID Control Room Air Conditioning System 25203-26027 (a)
Sheet 3 9.9-5 FIGURE 9.9-5 Control Element Drive Mechanism (CEDM) Fan Performance Curve N/A 9.9-6 FIGURE 9.9-6 Containment Purge Fan Performance Curve N/A 9.9-7 FIGURE 9.9-7 Containment Auxiliary Circulation Fan Performance Curve N/A 9.9-8 FIGURE 9.9-8 Containment Penetration Cooling Fan Performance Curve N/A 9.9-9 FIGURE 9.9-9 Radwaste Ventilation Fan Performance Curve N/A 9.9-10 FIGURE 9.9-10 Logic Diagram Radwaste Area Supply Fan 25203-28129 (a)
Sheet 22 9.9-11 FIGURE 9.9-11 Non-Radioactive Supply Fan Performance Curve N/A 9.9-12 FIGURE 9.9-12 Non-Radioactive Exhaust Fan Performance Curve N/A 9.9-13 FIGURE 9.9-13 Battery Room Exhaust Fan Performance Curve N/A 9.9-14 FIGURE 9.9-14 Cable Vault Transfer Fan Performance Curve N/A 9.9-15 FIGURE 9.9-15 Engineered Safety Features Room Fan Performance Curve N/A 9.9-16 FIGURE 9.9-16 Fuel Handling Supply Fan Performance Curve N/A 9.9-17 FIGURE 9.9-17 Deleted N/A 9.9-18 FIGURE 9.9-18 Main Exhaust Fan Performance Curve N/A 9.9-19 FIGURE 9.9-19 Control Room Air Conditioning Fan Performance Curve N/A 9.9-20 FIGURE 9.9-20 Air Cooled Condenser Fan Performance Curve N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 30 of 47 9.9-21 FIGURE 9.9-21 Control Room Exhaust Fan Performance Curve N/A 9.9-22 FIGURE 9.9-22 Control Room Filtration System Fan Performance Curve N/A 9.9-23 FIGURE 9.9-23 Diesel Generator Room Supply Fan Performance Curve N/A 9.9-24 FIGURE 9.9-24 Diesel Generator Fan Performance Curve N/A 9.9-25 FIGURE 9.9-25 Turbine Building Supply Fan Performance Curve N/A 9.9-26 FIGURE 9.9-26 Turbine Building Exhaust Fan Performance Curve N/A 9.9-27 FIGURE 9.9-27 Electrical Room Supply Fan Performance Curve N/A 9.9-28 FIGURE 9.9-28 Access Control Area Air Conditioning Fan Performance Curve N/A 9.9-29 FIGURE 9.9-29 Deleted N/A 9.9-30 FIGURE 9.9-30 Deleted N/A 9.9-31 FIGURE 9.9-31 P&ID Turbine Building, Intake Structure, Warehouse and Diesel Generator Room Chilled Water System 25203-26027 (a)
Sheet 2 9.10-1 FIGURE 9.10-1 Deleted N/A 9.10-2 FIGURE 9.10-2 P&ID Domestic Water (Sheet 1) 25203-26011 (a)
Sheet 1 of 7 9.10-2 FIGURE 9.10-2 P&ID Domestic Water (Sheet 2) 25203-26011 (a)
Sheet 2 of 7 9.11-1 FIGURE 9.11-1 P&ID Instrument Air System Compressors F-3E and F-3F 25203-26009 (a)
Sheet 1 9.11-2 FIGURE 9.11-2 P&ID Instrument Air System Compressors F-3D 25203-26009 (a)
Sheet 9 of 10 9.12-1 FIGURE 9.12-1 P&ID Diagram Water Treatment System 25203-26030 (a)
Sheet 1 of 1 9.13-1 FIGURE 9.13-1 P&ID Auxiliary Steam and Condensate (Sheet 1) 25203-26026 (a)
Sheet 1 of 5 9.13-1 FIGURE 9.13-1 P&ID Auxiliary Steam and Condensate (Sheet 2) 25203-26026 (a)
Sheet 2 of 5 9.13-1 FIGURE 9.13-1 P&ID Auxiliary Steam and Condensate (Sheet 3) 25203-26026 (a)
Sheet 3 of 5 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 31 of 47 9.13-1 FIGURE 9.13-1 P&ID Auxiliary Steam and Condensate (Sheet 4) 25203-26026 (a)
Sheet 4 of 5 10.1-1 FIGURE 10.1-1 Deleted by FSARCR 03-MP2-007]
N/A 10.1-2 FIGURE 10.1-2 Deleted by FSARCR 03-MP2-007 N/A 10.3-1 FIGURE 10.3-1 P&ID Main Steam from Generators (25203-26002 Sheet 1) 25203-26002 (a)
Sheet 1 of 5 10.3-1 FIGURE 10.3-1 P&ID Main Steam Generator Blowdown System (25203-26002 Sheet 2) 25203-26002 (a)
Sheet 2 of 5 10.3-1 FIGURE 10.3-1 P&ID Main Steam Turbine and Reheater 1A (25203-26002 Sheet 3) 25203-26002 (a)
Sheet 3 of 5 10.3-1 FIGURE 10.3-1 P&ID Main Steam Turbine (25203-26002 Sheet 4) 25203-26002 (a)
Sheet 4 of 5 10.4-1 FIGURE 10.4-1 P&ID Condenser Air Removal Water Box Priming and Turbine Building Sump (25203-26012) 25203-26012 (a) 10.4-2 FIGURE 10.4-2 P&ID Condensate System (25203-26005 Sheet 2) 25203-26005 (a)
Sheet 1 of 4 10.4-2 FIGURE 10.4-2 P&ID Condensate Storage and Auxiliary Feed (25203-26005 Sheet 3) 25203-26005 (a)
Sheet 2 of 4 10.4-2 FIGURE 10.4-2 P&ID Condensate Storage and Auxiliary Feed (25203-26005 Sheet 4) 25203-26005 (a)
Sheet 3 of 4 10.4-2 FIGURE 10.4-2 P&ID Condensate System (25203-26005 Sheet 1) 25203-26005 (a)
Sheet 4 of 4 11.1-1 FIGURE 11.1-1 P&ID Clean Liquid Radwaste System 25203-26020 (a)
Sheet 1 of 5 11.1-2 FIGURE 11.1-2 P&ID Clean Liquid Radwaste System 25203-26020 (a)
Sheet 2 of 5 11.1-3 FIGURE 11.1-3 P&ID Drains (Containment & Auxiliary Building and Auxiliary Yard Sump) (Sheet 1) 25203-26024 (a)
Sheet 1 11.1-3 FIGURE 11.1-3 P&ID Drains (Containment & Auxiliary Building and Auxiliary Yard Sump) (Sheet 2) 25203-26024 (a)
Sheet 2 LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 32 of 47 11.1-3 FIGURE 11.1-3 P&ID Drains (Containment & Auxiliary Building and Auxiliary Yard Sump) (Sheet 3) 25203-26024 (a)
Sheet 3 11.1-4 FIGURE 11.1-4 P&ID Aerated Liquid Radwaste System 25203-26021 (a)
Sheet 1 of 3 11.1-5 FIGURE 11.1-5 P&ID Diagram Gaseous Radwaste System 25203-26021 (a)
Sheet 2 of 3 11.1-6 FIGURE 11.1-6 Degasifier Performance Curve N/A 11.1-7 FIGURE 11.1-7 P&ID Spent Resin Radwaste System 25203-26021 (a)
Sheet 3 of 3 11.2-1 FIGURE 11.2-1 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building -
Elevation (-) 45 Feet 6 Inches 25203-17001 (a) 11.2-2 FIGURE 11.2-2 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building -
Elevation (-) 29 Feet 6 Inches 25203-17002 (a) 11.2-3 FIGURE 11.2-3 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building -
Elevation (-) 5 Feet 0 Inches 25203-17003 (a) 11.2-4 FIGURE 11.2-4 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment Building - Elevation 14 Feet 6 Inches and 38 Feet 6 Inches 25203-17004 (a) 11.2-5 FIGURE 11.2-5 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Auxiliary Building - Elevation 14 Feet 6 Inches and 25 Feet 6 Inches 25203-17005 (a) 11.2-6 FIGURE 11.2-6 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Turbine Building - Elevation 14 Feet 6 Inches 25203-17006 (a)
LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 33 of 47 11.2-7 FIGURE 11.2-7 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Auxiliary Building - Elevation 36 Feet 6 Inches 25203-17007 (a) 11.2-8 FIGURE 11.2-8 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building -
Section A-A 25203-17008 (a) 11.2-9 FIGURE 11.2-9 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building -
Section B-B 25203-17009 (a) 11.2-10 FIGURE 11.2-10 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary 25203-17010 (a) 11.2-11 FIGURE 11.2-11 Neutron Shield Segment N/A 11.2-12 FIGURE 11.2-12 Neutron Shielding - Sectional View N/A 11.2-13 FIGURE 11.2-13 Not Used N/A 11.2-14 FIGURE 11.2-14 Not Used N/A 11.2-15 FIGURE 11.2-15 Neutron Shield - Thermal Loadings (Typical Annular Section)
N/A 11.2-16 FIGURE 11.2-16 Neutron Shield - Thermal Loadings (Plug Shield Section)
N/A 11.B-1 FIGURE 11.B-1 NUREG-0017 Gale Code Input Diagram - Liquid Waste System N/A 11.B-2 FIGURE 11.B-2 NUREG-0017 Gale Code Input Diagram - Airborne N/A 13.2-1 FIGURE 13.2-1 Millstone Nuclear Power Station Organization Diagram During Initial Startup N/A 13.2-2 FIGURE 13.2-2 Startup Group Organization N/A 14.0.4-1 FIGURE 14.0.4-1 RCS Cold Leg Temperature as a Function of Power N/A 14.0.4-2 FIGURE 14.0.4-2 Not Used N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 34 of 47 14.0.4-3 FIGURE 14.0.4-3 Not Used N/A 14.0.4-4 FIGURE 14.0.4-4 Not Used N/A 14.0.4-5 FIGURE 14.0.4-5 Not Used N/A 14.0.4-6 FIGURE 14.0.4-6 Not Used N/A 14.0.4-7 FIGURE 14.0.4-7 Linear Heat Rate Limiting Condition for Operation used in Local Power Density Limiting Condition for Operation Verification N/A 14.0.7-1 FIGURE 14.0.7-1 Verification of Local Power Density Limiting Safety System Setting N/A 14.0.7-2 FIGURE 14.0.7-2 Thermal Margin/Low Pressure Trip Function A1 N/A 14.0.7-3 FIGURE 14.0.7-3 Thermal Margin/Low Pressure Trip Function QR1 N/A 14.0.7-4 FIGURE 14.0.7-4 Not Used N/A 14.0.7-5 FIGURE 14.0.7-5 Verification of the Departure from Nucleate Boiling Limiting Condition for Operation N/A 14.0.7-6 FIGURE 14.0.7-6 Verification of Local Power Density Limiting Condition for Operation N/A 14.0.7-7 FIGURE 14.0.7-7 Linear Heat Rate Limiting Condition of Operation Used in Local Power Density Limiting Condition of Operation Verification N/A 14.1.3-1 FIGURE 14.1.3-1 Normalized Power and Heat Flux for the Increase in Steam Flow Event N/A 14.1.3-2 FIGURE 14.1.3-2 Reactivity Feedback for the Increase in Steam Flow Event N/A 14.1.3-3 FIGURE 14.1.3-3 Reactor Coolant Temperatures for Increase in Steam Flow Event N/A 14.1.3-4 FIGURE 14.1.3-4 Core Inlet Mass Flow Rate for the Increase in Steam Flow Event N/A 14.1.3-5 FIGURE 14.1.3-5 Pressurizer Pressure for the Increase in Steam Flow Event N/A 14.1.3-6 FIGURE 14.1.3-6 Steam Generator Pressures for the Increase in Steam Flow Event N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 35 of 47 14.1.3-7 FIGURE 14.1.3-7 Steam Mass Flow Rates for the Increase in Steam Flow Event N/A 14.1.3-8 FIGURE 14.1.3-8 Main Feedwater Flow for the Increase in Steam Flow Event N/A 14.1.3-9 FIGURE 14.1.3-9 Main Feedwater Temperature for the Increase in Steam Flow Event N/A 14.1.5.1-1 FIGURE 14.1.5.1-1 Normalized Core Power (0.20 ft2 Asymmetric Break Inside Containment)
N/A 14.1.5.1-2 FIGURE 14.1.5.1-2 Core Inlet Temperatures (0.20 ft2 Asymmetric Break Inside Containment)
N/A 14.1.5.1-3 FIGURE 14.1.5.1-3 Reactivity Feedback (0.20 ft2 Asymmetric Break Inside Containment)
N/A 14.1.5.1-4 FIGURE 14.1.5.1-4 Pressurizer Pressure (0.20 ft2 Asymmetric Break Inside Containment)
N/A 14.1.5.1-5 FIGURE 14.1.5.1-5 Steam Generator Pressures (0.20 ft2 Asymmetric Break Inside Containment)
N/A 14.1.5.1-6 FIGURE 14.1.5.1-6 Steam Mass Flow Rates (0.20 ft2 Asymmetric Break Inside Containment)
N/A 14.1.5.1-7 FIGURE 14.1.5.1-7 Normalized Power and Heat Flux (Asymmetric 3.51 ft2 Break Inside Containment with Loss of Offsite Power)
N/A 14.1.5.1-8 FIGURE 14.1.5.1-8 Reactor Coolant Temperatures (Asymmetric 3.51 ft2 Break Inside Containment with Loss of Offsite Power)
N/A 14.1.5.1-9 FIGURE 14.1.5.1-9 Normalized Reactor Coolant System Flow Rate (Asymmetric 3.51 ft2 Break Inside Containment with Loss of Offsite Power)
N/A 14.1.5.1-10 FIGURE 14.1.5.1-10 Pressurizer Pressure (Asymmetric 3.51 ft2 Break Inside Containment with Loss of Offsite Power)
N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 36 of 47 14.1.5.1-11 FIGURE 14.1.5.1-11 Steam Generator Pressures (Asymmetric 3.51 ft2 Break Inside Containment with Loss of Offsite Power)
N/A 14.1.5.2-1 FIGURE 14.1.5.2-1 One Pump High Pressure Safety Injection System Delivery vs.
Primary Pressure (Post-Scram Steam Line Break)
N/A 14.1.5.2-2 FIGURE 14.1.5.2-2 Steam Generator Break Flow (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)
N/A 14.1.5.2-3 FIGURE 14.1.5.2-3 Steam Generators' Secondary Pressures (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)
N/A 14.1.5.2-4 FIGURE 14.1.5.2-4 Core Inlet Temperatures (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)
N/A 14.1.5.2-5 FIGURE 14.1.5.2-5 Pressurizer Pressure (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)
N/A 14.1.5.2-6 FIGURE 14.1.5.2-6 Pressurizer Level (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)
N/A 14.1.5.2-7 FIGURE 14.1.5.2-7 Steam Generators' Secondary Mass (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)
N/A 14.1.5.2-8 FIGURE 14.1.5.2-8 Reactivity Components (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)
N/A 14.1.5.2-9 FIGURE 14.1.5.2-9 Reactor Power (HZP Post-Scram Steam Line Outside Containment Break with Offsite Power Available)
N/A 14.1.5.2-10 FIGURE 14.1.5.2-10 Steam Generator Break Flow (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)
N/A 14.1.5.2-11 FIGURE 14.1.5.2-11 Steam Generators' Secondary Pressures (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)
N/A 14.1.5.2-12 FIGURE 14.1.5.2-12 Core Inlet Temperatures (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)
N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 37 of 47 14.1.5.2-13 FIGURE 14.1.5.2-13 Pressurizer Pressure (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)
N/A 14.1.5.2-14 FIGURE 14.1.5.2-14 Pressurizer Level (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)
N/A 14.1.5.2-15 FIGURE 14.1.5.2-15 Reactivity Components (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)
N/A 14.1.5.2-16 FIGURE 14.1.5.2-16 Reactor Power (HZP Post-Scram Steam Line Outside Containment Break with Loss of Offsite Power)
N/A 14.2.1-1 FIGURE 14.2.1-1 Reactor Power Level for Loss of External Load (Primary Overpressurization Case)
N/A 14.2.1-2 FIGURE 14.2.1-2 Core Average Heat Flux for Loss of External Load (Primary Overpressurization Case)
N/A 14.2.1-3 FIGURE 14.2.1-3 Reactor Coolant System Temperatures for Loss of External Load (Primary Overpressurization Case)
N/A 14.2.1-4 FIGURE 14.2.1-4 Primary System Pressures for Loss of External Load (Primary Overpressurization Case)
N/A 14.2.1-5 FIGURE 14.2.1-5 Total Reactivity for Loss of External Load (Primary Overpressurization Case)
N/A 14.2.1-6 FIGURE 14.2.1-6 Reactor Power Level for Loss of External Load (Secondary Overpressurization Case)
N/A 14.2.1-7 FIGURE 14.2.1-7 Core Average Hot Flux for Loss of External Load (Secondary Overpressurization Case)
N/A 14.2.1-8 FIGURE 14.2.1-8 Reactor Coolant System Temperatures for Loss of External Load (Secondary Overpressurization Case)
N/A 14.2.1-9 FIGURE 14.2.1-9 Pressurizer Pressure for Loss of External Load (Secondary Overpressurization Case)
N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 38 of 47 14.2.1-10 FIGURE 14.2.1-10 Total Reactivity for Loss of External Load (Secondary Overpressurization Case)
N/A 14.2.1-11 FIGURE 14.2.1-11 Maximum Secondary System Pressures for Loss of External Load (Secondary Overpressurization Case)
N/A 14.2.1-12 FIGURE 14.2.1-12 Reactor Power Level for Loss of External Load (MDNBR Case)
N/A 14.2.1-13 FIGURE 14.2.1-13 Normalized Heat Flux for Loss of External Load (MDNBR Case)
N/A 14.2.1-14 FIGURE 14.2.1-14 Reactor Coolant System Temperature for Loss of External Load (MDNBR Case)
N/A 14.2.1-15 FIGURE 14.2.1-15 Pressurizer Pressure for Loss of External Load (MDNBR Case)
N/A 14.2.1-16 FIGURE 14.2.1-16 Total Reactivity for Loss of External Load (MDNBR Case)
N/A 14.2.1-17 FIGURE 14.2.1-17 Maximum Secondary System Pressure for Loss of External Load (MDNBR Case)
N/A 14.2.4-1 FIGURE 14.2.4-1 Reactor Power Level for MSIV Closure (Lower Steam Flow Case)
N/A 14.2.4-2 FIGURE 14.2.4-2 Reactor Coolant System Temperatures for MSIV Closure (Lower Steam Flow Case)
N/A 14.2.4-3 FIGURE 14.2.4-3 Pressurizer Pressure for MSIV Closure (Lower Steam Flow Case)
N/A 14.2.4-4 FIGURE 14.2.4-4 Isolated Steam Generator Pressure at Bottom of Boiler Region for MSIV Closure (Lower Steam Flow Case))
N/A 14.2.4-5 FIGURE 14.2.4-5 Open MSIV Steam Generator Steam Dome Pressure for MSIV Closure (Lower Steam Flow Case))
N/A 14.2.7-1 FIGURE 14.2.7-1 Reactor Coolant System Loop Temperatures for Minimum Steam Generator Inventory Case: Offsite Power Available, B Motor-Driven AFW Pump Fails to Start N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 39 of 47 14.2.7-2 FIGURE 14.2.7-2 Steam Generator Dome Pressure for Minimum Steam Generator Inventory Case: Offsite Power Available, B Motor-Driven AFW Pump Fails to Start N/A 14.2.7-3 FIGURE 14.2.7-3 Pressurizer Level for Minimum Steam Generator Inventory Case:
Offsite Power Available, B Motor-Driven AFW Pump Fails to Start N/A 14.2.7-4 FIGURE 14.2.7-4 Steam Generator for Liquid Mass Inventory for Minimum Steam Generator Inventory Case: Offsite to Power Available, B Motor-Driven AFW Pump Fails to Start N/A 14.2.7-5 FIGURE 14.2.7-5 Steam Generator Collapsed Liquid Level for Minimum Steam Generator Inventory Case: Offsite to Power Available, B Motor-Driven AFW Pump Fails to Start N/A 14.2.7-6 FIGURE 14.2.7-6 Reactor Coolant System Loop Temperatures for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A 14.2.7-7 FIGURE 14.2.7-7 Steam Generator Dome Pressure for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A 14.2.7-8 FIGURE 14.2.7-8 Pressurizer Level for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A 14.2.7-9 FIGURE 14.2.7-9 Steam Generator Liquid Mass Inventory for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A 14.2.7-10 FIGURE 14.2.7-10 Steam Generator Collapsed Liquid Level for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start N/A 14.3.1-1 FIGURE 14.3.1-1 Reactor Power Level for Loss of Forced Reactor Coolant Flow N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 40 of 47 14.3.1-2 FIGURE 14.3.1-2 Core Average Heat Flux for Loss of Forced Reactor Coolant Flow N/A 14.3.1-3 FIGURE 14.3.1-3 Reactor Coolant System Temperature for Loss of Forced Reactor Coolant Flow N/A 14.3.1-4 FIGURE 14.3.1-4 Pressurizer Pressure for Loss of Forced Reactor Coolant Flow N/A 14.3.1-5 FIGURE 14.3.1-5 Reactivities for Loss of Forced Reactor Coolant Flow N/A 14.3.1-6 FIGURE 14.3.1-6 Primary Coolant Flow Rate for Loss of Forced Reactor Coolant Flow N/A 14.3.1-7 FIGURE 14.3.1-7 Secondary Pressure for Loss of Forced Reactor Coolant Flow N/A 14.3-3-1 FIGURE 14.3-3-1 Reactor Power Level for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-2 FIGURE 14.3-3-2 Core Average Heat Flux for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-3 FIGURE 14.3-3-3 Reactor Coolant System Temperatures for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-4 FIGURE 14.3-3-4 Pressurizer Pressure for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-5 FIGURE 14.3-3-5 Reactivities for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-6 FIGURE 14.3-3-6 Primary Coolant Flow Rate for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-7 FIGURE 14.3-3-7 Secondary Pressure for Reactor Coolant Pump Rotor Seizure N/A 14.4.1-1 FIGURE 14.4.1-1 Reactor Power Level for Low Power Bank Withdrawal N/A 14.4.1-2 FIGURE 14.4.1-2 Core Average Heat Flux for Low Power Bank Withdrawal N/A 14.4.1-3 FIGURE 14.4.1-3 Reactor Coolant Temperatures for Low Power Bank Withdrawal N/A 14.4.1-4 FIGURE 14.4.1-4 Pressurizer Pressure for Low Power Bank Withdrawal N/A 14.4.1-5 FIGURE 14.4.1-5 Reactivities for Low Power Bank Withdrawal N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 41 of 47 14.4.2-1 FIGURE 14.4.2-1 Reactor Core Power for an Uncontrolled Bank Withdrawal at Power N/A 14.4.2-2 FIGURE 14.4.2-2 Core Average Heat Flux for an Uncontrolled Bank Withdrawal at Power N/A 14.4.2-3 FIGURE 14.4.2-3 Reactor Coolant System Temperatures for an Uncontrolled Bank Withdrawal at Power N/A 14.4.2-4 FIGURE 14.4.2-4 Pressurizer Pressure for an Uncontrolled Bank Withdrawal at Power N/A 14.4.2-5 FIGURE 14.4.2-5 Reactivities for an Uncontrolled Bank Withdrawal at Power N/A 14.4.2-6 FIGURE 14.4.2-6 Secondary Pressure for an Uncontrolled Bank Withdrawal at Power N/A 14.4.3.1-1 FIGURE 14.4.3.1-1 Reactor Power Level for the Limiting Dropped Control Rod/Bank Case N/A 14.4.3.1-2 FIGURE 14.4.3.1-2 Reactor Coolant System Temperatures for the Limiting Dropped Control Rod/Bank Case N/A 14.4.3.1-3 FIGURE 14.4.3.1-3 Pressurizer Pressure for the Limiting Dropped Control Rod/Bank Case N/A 14.4.3.1-4 FIGURE 14.4.3.1-4 Secondary Pressure for the Limiting Dropped Control Rod/Bank Case N/A 14.4.8-1 FIGURE 14.4.8-1 Core Power for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)
N/A 14.4.8-2 FIGURE 14.4.8-2 Core Average Heat Flux for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)
N/A 14.4.8-3 FIGURE 14.4.8-3 Reactor Coolant System Temperatures for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)
N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 42 of 47 14.4.8-4 FIGURE 14.4.8-4 Pressurizer Pressure for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)
N/A 14.4.8-5 FIGURE 14.4.8-5 Reactivities for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)
N/A 14.4.8-6 FIGURE 14.4.8-6 Secondary Pressure for a CEA Ejection (Minimum Departure for Nucleate Boiling Ratio Case)
N/A 14.4.8-7 FIGURE 14.4.8-7 Core Power for a CEA Ejection (Overpressure)
N/A 14.4.8-8 FIGURE 14.4.8-8 Core Average Heat Flux for a CEA Ejection (Overpressure)
N/A 14.4.8-9 FIGURE 14.4.8-9 Primary System Temperatures for a CEA Ejection (Overpressure)
N/A 14.4.8-10 FIGURE 14.4.8-10 Pressurizer Pressure for a CEA Ejection (Overpressure)
N/A 14.4.8-11 FIGURE 14.4.8-11 Reactivities for a CEA Ejection (Overpressure)
N/A 14.4.8-12 FIGURE 14.4.8-12 Secondary Pressure for a CEA Ejection (Overpressure)
N/A 14.6.1-1 FIGURE 14.6.1-1 Reactor Power Level for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)
N/A 14.6.1-2 FIGURE 14.6.1-2 Core Average Heat Flux for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)
N/A 14.6.1-3 FIGURE 14.6.1-3 Reactor Coolant System Temperatures for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)
N/A 14.6.1-4 FIGURE 14.6.1-4 Pressurizer Pressure for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)
N/A 14.6.1-5 FIGURE 14.6.1-5 Reactivities for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)
N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 43 of 47 14.6.1-6 FIGURE 14.6.1-6 Secondary Pressure for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve (Rated Power)
N/A 14.6.3-1 FIGURE 14.6.3-1 Steam Generator Tube Rupture with the Loss of Offsite Power RCS Temperature Versus Time N/A 14.6.3-2 FIGURE 14.6.3-2 Steam Generator Tube Rupture with the Loss of Offsite Power Pressurizer Level Versus Time N/A 14.6.3-3 FIGURE 14.6.3-3 Steam Generator Tube Rupture with the Loss of Offsite Power Pressurizer Pressure Versus Time N/A 14.6.3-4 FIGURE 14.6.3-4 Steam Generator Tube Rupture with the Loss of Offsite Power Steam Generator Pressure Versus Time N/A 14.6.3-5 FIGURE 14.6.3-5 Steam Generator Tube Rupture with the Loss of Offsite Power Total Break Flow Rate Versus Time N/A 14.6.3-6 FIGURE 14.6.3-6 Steam Generator Tube Rupture with the Loss of Offsite Power Flashed Break Flow Rate Versus Time N/A 14.6.3-7 FIGURE 14.6.3-7 Steam Generator Tube Rupture with the Loss of Offsite Power Atmospheric Dump Valve Flow Rate per Steam Generator Versus Time N/A 14.6.3-8 FIGURE 14.6.3-8 Steam Generator Tube Rupture with the Loss of Offsite Power Main Steam Safety Valve Flow Rates per Steam Generator Versus Time N/A 14.6.3-9 FIGURE 14.6.3-9 Steam Generator Tube Rupture with the Loss of Offsite Power Auxiliary Feedwater Flow Versus Time N/A 14.6.5.1-1 FIGURE 14.6.5.1-1 Scatter Plot Operational Parameters N/A 14.6.5.1-2 FIGURE 14.6.5.1-2 PCT Versus PCT Time Scatter Plot N/A 14.6.5.1-3 FIGURE 14.6.5.1-3 PCT Versus PCT Time Scatter Plot N/A 14.6.5.1-4 FIGURE 14.6.5.1-4 Maximum Local Oxidation Versus PCT Scatter Plot N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 44 of 47 14.6.5.1-5 FIGURE 14.6.5.1-5 Total Core Wide Oxidation Versus PCT Scatter Plot N/A 14.6.5.1-6 FIGURE 14.6.5.1-6 Peak Cladding Temperature (Independent of Elevation) for the Demonstration Case N/A 14.6.5.1-7 FIGURE 14.6.5.1-7 Break Flow for the Demonstration Case N/A 14.6.5.1-8 FIGURE 14.6.5.1-8 Core Inlet Mass Flux for the Demonstration Case N/A 14.6.5.1-9 FIGURE 14.6.5.1-9 Core Outlet Mass Flux for the Demonstration Case N/A 14.6.5.1-10 FIGURE 14.6.5.1-10 Void Fraction at RCS Pumps for the Demonstration Case N/A 14.6.5.1-11 FIGURE 14.6.5.1-11 ECCS Flows (Includes SIT, HPSI and LPSI) for the Demonstration Case N/A 14.6.5.1-12 FIGURE 14.6.5.1-12 Upper Plenum Pressure for the Demonstration Case N/A 14.6.5.1-13 FIGURE 14.6.5.1-13 Collapsed Liquid Level in the Downcomer for the Demonstration Case N/A 14.6.5.1-14 FIGURE 14.6.5.1-14 Collapsed Liquid Level in the Lower Plenum for the Demonstration Case N/A 14.6.5.1-15 FIGURE 14.6.5.1-15 Collapsed Liquid Level in the Core for the Demonstration Case N/A 14.6.5.1-16 FIGURE 14.6.5.1-16 Containment and Loop Pressures for the Demonstration Case N/A 14.6.5.1-17 FIGURE 14.6.5.1-17 Pressure Differences between Upper Plenum and Downcomer for the Demonstration Case N/A 14.6.5.2-1 FIGURE 14.6.5.2-1 Peak Cladding Temperature Versus Break Size (SBLOCA Break Spectrum)
N/A 14.6.5.2-2 FIGURE 14.6.5.2-2 Reactor Power - 3.78-Inch Break N/A 14.6.5.2-3 FIGURE 14.6.5.2-3 Primary and Secondary System Pressures - 3.78-Inch Break N/A 14.6.5.2-4 FIGURE 14.6.5.2-4 Break Mass Flow Rate - 3.78-Inch Break N/A 14.6.5.2-5 FIGURE 14.6.5.2-5 Break Vapor Void Fraction - 3.78-Inch Break N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 45 of 47 14.6.5.2-6 FIGURE 14.6.5.2-6 Loop Seal Void Fraction - 3.78-Inch Break N/A 14.6.5.2-7 FIGURE 14.6.5.2-7 Total Core Inlet Mass Flow Rate - 3.78-Inch Break N/A 14.6.5.2-8 FIGURE 14.6.5.2-8 Downcomer Collapsed Liquid Level - 3.78-Inch Break N/A 14.6.5.2-9 FIGURE 14.6.5.2-9 Inner and Outer Core Collapsed Liquid Level - 3.78-Inch Break N/A 14.6.5.2-10 FIGURE 14.6.5.2-10 Reactor Vessel Mass - 3.78-Inch Break N/A 14.6.5.2-11 FIGURE 14.6.5.2-11 RCS Loop Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-12 FIGURE 14.6.5.2-12 Steam Generator Main Feedwater Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-13 FIGURE 14.6.5.2-13 Steam Generator Auxiliary Feedwater Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-14 FIGURE 14.6.5.2-14 Steam Generator Total Mass - 3.78-Inch Break N/A 14.6.5.2-15 FIGURE 14.6.5.2-15 Steam Generator Narrow Range Level % - 3.78-Inch Break N/A 14.6.5.2-16 FIGURE 14.6.5.2-16 High Pressure Safety Injection Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-17 FIGURE 14.6.5.2-17 Low Pressure Safety Injection Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-18 FIGURE 14.6.5.2-18 Safety Injection Tank Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-19 FIGURE 14.6.5.2-19 Integrated Break Flow And ECCS Flow - 3.78-Inch Break N/A 14.6.5.2-20 FIGURE 14.6.5.2-20 Hot Assembly Collapsed Liquid Level - 3.78-Inch Break N/A 14.6.5.2-21 FIGURE 14.6.5.2-21 Hot Assembly Mixture Level - 3.78-Inch Break N/A 14.6.5.2-22 FIGURE 14.6.5.2-22 Peak Cladding Temperature At Pct Location (11.02 Ft) - 3.78-Inch Break N/A 14.6.5.2-23 FIGURE 14.6.5.2-23 (DELETED by FSARCR 00-MP2-023)
N/A 14.6.5.2-24 FIGURE 14.6.5.2-24 (DELETED by FSARCR 00-MP2-023)
N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 46 of 47 14.6.5.3-1 FIGURE 14.6.5.3-1 Long Term Cooling Plan N/A 14.6.5.3-2 FIGURE 14.6.5.3-2 Reactor Coolant System Refill Time vs. Break Area N/A 14.6.5.3-3 FIGURE 14.6.5.3-3 Core Flush by Hot Side Injection for a Double-Ended Guillotine Cold Leg Break N/A 14.6.5.3-4 FIGURE 14.6.5.3-4 Inner Vessel Boric Acid Concentration vs. Time for a Double-Ended Guillotine Cold Leg Break N/A 14.8.2-1 FIGURE 14.8.2-1 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Containment Pressure vs. Time N/A 14.8.2-2 FIGURE 14.8.2-2 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Containment Temperature vs. Time N/A 14.8.2-3 FIGURE 14.8.2-3 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Mass Flow Rate vs. Time N/A 14.8.2-4 FIGURE 14.8.2-4 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Energy Release Rate vs. Time N/A 14.8.2-5 FIGURE 14.8.2-5 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Integrated Mass Flow vs. Time N/A 14.8.2-6 FIGURE 14.8.2-6 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Integrated Energy Release vs. Time N/A 14.8.2-7 FIGURE 14.8.2-7 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Affected Steam Generator Pressure vs. Time N/A LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet
Revision 3906/30/21 MPS-2 FSAR Page 47 of 47 14.8.2-8 FIGURE 14.8.2-8 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Unaffected Steam Generator Pressure vs. Time N/A 14.8.2-9 FIGURE 14.8.2-9 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA Affected Steam Generator Liquid Mass vs. Time N/A 14.8.3-1 FIGURE 14.8.3-1 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-2 FIGURE 14.8.3-2 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-3 FIGURE 14.8.3-3 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-4 FIGURE 14.8.3-4 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-5 FIGURE 14.8.3-5 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-6 FIGURE 14.8.3-6 Deleted by FSARCR 04-MP2-018 N/A a.
Incorporated by reference this engineering controlled drawing is, coincidentally, an MPS-2 FSAR figure. Refer to the controlled plant drawing for the latest revision.
LIST OF EFFECTIVE FIGURES (CONTINUED)
Figure Number Figure Label Title Drawing Number Sheet