ML22193A135

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5 to Updated Final Safety Analysis Report
ML22193A135
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 06/23/2022
From:
Dominion Energy Nuclear Connecticut
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22193A089 List:
References
22-195
Download: ML22193A135 (144)
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Text

MILLSTONE POWER STATION UNIT 3 INAL SAFETY ANALYSIS REPORT Revision 3506/30/22

Revision 3506/30/22 Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

35 06/30/22 MP3-UCR-2020-013 6.2.2.3, Table 9.2-1, Table Update Required SW Flow Rate, Heat Transfer 9.2.-2 MP3 SW Heat Exchangers CR1166683 35 06/30/22 MP3-UCR-2021-014 Table 6.2-65 Update to Correct the Closure Stroke Time Requirement for 3QSS*MOV34/AB CR1170181/CA8451868 35 06/30/22 MP3-UCR-2021-015 5.4.3.2 Pressurizer Small Class 2 Steam Space Lines U As-Is Disposition ETE-MP-2021-1041 35 06/30/22 MP3-UCR-2021-016 Appendix 7.5A Deviation Actual Indicated Range Change for 3HVR*FT1 Number 29, Table 7.5-1 Item SLCRS Process Flow to Millstone Stack E3 ETE-MP-2021-1065 35 06/30/22 MP3-UCR-2021-017 Table 1.3-12, Table 1.3-14, Abandonment of Waste Evaporator System (RE Table 3.6-1, 9.2.2.1, 9.2.8, 0786) 9.3.3, 9.3.3.2.2, 9.3.5.2, PA 7376113, REA 0786 Table 9.3-1, 10.4.10, 11.2.2.1, Table 11.2-2, Table 11.2-3, 11.3, 11.4, 11.4.2.1.2, Table 11.4-4, 12.3.2.1, FPER

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

35 06/30/22 MP3-UCR-2021-018 4.1, 4.2, 4.3.1, 4.3.2, 4.4.2, Millstone Unit 3 Measurement Uncertainty 4.4.3, 4.4.4, 4.4.7, 6.2.1, Recapture Safety Analysis Implementing ETE 11.2.3, 11.3.3, 15.0.3, 15.0.8, FSAR Package 15.1.1, 15.1.2, 15.1.3, 15.1.4, ETE-NAF-2021-0020 15.2.3, 15.2.6, 15.2.7, 15.2.8, 15.4.1, 15.4.2, 15.4.3, 15.5.1, 15.5.2, 15.6.1, 15.6.3, Tables 4.4-1, 4.1-2, 4.4-1, 6.2-1, 6.2-6H, 6.2-7, 6.2-23, 15.0-1, 15.0-2, 15.0-3, 15.1-3, 15.4-3, 5.4-5, 15.6-3, 15.6-9, 15.6-15, Figures 4.4-8, 6.2-8, 15.4-10, 15.5-1, 15.5-2 35 06/30/22 MP3-UCR-2021-019 10.4.5.1, 10.4.5.2 Clarification of MPS3 Screen Wash System Bac up Functions Design Change Notice DM2-01-0124-08 35 06/30/22 MP3-UCR-2022-003 4.3.1.5, 4.3.2.6, List of Millstone Unit 3 NRC Identified Omission and Figures 9.1.2.2, Figure 9.1- Grammatical Errors Corrections 22 CR1191483 34.02 01/27/21 MP3-UCR-2016-016 FPER Section 5.5 Analysis The Fire Protection Evaluation Report (FPER) i 20 updated to reflect the new types of combustible materials installed in fire area CSW-2 by DC MPG-15-01053 MPG-15-01053 34.02 01/27/21 MP3-UCR-2020-010 Figure 8.1-3 345kV Switch 15G-10T-4 Replacement MP2-19-01182

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

34.02 01/27/21 MP3-UCR-2021-024 Table 1.10-1 Update "Design Control Manual" Historical Reference in Table 1.10-1 TMI Action Items PA8379726 34.01 09/30/21 MP3-UCR-2018-011 FPER Sections 4.1.4 and 5.5 Fire Detection System Upgrade, Zone Panel 2 MP3-18-00189 34.01 09/30/21 MP3-UCR-2018-018 9.5.2, FPER 4.5 FSAR change to update Communications Syste for replacement of Trunked Radio System.

MPG-15-01007, CR499771 34.01 09/30/21 MP3-UCR-2020-012 5.4.7.2.1, 5.4.7.2.2, 6.3.2.2.3, Non-substantive change to the maximum flow r Figure 5.4-6, Table 5.4-9 set point of the RHS mini-flow MOVs to close CR1148061/CA8046113 34.01 09/30/21 MP3-UCR-2021-008 19.2.1.16, Table 19.6-1 Deletion of Chapter 19 Commitment 14 ETE-MP-2021-1028 Revision 3406/30/21 Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

34 06/30/21 MP3-UCR-2021-003 1.11, 17.1 Incorporating Quality Assurace Program Description by Reference CA8102163 33.02 03/31/21 MP3-UCR-2013-028 2.1.2.5 Reflects update to discussion of ISFSI.

MPG-13-01192

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

33.02 03/31/21 MP3-UCR-2015-022 9.5.3.1, FPER Analysis 56, Update the SAR to upgrade the existing lighting FPER Analysis 57 on the 52'-4" elevation of the Fuel Building to support the transfer cask and DSC preparation activities at the loading area location.

MP3-15-01021 33.02 03/31/21 MP3-UCR-2016-011 Figure 3.9N-4 Reflects CRDM Eye Bolt Leakage Repair.

DC: MP3-16-01053 33.02 03/31/21 MP3-UCR-2016-019 8.1.3 MP3 FSAR Update To Document The Addition Of The Open Phase Detection Relay Schemes O The High Voltage Side Of The Generator Step-u And Rsst Transformers MP3-15-01027 33.02 03/31/21 MP3-UCR-2018-008 1.8, Table 1.8-1 Unit 3 SAR change for TSTF-522, Revision 0, "Revise Ventilation System Surveillance Requirements to Operate for 10 Hours per Month."

LBDCR 18-MP3-009 33.02 03/31/21 MP3-UCR-2018-019 Table 10.3-2 Update to Table 10.3-2 "Materials of Main Stea Safety Valves" MP3-18-01086 33.02 03/31/21 MP3-UCR-2019-016 3.1.2.62, 4.3.1.5, 4.3.2.6, Millstone Unit 3 Spent Fuel Pool Criticality and 9.1.1.1, 9.1.1.3, 9.1.2.1, New Fuel Storage Area Analysis.

9.1.2.2, 9.1.2.3, 9.1.3.2, LBDCR 17-MP3-009, LA7438725 9.1.4.2.1, 9.1.6, Figure 9.1-22

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

33.02 03/31/21 MP3-UCR-2019-025 Table 3.6-4, Figure 3.8-62 3CCE*E1A Small Bore Piping Tie-In (Sheets 1,2,&9 of 10), MP3-18-00117 9.2.2.4.2, Tables 9.2-2 and 9.2-10, FPER Section 5 Analysis 2, FPER Section 5 Analysis 5 33.02 03/31/21 MP3-UCR-2019-027 Figure 8.1-1 Reserve Station Service Transformer Primary Disconnect Switch Replacements MP3-18-01083 33.02 03/31/21 MP3-UCR-2020-002 Figure 8.1-3 345kV Switch 15G-18T-8 Replacement MP3-18-01094 33.02 03/31/21 MP3-UCR-2020-007 FPER Analysis 74, FPER Reserve Station Service Transformer Analysis 75 Replacements MP3-18-01082 33.02 03/31/21 MP3-UCR-2020-011 6.2.6.4 Containment Isolation Valve Testing (Type C)

Frequency Increase from 60 Months to 75 Mon MP3 Technical Specification Amendment 276 Type A and Type C Test Intervals 33.02 03/31/21 MP3-UCR-2020-015 7.7.1.3.2 Digital Rod Position Indication System Coil #2 for H12 Temporary Bypass Information Update MP3-19-01096

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

33.02 03/31/21 MP3-UCR-2020-014 Table 6.2-7A Correct the decay heat generation rate value for 40,000 seconds in MPS3 FSAR Table 6.2-7A to match that presented and approved in FSARCR 07-MP3-038 CR1159059 and CA8197216 33.02 03/31/21 MP3-UCR-2020-018 9.5.1 Replacing ENRS (ARCOS) with DEENS (Everbridge)

MP-20-04 EP-AA-101-Attachment 2, 50.54(q), for change from Emergency Notificati

& Response System (ENRS) to Dominion Ener Emergency Notification System (DEENS) 33.02 03/31/21 MP3-UCR-2020-015 7.7.1.3.2 Digital Rod Position Indication System Coil #2 for H12 Temporary Bypass Information Update MP3-19-01096 33.02 03/31/21 MP3-UCR-2020-014 Table 6.2-7A Correct the decay heat generation rate value for 40,000 seconds in MPS3 FSAR Table 6.2-7A to match that presented and approved in FSARCR 07-MP3-038 CR1159059 and CA8197216 33.02 03/31/21 MP3-UCR-2020-018 9.5.1 Replacing ENRS (ARCOS) with DEENS (Everbridge)

MP-20-04 EP-AA-101-Attachment 2, 50.54(q), for change from Emergency Notificati

& Response System (ENRS) to Dominion Ener Emergency Notification System (DEENS)

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

33.01 09/30/20 MP3-UCR-2015-024 Figure 8.1-3 Update the SAR to reflect Eversource replacement of the PT installed on the "A" pha of 310-15G-2H with a CCVT as part of the Millstone 15G Substation, High Creep Insulator Project ETE-MP-2020-1020 33.01 09/30/20 MP3-UCR-2019-020 12.5 Change "annual retraining" frequency to "period retraining" in Chapter 12, Section 12.5 of Unit FSAR. Provide exemption statement to Regulatory Guide 8.27, Revision 0 for recommended annual retraining frequency.

CR1116135/CA7524012 and Efficiency Bulleti 16-26b 33.01 09/30/20 MP3-UCR-2020-001 9.2.1.2, 9.2.1.4, 19.2.1.20 MP3 Service Water Thermal Performance Testi Elimination ETE-MP-2019-1084 33.01 09/30/20 MP3-UCR-2020-008 6.2.1.1, 6.2.1.2, 6.2.1.3, Implementation of PWROG-17034-P-A 6.2.1.4, 6.2.7 ETE-NAF-2020-0057 33.01 09/30/20 MP3-UCR-2020-009 15.3.3.2, 15.2-2, Figure 15.3- Update MPS3 Locked Rotor Event for Reactor 10 Note Coolant System Overpressure to address legacy issue in NSAL-09-2 ETE-NAF-2020-0053

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

33 06/30/20 MP3-UCR-2019-026 3.6.2.1.2.2.f, 3.6.3.3.6-14, Risk informed methodology reference now bein 6.6.3 credited within the ISI Program ETE-MP-2019-1004 32.01 03/31/20 MP3-UCR-2019-019 Table 3.2-1, 9.2.1.3, 9.5.8.3, Tornado Missile Protection Documentation Issu 10.3.3, 10.4.9.3 CR112287 32.01 03/31/20 MP3-UCR-2019-024 15.7.4, Table 1.7-8, Table FHA drop of a Non-Spent Fuel Assembly.

15.6-12, table 15.0-8 ETE-NAF-2019-0110 32.01 03/31/20 MP3-UCR-2020-003 9.5.3.1 High-bay/Medium-height Lighting Clarification 32.01 03/31/20 MP3-UCR-2019-022 15.8 Updated ATWS Analysis for Millstone Unit 3 ETE-NAF-2019-0094 32.01 03/31/20 MP3-UCR-2018-017 Table 6.2-65, Table 6.3-70 MP3 10CFR50 Appendix J Reduction of Containments Isolation Valve Test Requirement associated with ETE-MP-2018-1006.

32.01 03/31/20 MP3-UCR-2019-021 9.5 Unit 3 SAR change allowing Jacket Water mak up to the Emergency Diesel Generators.

ETE-MP-2019-1080 32.01 03/31/20 MP3-UCR-2018-009 4.1.4, 5.5 Fire Detection System Upgrade, Control Room Console and Zone Panel 7.

MP3-18-00187 32.01 03/31/20 MP3-UCR-2019-015 Table 15.0-2, 15.5.1, 15.5.2, Implementation of Safety Analysis for Inadverte 15.5.4 (References) Operation of ECCS.

ETE-NAF-2019-0033

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

32.01 03/31/20 MP3-UCR-2016-023 8.3.1.1.1, Fig. 8.1-1 FSAR, MP3 NSST Replacement.

FPER MP3-16-01121 32.01 03/31/20 MP3-UCR-2019-010 FSAR 9.5.7 Raise MP3 EDG Lube Oil Low Temperature Alarm (3EGO*TS25A/B)

MP3-19-01021 32.01 03/31/20 MP3-UCR-2019-006 FSAR SAR Change for Replacement MP3 Vacuum Priming Piping.

MP3-18-01102

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

32.01 03/31/20 MP3-UCR-2019-003 4.3.1.5, 4.3.2.1, 4.3.2.2, Implementation of Dominion Reload Core Desi 4.3.2.2.6, 4.3.2.3, 4.3.2.3.1, and Safety Analysis Methods 4.3.2.3.2, 4.3.2.3.3, 4.3.2.3.4, ETE-NAF-2019-005 4.3.2.4.9, 4.3.2.7.6, 4.3.3, 4.3.3.1, 4.3.3.2, 4.3.3.3, 4.3.4, 4.4.1.1, 4.4.1.5, 4.4.2.2, 4.4.2.2.1, 4.4.2.2.2, 4.4.2.2.3, 4.4.2.2.4, 4.4.2.4, 4.4.2.9.5, 4.4.2.9.8, 4.4.2.7.3, 4.4.2.11.6, 4.4.4.2, 4.4.4.3, 4.4.4.5, 4.4.4.7, 15.0.3.1, 15.0.3.2, 15.0.3.3, 15.0.10.2, 15.0.10.3, 15.0.10.4, 15.0.10.6, 15.0.10.7, 15.0.11, 15.1.2.2, 15.1.3.2, 15.1.4.1, 15.1.5.1, 15.1.5.2, 15.1.5.3, 15.1.6, 15.2.3.3, 15.2.9, 15.3.1.2, 15.3.2.2, 15.3.5, 15.4.1.2, 15.4.2.2, 14.4.3.2, 15.4.6.2, 15.4.8.2.1, 15.4.9, 15.6.1.2, 15.6.7, Figures: 15.0-1, 15.1-2, 15.1-11, 15.1-14, 15.1-15, 15.1-15A, 15.1-16, 15.1-16A, 15.1-17, 15.1-17A, 15.2-4, 15.3-4, 15.3-8, 15.3-16, 15.4-1, 15.4-3, 15.4-4, 15.4-5, 15.4-6, 15.4-7, 15.4-8, 15.4-9, 15.4-10, 15.4-11, 15.4-12, 15.6-1,

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

32.01 03/31/20 MP3-UCR-2019-003 Tables: 4.1-1, 4.1-2, 4.4-1, (cont) 4.4-4(new), 15.0-2, 15.0-4, 15.1-1, 15.4-1, 15.4.2 (deleted)

Revision 3206/27/19 Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

32 06/27/19 MP3-UCR-2019-009 4.2.2.3.1, 4.2.2.3.1.1, 4.2.2.3.3 Millstone Unit 3 FSAR Changes associated with the Cycle 20 Reload Safety Evaluation.

EVAL-ENG-RESE-M3C20 32 06/27/19 MP3-UCR-2019-013 8.3.2.1.2.4, 8.3.2.1.2.2, 1.8-10, Extending Frequencies of Unit 3 Battery Discharge 1.8-60 Testing and Battery Charger Load Testing, as specifi in STI-M3-2017-002.

STI-M3-2017-002, ETE-MP-2019-1024 31.2 12/28/18 MP3-UCR-2017-010 Table 1.7-1, 6.3.3.2, 6.3.4.2, Revise FSAR Table 6.3-10 to be consistent with Tab Table 6.3-10, 7.3.1.1.5, 3.9N-11 per ACE CA3054810. Revise Section 6.3.4 Table 7.4-1, 8.3.1.1.3 to clarify that specifically one charging can be out o service for maintenance.

ACE CA3054810 31.2 12/28/18 MP3-UCR-2018-020 4.4.64 Loose Parts Monitor MP3-UCR-2018-005 31.1 09/27/18 MP3-UCR-2016-017 10.3.5, 10.4.7.2 Addition of Polymeric Dispersant feedwater system MP3-16-01046

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

31.1 09/27/18 MP3-UCR-2018-005 4.4.6.4 Loose Parts Monitoring System update.

LBDCR 18-MP3-008, TRM 3.3.3.8 31.1 09/27/18 MP3-UCR-2018-006 9.5.6.2, 9.5.6.5 Setpoint Change A and B EGA Starting Air.

MP3-18-00150, MPE-18-00151 31.1 09/27/18 MP3-UCR-2018-007 Table 9.2-1 Update of FSAR Table 9.2-1 to reflect EDG Downtu Coating.

ETE-MP-2017-1100 Revision 3106/28/18 Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 except Release Date (Sections, Tables, Figures) where indicated in brackets.

31 06/28/18 MP3-UCR-2015-001 9.2.2.1.2, 9.3.1.1.1, 9.3.1.1.2 Reflects updates to provide clarification text for shutdown air compressors.

OP 3332A-001, OP 3332A-004, OP 3332A-015, OP 3332A-030, DCR M3-97005, CR285627 30.3 03/29/18 MP3-UCR-2017-004 2.3.3.3 Data Recording Systems and Data Processing, is updat to reflect the removal of the EDAN field minicompute from the Meteorological instrument shelters at the Primary and Backup Mast locations and their relocatio to the MPS Datacenter.

DC: MPG-16-01139 30.3 03/29/18 MP3-UCR-2018-001 Table 6.3-7 Update FSAR Table 6.3-7 Switchover procedure to agr with EOP ES-1.3 Transfer to Cold Leg Recirculation.

LA3019642

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 except Release Date (Sections, Tables, Figures) where indicated in brackets.

30.3 03/29/18 MP3-UCR-2018-004 5.4.1.3.1 Update MP3 Reactor Coolant Pump Seal Materials.

DC: MP3-13-01055 DC: MP3-14-01022 CR: CR1083652 30.2 12/28/17 MP3-UCR-2017-008 9.5.10.2, 11.5.2.2.8 Missed updates of the hydrogen monitoring system modification M3-04007 DCR: M3-04007 30.2 12/28/17 MP3-UCR-2017-018 4.1, 4.2.1, 4.2.1.1, 4.2.2, FSAR Change No. in order to support the M3C19 relo 4.2.2.3.3, 4.2.4.2, 15.0.3.2, EVAL-ENG-RSE-M3C19 15.2.7.2, 15.5.1.1, Table 15.6-2 30.1 09/28/17 MP3-UCR-2015-031 11.2.2.1, 11.4.1, 11.4.2.2, Replacement of the Portable resin handling and 11.4.2.2.2, 11.4.2.7 dewatering system with a vendor supplied solid radioactive waste processing system.

MP3-15-01066 30.1 09/28/17 MP3-UCR-2016-004 8.1.3, 8.2.2 Eversource 15G Breaker Failure Relay Replacement.

ETE-MP-2015-1186 30.1 09/28/17 MP3-UCR-2016-008 FPER Section 5.5 - Analysis Replacement of the portable handling and dewatering 90 system with the Energy Solutions ALPS/AIM and SE systems.

MP3-15-01066 30.1 09/28/17 MP3-UCR-2016-015 List of Effective Figures, Installation of a backup electric motor-driven air 9.3.1.3 (new), FPER compressor and desiccant air dryer powered by a diese Section 5.5 Analysis 87, FPER generator that will be connected to the MP3 Instrumen Section 5.5 Analysis 101 Air System (IAS).

(new) MP3-15-01137

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 except Release Date (Sections, Tables, Figures) where indicated in brackets.

30.1 09/28/17 MP3-UCR-2016-022 8.1.1, 8.1.3, 8.1.4, Figure 8.1- Eversource Energy proposes to reconfigure the 345kV 2, Figure 8.1-3, 8.2.1, 8.2.2, Millstone - Haddam - Beseck 348 03.

Figure 8.2-2 ETE-MP-2016-1135 30.1 09/28/17 MP3-UCR-2017-007 Table 9.3-6 Unit 3 Reactor Coolant Pump Seal Replacement additional FSAR changes missed during the initial project.

MP3-13-01055, MP3-14-01022 30.1 09/28/17 MP3-UCR-2017-009 9.3.5.2, Table 11.4-1 Modify U3 FSAR to correct item related to previous Thermal Regeneration FSAR Change FSAR 01-MP3-042 30.1 09/28/17 MP3-UCR-2017-012 10.4.7.3, 10.4.8.5, 9.2.1.5 Fix inconsistencies in Sections 9.2.6.5 and 10.4.7 LA3019645 Recovery Plan Action Item 5.a.23 Reconc FSAR Comments Revision 3006/29/17 Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

30 06/29/17 Administrative As identified in the 2017 NRC Major Revision issued for the purpose of 2017 NRC Submittal List of Changed Submittal. Updated footer on all pages to reflect Revis Pages and submitted Summary 30.

of Change.

29.3 03/30/17 MP3-UCR-2016-018 2.4.7, 2.4.11.6, 10.4.5.2 Reference to and discussion regarding the recirculatio tempering line is removed from these sections. MP3-01042

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

29.3 03/30/17 MP3-UCR-2015-018 Table 9.2-5 Reflects replacement of CCP HX E1B. MP3-14-0118 29.2 12/22/16 MP3-UCR-2016-021 8.1.3 Eversource 348 line teleprotection.

29.2 12/22/16 MP3-UCR-2016-020 19.2.1.20 MP3 HVK Chiller Service Water Thermal Performan Testing Elimination 29.2 12/22/16 MP3-UCR-2016-013 FPER, Section 5.5 Analysis 56 Loading, closure and transfer activities for the transfe spent fuel from the Unit 3 SFP to the site ISFSI utiliz the NUHOMS Dry Shielded Canister (DSC) and Transfer Cask (TC).

29.2 12/22/16 MP3-UCR-2016-005 9.1.2, Figure 15.0-31 FSAR Section 9.1.4.2.6 is added to the FSAR to descr the dry storage option of Unit 3 spent fuel at the ISFS 29.2 12/22/16 MP3-UCR-2015-009 2.1.2.5 Updating the SAR to extend the Heavy Haul Road to Unit 3 Fuel Building 29.2 12/22/16 MP3-UCR-2013-016 Table 6.2-63, Table 9.4-3, Implementation of an open phase protection system Table 9.4-8 which protects important to safety equipment from th potentially detrimental effects of an open phase event 29.1 09/29/16 MP3-UCR-2016-014 Chapter 8 List of Figures; Unit 3 SLOD Removal (LBDCR 15-MP3-006)

Sections 8.1.3; 8.2.1; 8.2.2; Figure 8.2-1; Figure 8.2-2 29.1 09/29/16 MP3-UCR-2016-012 Section 5.3.1.6 Update Capsule withdrawal schedule on page 5.3-6.

(TRM Change 16-MP3-007) 29.1 09/29/16 MP3-UCR-2016-010 Section 10.4.8.1, Table 10.1-1 Change to the Steam Generator blowdown system ven volumetric flow to differential pressure relationship (

MP3-10-01139)

Document Elements Summary Description of Changes Revision Revision Change Activity Affected Made under the provisions of 10 CFR 50.59 excep Release Date (Sections, Tables, Figures) where indicated in brackets.

29.1 09/29/16 MP3-UCR-2016-009 Section 5.3.1.6 Remove capsule withdrawal schedule from page 5.3-and incorporate edits to final paragraph of section 5.3.

(NRC Safety Evaluation by letter dated March 17, 20 serial # 16-131) 29.1 09/29/16 MP3-UCR-2016-007 Section 9.2.8 Change section 9.2.8 to correct the amount of flow ab to be supplied to the boric acid blender by the Primar Grade Water pumps. (CR 1028775/CA 3025491) 29.1 09/29/16 MP3-UCR-2016-003 Sections 4.2.2, 4.2.2.2.2, M3C18 reload project (EVAL-ENG-RSE-M3C18, Re 4.2.2.3.3, 4.4.2.2.7, 15.0.3.2, 0) 15.4.2.2, 15.6.1.2 29.1 09/29/16 MP3-UCR-2016-001 Section 9.5.4.4 Change to the fuel oil sampling wording to remove ambiguity. (CA3018205) 29.1 09/29/16 MP3-UCR-2015-033 Section 8.3.1.1.6 SBO Diesel Autostart (DC: MP3-15-01099) 29.1 09/29/16 MP3-UCR-2015-030 Sections 7.3.1.1.5, 10.4.9.5 TDAFW control transfer switch position (DC: MP3-1 01124) 29.1 09/29/16 MP3-UCR-2015-023 Section 9.1.2 Type Update UCR associated with LAR (LBDCR 1 MP3-009). (Lic Ltr 15-410, CR580759) 29.1 09/29/16 MP3-UCR-2015-008 Section 5.2.5.1.3, 5.4.1.2.2, Reflects replacement of RCP B & C seals (3R17) 5.4.1.3.1, 5.4.1.3.4, 5.4.1.3.7, (DC: MP3-14-01022) 5.4.1.3.10, 5.4.1.3.11, 5.4.

7.2.1, Table 5.4-1, Figure 5.4-1, Sections 9.2.2.1.3, 9.2.8.2, 9.3.4.2.1, 9.3.4.2.5, Table 9.3-6 29.1 09/29/16 MP3-UCR-2014-014 Table 10.4-4 Reflects updated discussion on TDAFW pump oversp values. (DC: MP3-14-01107)

APTER 1: INTRODUCTION AND GENERAL DESCRIPTION OF PLANT Table of Contents List of Tables List of Figures Introduction....................................................................................................... 1.1-1 General Plant Description................................................................................. 1.2-1 Comparison Tables ........................................................................................... 1.3-1 Identification of Agents and Contractors.......................................................... 1.4-1 Requirements for Further Technical Information............................................. 1.5-1 General References (Historical)........................................................................ 1.6-1 Drawings and Other Detailed Information ....................................................... 1.7-1 Conformance to NRC Regulatory Guides ........................................................ 1.8-1 N NSSS Conformance to NRC Regulatory Guides........................................... 1.8N-1 Standard Review Plan Documentation of Differences ..................................... 1.9-1 TMI Action Items ........................................................................................... 1.10-1 Material Incorporated by Reference ............................................................... 1.11-1 APTER 2: SITE CHARACTERISTICS Table of Contents List of Tables List of Figures Geography and Demography ............................................................................ 2.1-1 Nearby Industrial, Transportation, and Military Facilities .............................. 2.2-1 Meteorology...................................................................................................... 2.3-1 Hydrologic Engineering................................................................................... 2.4-1 Geology, Seismology, and Geotechnical Engineering ..................................... 2.5-1

ion Title Page 1 Basic Geological and Seismic Information ................................................... 2.5.1-1 2 Vibratory Ground Motion.............................................................................. 2.5.2-1 3 Surface Faulting............................................................................................. 2.5.3-1 4 Stability of Subsurface Materials and Foundations ....................................... 2.5.4-1 5 Stability of Slopes.......................................................................................... 2.5.5-1 6 Embankments and Dams ............................................................................... 2.5.6-1 endix 2.5A-Age of Till at Millstone Point ............................................................... 2.5A-1 endix 2.5B-Petrographic Reports, Final Grade .........................................................2.5B-1 endix 2.5C-Mineralogical Analysis of Millstone Fault Gouge Samples ..................2.5C-1 endix 2.5D-Potassium - Argon Age Determination ................................................. 2.5D-1 endix 2.5E-Separation of < 2Fraction and Clay Analysis of Samples B, C, D (ESF Building) and P-1 and P-2 (Pumphouse) ...................................................2.5E-1 endix 2.5F-Dynamic Soil Testing on Beach Sands................................................... 2.5F-1 endix 2.5G-Consolidated Undrained Tests on Beach Sands.................................... 2.5G-1 endix 2.5H-Seismic Velocity Measurements ........................................................... 2.5H-1 endix 2.5I-Direct Shear Tests on Natural Rock Joints ............................................... 2.5I-1 endix 2.5J-Boring Logs ..............................................................................................2.5J-1 endix 2.5K-Seismic Survey...................................................................................... 2.5K-1 endix 2.5L-Seismic and Bathymetric Survey............................................................2.5L-1 endix 2.5M-Laboratory Test Program for Proposed Additional Structural Backfill Sources 2.5M-1 APTER 3: DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS Table of Contents List of Tables List of Figures

ion Title Page Conformance With NRC General Design Criteria ........................................... 3.1-1 Classification of Structures, Systems, and Components................................... 3.2-1 Wind and Tornado Loadings ............................................................................ 3.3-1 Water Level (Flood) Design ............................................................................. 3.4-1 Missile Protection ............................................................................................. 3.5-1 Protection Against Dynamic Effects Associated With the Postulated Ruptures of Piping ................................................................................................................ 3.6-1 Seismic Design ................................................................................................. 3.7-1 N Seismic Design .......................................................................................... 3.7N-110 Design of Category I Structures........................................................................ 3.8-1 Mechanical Systems and Components ............................................................. 3.9-1 N Mechanical Systems and Components ........................................................ 3.9N-27 Seismic Qualification of Seismic Category I Instrumentation and Electrical Equipment ....................................................................................................... 3.10-1 N Seismic Qualification of Seismic Category I Instrumentation and Electrical Equipment .................................................................................................... 3.10N-5 Environmental Design of Mechanical and Electrical Equipment................... 3.11-1 N Environmental Design of Mechanical and Electrical Equipment.............. 3.11N-11 Appendix 3A -Computer Programs for Dynamic and Static Analysis of Seismic Category I Structures, Equipment, and Components ......................... 3A-0 Appendix 3B -Environmental Design Conditions .............................................3B-0 APTER 4: REACTOR Table of Contents List of Tables List of Figures Summary Description ....................................................................................... 4.1-1

ion Title Page Fuel System Design .......................................................................................... 4.2-1 Nuclear Design ................................................................................................. 4.3-1 Thermal and Hydraulic Design......................................................................... 4.4-1 Reactor Materials .............................................................................................. 4.5-1 Functional Design of Reactivity Control Systems............................................ 4.6-1 APTER 5: REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Table of Contents List of Tables List of Figures Summary Description ....................................................................................... 5.1-1 Integrity of Reactor Coolant Pressure Boundary .............................................. 5.2-1 Reactor Vessel .................................................................................................. 5.3-1 Component and Subsystem Design .................................................................. 5.4-1 APTER 6: ENGINEERED SAFETY FEATURES Table of Contents List of Tables List of Figures Introduction....................................................................................................... 6.0-1 Engineered Safety Feature Materials ................................................................ 6.1-1 Containment Systems ....................................................................................... 6.2-1 Emergency Core Cooling System..................................................................... 6.3-1 Habitability Systems ......................................................................................... 6.4-1 Fission Product Removal and Control Systems................................................ 6.5-1 Inservice Inspection of Class 2 and 3 Components .......................................... 6.6-1

ion Title Page APTER 7: INSTRUMENTS AND CONTROLS Table of Contents List of Tables List of Figures Introduction....................................................................................................... 7.1-1 Reactor Trip System ......................................................................................... 7.2-1 Engineered Safety Features System.................................................................. 7.3-1 Systems Required For Safe Shutdown.............................................................. 7.4-1 Safety Related Display Instrumentation ........................................................... 7.5-1 Appendix 7.5AMillstone Unit 3 Deviations to Regulatory Guide 1.97 Revision 2 ..

7-i Deviation Number 1....................................................................................... 7.5A-1 Deviation Number 2....................................................................................... 7.5A-2 Deviation Number 3....................................................................................... 7.5A-3 Deviation Number 4....................................................................................... 7.5A-4 Deviation Number 5....................................................................................... 7.5A-5 Deviation Number 6....................................................................................... 7.5A-6 Deviation Number 7....................................................................................... 7.5A-7 Deviation Number 8....................................................................................... 7.5A-8 Deviation Number 9....................................................................................... 7.5A-9 Deviation Number 10................................................................................... 7.5A-10 Deviation Number 11................................................................................... 7.5A-11 Deviation Number 12................................................................................... 7.5A-12 Deviation Number 13................................................................................... 7.5A-13

ion Title Page Deviation Number 14................................................................................... 7.5A-14 Deviation Number 15................................................................................... 7.5A-15 Deviation Number 16................................................................................... 7.5A-16 Deviation Number 17................................................................................... 7.5A-17 Deviation Number 18................................................................................... 7.5A-18 Deviation Number 19................................................................................... 7.5A-19 Deviation Number 20................................................................................... 7.5A-20 Deviation Number 21................................................................................... 7.5A-21 Deviation Number 22................................................................................... 7.5A-22 Deviation Number 23................................................................................... 7.5A-23 Deviation Number 24................................................................................... 7.5A-24 Deviation Number 25................................................................................... 7.5A-25 Deviation Number 26................................................................................... 7.5A-26 Deviation Number 27................................................................................... 7.5A-27 Deviation Number 28................................................................................... 7.5A-28 Deviation Number 29................................................................................... 7.5A-29 Deviation Number 30................................................................................... 7.5A-30 Deviation Number 31................................................................................... 7.5A-31 Deviation Number 32................................................................................... 7.5A-32 Deviation Number 33................................................................................... 7.5A-34 Deviation Number 34................................................................................... 7.5A-36 All Other Systems Required For Safety ........................................................... 7.6-1 Control Systems Not Required For Safety ....................................................... 7.7-1 Anticipated Transients Without Scram Mitigation System Actuation Circuitry 7.8-1

ion Title Page APTER 8: ELECTRIC POWER Table of Contents List of Tables List of Figures Introduction....................................................................................................... 8.1-1 Off Site Power System...................................................................................... 8.2-1 On Site Power Systems..................................................................................... 8.3-1 APTER 9: AUXILIARY SYSTEMS Table of Contents List of Tables List of Figures Fuel Storage and Handling ............................................................................... 9.1-1 Water Systems .................................................................................................. 9.2-1 Process Auxiliaries ........................................................................................... 9.3-1 Air Conditioning, Heating, Cooling, and Ventilation Systems ........................ 9.4-1 Other Auxiliary Systems................................................................................... 9.5-1 APTER 10: STEAM AND POWER CONVERSION SYSTEM Table of Contents List of Tables List of Figures Summary Description ..................................................................................... 10.1-1 Turbine-Generator .......................................................................................... 10.2-1 Main Steam System ....................................................................................... 10.3-1 Other Features of Main Steam and Power Conversion System ...................... 10.4-1

ion Title Page APTER 11: RADIOACTIVE WASTE MANAGEMENT Table of Contents List of Tables List of Figures Background ..................................................................................................... 11.0-1 Source Terms .................................................................................................. 11.1-1 Liquid Waste Management Systems............................................................... 11.2-1 Gaseous Waste Management Systems............................................................ 11.3-1 Solid Waste Management ............................................................................... 11.4-1 Process, Effluent, and Airborne Radiation Monitoring Systems.................... 11.5-1 Appendix 11A .................................................................................. 11A-0 Part ISummary of Annual Radiation Doses (Historical) ......................... 11A.1-1 Part IIDose Calculation Models and Assumptions (Historical)............... 11A.2-1 Part IIICost-Benefit Analysis (Historical) ............................................... 11A.3-1 APTER 12: RADIATION PROTECTION Table of Contents List of Tables List of Figures Introduction..................................................................................................... 12.0-1 Ensuring That Occupational Radiation Exposures Are As Low As Reasonably Achievable (ALARA)..................................................................................... 12.1-1 Radiation Sources ........................................................................................... 12.2-1 Radiation Protection Design Features............................................................. 12.3-1 Dose Assessment ............................................................................................ 12.4-1

ion Title Page Health Physics Program.................................................................................. 12.5-1 APTER 13: CONDUCT OF OPERATIONS Table of Contents List of Figures Organizational Structure ................................................................................. 13.1-1 Training Programs .......................................................................................... 13.2-1 Emergency Planning ....................................................................................... 13.3-1 Review and Audit ........................................................................................... 13.4-1 Plant Procedures ............................................................................................. 13.5-1 Physical Security Plans................................................................................... 13.6-1 APTER 14: INITIAL TEST PROGRAM Table of Contents List of Tables List of Figures Specific Information to be Included in Preliminary Safety Analysis Reports 14.1-1 Specific Information to be Included in Final Safety Analysis Report ............ 14.2-1 APTER 15: ACCIDENT ANALYSES Table of Contents List of Tables List of Figures Introduction..................................................................................................... 15.0-1 Increase in Heat Removal by the Secondary System ..................................... 15.1-1 Decrease in Heat Removal by the Secondary System .................................... 15.2-1 Decrease In Reactor Coolant System Flow Rate ............................................ 15.3-1

ion Title Page Reactivity and Power Distribution Anomalies ............................................... 15.4-1 Increase in Reactor Coolant Inventory ........................................................... 15.5-1 Decrease in Reactor Coolant Inventory .......................................................... 15.6-1 Radioactive Release From a Subsystem or Component ................................. 15.7-1 Anticipated Transients Without SCRAM ....................................................... 15.8-1 Appendix 15ADose Methodology ..................................................................... 15-1 Appendix 15BDeleted by FSARCR 02-MP3-017............................................. 15-1 APTER 16: TECHNICAL SPECIFICATIONS Table of Contents Millstone Unit 3 Technical Specifications...................................................... 16.1-1 APTER 17: QUALITY ASSURANCE Table of Contents Quality Assurance Program Topical Report ................................................... 17.1-1 APTER 18: HUMAN FACTORS ENGINEERING Table of Contents Human Factors Control Room Design Review .............................................. 18.1-1 Safety Parameter Display System (SPDS)...................................................... 18.2-1 APTER 19: LICENSE RENEWAL Table of Contents List of Tables Introduction..................................................................................................... 19.0-1 Aging Management......................................................................................... 19.1-1 Programs That Manage the Effects of Aging on Structures and Components Within the Scope of License Renewal ........................................................................ 19.2-1

ion Title Page Time-Limited Aging Analysis ........................................................................ 19.3-1 TLAA Support Programs................................................................................ 19.4-1 Exemptions ..................................................................................................... 19.5-1 License Renewal Commitments ..................................................................... 19.6-1 E PROTECTION EVALUATION REPORT Table of Contents List of Tables List of Figures Section 1 Introduction Section 2 Historical Background Section 3 Administration Section 4 Plant Design Features Section 5 Fire Hazard Analysis (FHA)

Section 6 Safe Shutdown Evaluation Section 7 Support Systems Section 8 Resolution of Safe Shutdown Evaluation Problem Areas Section 9 Operator Actions Required Following a Fire Section 10 Conclusions Appendix ASummary of Compliance With Branch Technical Position APCSB 9.5-1, Appendix A (July 1, 1976)......................................................... A-1 Appendix BComparison of Millstone 3 Plant Design to Branch Technical Position CMEB 9.5-1 Guidelines (NUREG 0800, July 1981)..............B-1 Appendix CSummary of Comparison With 10 CFR 50, Appendix R.............C-1

le 1.3-1 Design Comparison le 1.3-2 Comparison of Engineered Safety Features le 1.3-3 Comparison of Containment Concepts le 1.3-4 Comparison of Containment Atmosphere Pressure Sensor Parameters le 1.3-5 Comparison of Reactor Coolant Pump Bus Protection le 1.3-6 Comparison of Engineered Safety Feature Actuation Signals le 1.3-7 Comparison of Emergency Generator And Steam Generator Auxiliary Feedwater Pump Start Signals le 1.3-8 Comparison of Process And Effluent Radiation Monitoring Systems le 1.3-9 Comparison of Area Radiation Monitoring Systems le 1.3-10 Comparison of Airborne Radiation Monitoring Systems le 1.3-11 Comparison of Electrical System Parameters le 1.3-12 Comparison of Radioactive Liquid Waste Systems le 1.3-13 Comparison of Radioactive Gaseous Waste Systems le 1.3-14 Comparison of Radioactive Solid Waste Systems le 1.3-15 Comparison of Other Reactor Plant Systems le 1.3-16 Comparison of Final And Preliminary Information le 1.6-1 Topical Reports as General References (Historical) le 1.7-1 Electrical, Instrumentation, And Control Reference Documentation le 1.7-2 Piping And Instrumentation Diagrams le 1.7-3 Omitted le 1.7-4 Special Reports And Programs le 1.8-1 NRC Regulatory Guides le 1.8N-1 NRC Regulatory Guides

mber Title le 1.9-1 Summary of Differences From SRP le 1.9-2 SRP Differences And Justifications le 1.10-1 TMI Action Items le 2.1-1 1990 Population and Population Densities Cities and Towns Within 10 Miles of Millstone le 2.1-2 Population Growth 1960-1990 le 2.1-3 Population Distribution 1985 (0-20 km) le 2.1-4 Population Distribution Within 10 Miles of Millstone - 1990 Census le 2.1-5 Population Distribution Within 10 Miles of Millstone - 2000 Projected le 2.1-6 Population Distribution Within 10 Miles of Millstone - 2010 Projected le 2.1-7 Population Distribution Within 10 Miles of Millstone - 2020 Projected le 2.1-8 Population Distribution Within 10 Miles of Millstone - 2030 Projected le 2.1-9 Population Distribution 1985 (0-80 km) le 2.1-10 Population Distribution Within 50 Miles of Millstone - 1990 Census le 2.1-11 Population Distribution Within 50 Miles of Millstone - 2000 Projected le 2.1-12 Population Distribution Within 50 Miles of Millstone - 2010 Projected le 2.1-13 Population Distribution Within 50 Miles of Millstone - 2020 Projected le 2.1-14 Population Distribution Within 50 Miles of Millstone - 2030 Projected le 2.1-15 Transient Population Within 10 Miles of Millstone - 1991-1992 School Enrollment le 2.1-16 Transient Population Within 10 Miles of Millstone (Employment) le 2.1-17 Transient Population Within 10 Miles of Millstone State Parks and Forests (With Documented Attendance) le 2.1-18 Low Population Zone Permanent Population Distributions

mber Title le 2.1-19 Low Population Zone School Enrollment and Employment le 2.1-20 Metropolitan Areas Within 50 Miles of Millstone 1990 Census Population le 2.1-21 Population Centers Within 50 Miles of Millstone le 2.1-22 Population Density* 1985 (0-20 km) le 2.1-23 Population Density 1985 (0-80 km) le 2.1-24 Population Density Within 10 Miles of Millstone 1990 (People per Square Mile) le 2.1-25 Population Density Within 10 Miles of Millstone 2030 (People per Square Mile) le 2.1-26 Population Density Within 50 Miles of Millstone 1990 (People per Square Mile) le 2.1-27 Population Density Within 50 Miles of Millstone 2030 (People per Square Mile) le 2.1-28 Cumulative Population Density 1985 le 2.1-29 Cumulative Population Density Within 50 Miles of Millstone 1990 (People per Square Mile) le 2.1-30 Cumulative population Density Within 50 Miles of Millstone 2030 (People per Square Mile) le 2.2-1 Description of Facilities le 2.2-2 List of Hazardous Materials Potentially Capable of Producing Significant Missiles le 2.2-3 Summary of Exposure Distance Calculation le 2.2-4 Aggregate Probability of Explosion or Violent Rupture Capable of Missile Generation le 2.2-5 Types of Tank Car Missiles le 2.2-6 Tank Car Fragment Range (Feet) at 10-Degree Launch Angle

mber Title le 2.2-7 Estimated Ignition Probabilities le 2.2-8 Probability of an Unconfined Vapor Cloud Explosion le 2.3-1 Monthly, Seasonal, and Annual averages and Extremes of Temperature at Bridgeport, Conn. (1901-1981) le 2.3-2 Mean Number of Days with Selected Temperature Conditions at Bridgeport, Conn. (1966-1981) le 2.3-3 Monthly, Seasonal, and Annual Averages and Extremes of Relative Humidity at Bridgeport, Conn. (1949-1981) le 2.3-4 Monthly, Seasonal, and Annual Frequency Distributions of Wind Direction at Bridgeport, Conn. (1949-1980) le 2.3-5 Occurrence of Bridgeport Wind Persistence Episodes within the same 22.5-Degree Sector (1949-1965) le 2.3-6 Monthly, Seasonal, and Annual Frequency Distributions of Wind Direction at Bridgeport, Conn. (1949-1980) le 2.3-7 Monthly, Seasonal, and Annual Wind Speed Extremes at Bridgeport, Conn.

(1961-1990) le 2.3-8 Mean Number of Days of Thunderstorm Occurrence at Bridgeport, Conn.

(1951-1981) le 2.3-9 Monthly, Seasonal, and Annual Averages and Extremes of Precipitation at Bridgeport, Conn. (1901-June 1982) le 2.3-10 Estimated Precipitation Extremes for Periods up to 24 Hours and Recurrence Intervals Up to 100 Years le 2.3-11 Monthly, Seasonal, and Annual Averages and Extremes of Snowfall at Bridgeport, Conn. (1893-June 1990) le 2.3-12 Monthly, Seasonal, and Annual Averages of Freezing Rain and Drizzle at Bridgeport, Conn. (1949-1980) le 2.3-13 Average Monthly, Seasonal, and Annual Hours and Frequencies (percent) of Various Fog Conditions (1949-1980) at Bridgeport, Connecticut

mber Title le 2.3-14 Monthly and Annual Wind Direction and Speed Distributions for Surface Winds, at Bridgeport, Conn. (1949-1980) le 2.3-15 Monthly and Annual Wind Direction and Speed Distributions for 33-Foot Winds at Millstone (1974-1981) le 2.3-16 Comparison of Wind Direction Frequency Distribution by Quadrant at Bridgeport, Conn. and Millstone le 2.3-17 Comparison of Average Wind Speed by Quadrant at Bridgeport, Conn. and Millstone le 2.3-18 Occurrence of Wind Persistence Episodes Within the Same 22.5-Degree Sector at Millstone (1974-1981) le 2.3-19 Millstone Climatological Summary (1974-2000) le 2.3-20 Comparison of Monthly and Annual Average Dry-Bulb and Dewpoint Temperature Averages at Bridgeport, Conn. and Millstone le 2.3-21 Comparison of Monthly and Annual Average Relative Humidity Averages at Bridgeport and Millstone le 2.3-22 Mean Number of Days with Heavy Fog at Bridgeport, Conn. and Block Island, Rhode Island (1951-1981) le 2.3-23 Wind Direction/Stability Class/Visibility Joint Frequency Distribution at Millstone le 2.3-24 Persistence of Poor Visibility (1 Mile) Conditions at Millstone (Hours)

(1974-1981) le 2.3-25 Bridgeport Pasquill Stability Class Distribution (1949-1980) le 2.3-26 Millstone Stability Class Distribution Using Delta-T for Stability Determination le 2.3-27 Millstone Stability Class Distribution Using Sigma Theta for Stability Determination le 2.3-28 Comparison of Pasquill Stability Class Distribution at Bridgeport, Conn.

and Millstone

mber Title le 2.3-29 Persistence of Stable Conditions (E, F, and G Stabilities) at Millstone (1974-1981) le 2.3-30 Seasonal and Annual Atmospheric Mixing Depths at Millstone le 2.3-31 On-site Meteorological Tower Measurements le 2.3-32 Millstone Meteorological Tower Instrumentation le 2.3-33 Monthly Summary of Data Recovery Rates/Meteorological System le 2.3-34 Distances from Release Points to Receptors le 2.4-1 Connecticut Public Water Supplies within 20 Miles of Millstone 3 le 2.4-2 Maximum Wave Heights Generated by Slow, Medium, and High Speed Storms (Deep-Water Fetch) le 2.4-3 Maximum Shallow Water Waves (after Refraction) Slow Speed Probable Maximum Hurricane le 2.4-4 Maximum Shallow Water Waves (after Refraction) Medium Speed Probable Maximum Hurricane le 2.4-5 Maximum Shallow Water Waves (after Refraction) High Speed Probable Maximum Hurricane le 2.4-6 Lowest Tides at New London, Connecticut 1938-1974 le 2.4-7 Circulating Water System and Service Water System Heat Loads le 2.4-8 Dilution Factors and Travel Time

  • le 2.4-9 Category I Structures - Roof Survey le 2.4-10 Input Data to Program HEC-2 Water Surface Computations le 2.4-11 Computed Water Surface Elevations at Safety-Related Structures le 2.4-12 Roof Area and Ponding Level Due to PMP (1)Category I Structures le 2.4-13 Overflow Length of the Parapet Wall on the Roof Used in PMP Analysis -

Category I Structures

mber Title le 2.5.1-1 Rock Formations of the Coastal Plain off Southern New England le 2.5.1-2 Rock Formations of Western Connecticut le 2.5.1-3 Rock Formations of Eastern Connecticut and Western Rhode Island le 2.5.1-4 Rock Formations of Central Rhode Island (and not Included in Previous Descriptions) le 2.5.1-5 Rock Formations in Northern and Eastern Rhode Island and Southern Massachusetts le 2.5.1-6 Rock Formations of Central Massachusetts le 2.5.1-7 East of Clinton-Newbury Fault System, Eastern Massachusetts, and New Hampshire le 2.5.1-8 Descriptions of Lineaments from LANDSAT Photographs (Shown on Figure 2.5.1-10) le 2.5.2-1 Modified Mercalli (MM) Intensity Scale of 1931 le 2.5.2-2 List of Operating Seismic Stations le 2.5.2-3 Chronological Catalog of Earthquake Activity within 200 Miles of the Site le 2.5.2-4 List of Earthquakes within the 50-Mile Radius le 2.5.3-1 List of Faults le 2.5.3-2 List of Samples le 2.5.3-3 List of K/Ar Age Determinations of Fault Gouge le 2.5.4-1 List of Joints - Final Grade Floors of Structures le 2.5.4-2 List of Foliations - Final Grade Floors of Structures le 2.5.4-3 List of Slickensides - Final Grade Floors of Structures le 2.5.4-4 List of Joints - Final Grade Containment and Engineered Safety Features Building Walls

mber Title le 2.5.4-5 List of Foliations - Final Grade Containment and Engineered Safety Features Building Walls le 2.5.4-6 List of Slickensides - Final Grade Containment and Engineered Safety Features Building Walls le 2.5.4-7 List of Joints - Final Grade Walls of Structures le 2.5.4-8 List of Foliations - Final Grade Walls of Structures le 2.5.4-9 List of Slickensides - Final Grade Walls of Structures le 2.5.4-10 Rock Compression Test Results le 2.5.4-11 Direct Shear Test Results From Joint and Foliating Surfaces le 2.5.4-12 Summary of Static Soil Properties for Beach Sands

  • le 2.5.4-13 Natural Water Contents of Split Spoon Samples le 2.5.4-14 Foundation Data for Major Structures le 2.5.4-15 List of Approximate Boring Locations, Ground Elevations, and Groundwater Elevations
  • le 2.5.4-16 Summary of Water Pressure Test Data le 2.5.4-17 Groundwater Observations le 2.5.4-18 Factors of Safety Against Liquefaction of Beach Sands le 2.5.4-19 In-Place Density Test Results on Category I Structural Backfill Beneath the Service Water Intake Pipe Encasement le 2.5.4-20 In-Place Density Test Results at Control and Emergency Generator Enclosure Buildings le 2.5.4-21A Emergency Generator Enclosure - Free Field Soil Properties from SHAKE Analysis le 2.5.4-22B Emergency Generator Enclosure - Soil Properties with Structure Effects from SHAKE Analysis

mber Title le 2.5.4-23 Emergency Generator Enclosure - Soil Properties with Structure Effects from SHAKE Analysis le 2.5.4-24 Bearing Capacity of Major Structures le 2.5.4-25 Results of Two-Dimensional Liquefaction Analysis of Beach Area Sands le 3.2-1 List of QA Category I and Seismic Category I Structures, Systems, and Components le 3.2-2 Safety Classes 2 and 3 Instrument Tubing Requirements le 3.2-3 Instrument Tubing Examination and Testing Program le 3.2-4 Comparison of Proposed Tubing Examination and Testing with ASME III Requirements le 3.3-1 Structural Panels Subject to Tornado Pressure Drop le 3.5-1 Safety Related Structures, Systems, and Components Outside Containment Required for Safe Reactor Shutdown*

le 3.5-2 Safety Related Structures, Systems, and Components Inside Containment Required for Safe Reactor Shutdown*

le 3.5-3 Summary of Control Rod Drive Mechanism Missile Analysis le 3.5-4 Valve-Missile Characteristics*

le 3.5-5 Piping Temperature Element Assembly - Missile Characteristics le 3.5-6 Characteristics of Other Missiles Postulated within Reactor Containment le 3.5-7 Turbine-Target Distances and Impact Areas le 3.5-8 Deleted by FSARCR 02-MP3-13 le 3.5-9 Deleted by FSARCR 02-MP3-13 le 3.5-10 Deleted by FSARCR 02-MP3-13 le 3.5-11 Deleted by FSARCR 02-MP3-13 le 3.5-12 Deleted by FSARCR 02-MP3-13

mber Title le 3.5-13 Postulated Tornado-Generated External Missiles le 3.5-14 Barrier Deflection and Ductility Ratios for Tornado-Borne Missiles Plus 360 MPH Tornado Wind le 3.5-15 Barrier Deflection and Ductility Ratio for a Beam-Column Plus 360 MPH Tornado Wind le 3.6-1 High-Energy Systems Remote from Essential Structures, Systems, and Components le 3.6-2 High-energy Systems in Proximity to Essential Structures, Systems, and Components le 3.6-3 Moderate-Energy Systems in Remote from Essential Structures, Systems, and Components le 3.6-4 Moderate-Energy Systems Proximate to Essential Structures, Systems, and Components le 3.6-5 Essential Structures, Systems, and Components Required for Safe Reactor Shutdown le 3.6-6 Postulated Breaks Main Steam System le 3.6-7 Pipe Whip Effects Main Steam System le 3.6-8 Jet Impingement Effects - Main Steam System le 3.6-9 Postulated Breaks Main Feedwater System le 3.6-10 Pipe Whip Effects - Main Feedwater System le 3.6-11 Jet Impingement Effects - Main Steam System le 3.6-12 Postulated Breaks - Reactor Coolant System - Loop Stop Valve Bypass Piping, Excess Letdown Piping, Loop Fill Piping, Loop Drain Piping. Letdown Line, and Normal Charging le 3.6-13 Pipe Whip Effects - Reactor Coolant System - Loop Stop Valve Bypass Piping, Excess Letdown Piping, Loop Fill Piping, Loop Drain Piping, Letdown and Normal Charging

mber Title le 3.6-14 JET Impingement Effects - Reactor Coolant System - Loop Stop Valve Bypass Piping, Excess Letdown Piping, Loop Drain Piping, Loop Fill Piping, Letdown Line, and Normal Charging le 3.6-15 Postulated Breaks - Reactor Coolant System - Pressurizer Cubicle Piping le 3.6-16 Pipe Whip Effects - Reactor Coolant System - Pressurizer Cubicle Piping le 3.6-17 Jet Impingement Effects - Reactor Coolant System - Pressurizer Cubicle Piping le 3.6-18 Postulated Pipe Breaks - Reactor Coolant System - Low Pressure Safety Injection, High Pressure Safety Injection, and Residual Heat Removal Piping le 3.6-19 Pipe Whip Effects - Reactor Coolant System - Low Pressure Safety Injection, High Pressure Safety Injection, and Residual Heat Removal Piping le 3.6-20 Jet Impingement Effects - Low Pressure Safety Injection, High Pressure Safety Injection, and Residual Heat Removal Piping le 3.6-21 Postulated Breaks - Chemical Volume Control System - Normal Charging le 3.6-22 Pipe Whip Effects - Chemical Volume Control System - Normal Charging le 3.6-23 Jet Impingement Effects - Chemical Volume Control System - Normal Charging le 3.6-24 Postulated Breaks - Chemical Volume Control System - Letdown Line le 3.6-25 Pipe Whip Effects - Chemical Volume Control System - Letdown Line le 3.6-26 Jet Impingement Effects - Chemical and Volume Control System - Letdown Line Piping le 3.6-27 Postulated Breaks - Seal Water Injection System le 3.6-28 Pipe Whip Effects - Chemical Volume Control System - Seal Water Injection Line le 3.6-29 Jet Impingement Effects - Chemical Volume Control System - Seal Water Injection Line

mber Title le 3.6-30 Postulated Breaks - Steam Generator Blowdown System le 3.6-31 Pipe Whip Effects - Steam Generator Blowdown System le 3.6-32 Jet Impingement Effects - Steam Generator Blowdown System le 3.6-33 Energy Absorbing Capacity of a 4 Inch Schedule 80 Pipe le 3.6-34 Postulated Breaks Auxiliary Feedwater System le 3.6-35 Pipe Whip Effects Auxiliary Feedwater System le 3.6-36 Jet Impingement Effects Auxiliary Feedwater Systems le 3.7-1 Seismic Instrumentation le 3.7B-1 Damping Factors le 3.7B-2 Methods of Seismic Analysis Used for Seismic Category I Structures le 3.7B-3 Containment and Internal Structures Significant Modal Frequencies and Participation Factors Uncracked Model le 3.7B-4 Containment and Internal Structures Significant Modal Frequencies and Participation Factors Cracked Model le 3.7B-5 Containment and Internal Structures Significant Mode Shapes (Normalized Eigenvectors) Uncracked Model le 3.7B-6 Containment and Internal Structures Significant Mode Shapes (Normalized Eigenvectors) Cracked Model le 3.7B-7 Containment and Internal Structures SRSS Accelerations and Displacements for Safe Shutdown Earthquake Uncracked Model, Response Spectrum Analysis le 3.7B-8 Containment and Internal Structures SRSS Accelerations and Displacements for Safe Shutdown Earthquake Cracked Model, Response Spectrum Analysis le 3.7B-9 Containment and Internal Structures Degrees of Freedom le 3.7B-10 Containment and Internal Structure Enveloped Accelerations and Displacements Horizontal-motion

  • mber Title le 3.7B-11 Containment and Internal Structure Enveloped Accelerations and Displacements Vertical-Motion
  • of Safe Shutdown Earthquake Responses le 3.7B-17 Main Steam Valve Building Degrees of Freedom le 3.7B-18 Emergency Generator Enclosure Accelerations and Displacements Horizontal-Motion*

le 3.7B-19 Emergency Generator Enclosure Accelerations and Displacements Vertical

- Motion le 3.7B-20 Comparison of Response Spectra and Time History Analysis Results Containment and Internal Structures (Uncracked Properties) le 3.7B-21 Comparison of Response Spectra and Time History Analysis Results Containment and Internal Structures (Cracked Properties) le 3.7B-22 Comparison of Response Spectra and Time History Analysis Results Main Steam Valve Building SSE Accelerations*

le 3.7B-23 1 G Flat Response le 3.7B-24 Modal Density, n*

le 3.7B-25 Amplified Response Dynamic Factor Study le 3.7B-26 Piping System Seismic Design and Analysis Criteria le 3.7N-1 Damping Values Used for Seismic Analysis for Westinghouse Supplied Equipment

mber Title le 3.8-1 Loading Conditions - Liner Plate and Access Openings le 3.8-2 Loading Conditions, Penetrations le 3.8-3 Loads and Loading Combinations le 3.8-4 Load Combinations for ASME III Class 2 Penetrations except Quench, Recirculation, and Safety Injection Piping le 3.8-5 Load Combinations for ASME III Class 2 Penetrations for the Quench Spray, Recirculation Spray, and Safety Injection Systems le 3.8-6 Load Combinations for ASME III Class MC Sleeved Penetrations le 3.8-7 Nomenclature for Tables 3.8-4 through 3.8-6 le 3.9B-1 List of Input Documents Describing Design Transient for Fatigue Analysis of RCP and Associated Class 1 Piping le 3.9B-2 List of MPS-3 Documents Describing Components Requiring Inelastic Analysis le 3.9B-3 Preoperational Tests (1) le 3.9B-4 Omitted le 3.9B-5 Stress Limits for ASME Section III Class 1 (NB) Seismic Category I Components (Elastic Analysis) le 3.9B-6 Comparison of Class 1 Requirements Regulatory Guide 1.48 vs. Tables 3.9B-5 and 3.9B-10 le 3.9B-7 Stress Limits for ASME Section III Class 2 and 3 Components (Elastic Analysis) le 3.9B-8 Comparison of Classes 2 and 3 Requirements Regulatory Guide 1.48 vs Table 3.9B-7 le 3.9B-9 Stress Limits for ASME Section III Class 1, 2, and 3 Component Supports*

le 3.9B-9A Load Combinations for ASME Section III Class 1, 2, and 3 Component Supports le 3.9B-10 ASME III Class 1 Stress and Fatigue Analysis Requirements per NB3650

mber Title le 3.9B-11 ASME III Class 2 and 3* Stress Analysis Requirements per NC3650 and ND3650 le 3.9B-12 Loadings Applicable to Piping Systems le 3.9B-13 Active Pumps and Valves le 3.9B-14 Omitted le 3.9B-15 Postulated Primary Loop Breaks le 3.9B-16 Steam Generator and Reactor Coolant Pump Support Snubber Embedment Loads(1) (KIPS) le 3.9B-17 Steam Generator and Reactor Coolant Pump Support Column Embedment Loads(1)(KIPS) le 3.9B-18 Factors of Safety for Primary Members of Steam Generators and Reactor Coolant Pump Supports le 3.9B-19 Minimum Design Margins for Pressurizer Support le 3.9B-20 Design Margins for the Primary Members of the Pressurizer Safety Valve Support le 3.9B-21 Design Margins for Primary Members of Reactor Pressure Vessel Support le 3.9B-22 Design Margins for Primary Loop Bumper Support Structure le 3.9N-1 Summary of Reactor Coolant System Design Transients le 3.9N-2 Loading Combinations for Reactor Coolant System Components le 3.9N-3 Allowable Stresses for Reactor Coolant System Components le 3.9N-4 Design Loading Combinations for ASME Code Class 2 and 3 Components and Supports le 3.9N-5 Stress Criteria for Safety Code Class 2 (1) and Class 3 Tanks le 3.9N-6 Stress Criteria for ASME Code Class 2 Tanks(1) le 3.9N-7 Stress Criteria for ASME Code Class 2 and Class 3 Inactive Pumps

mber Title le 3.9N-8 Stress Criteria for Safety Related ASME Code Class 2 and Class 3 Active and Inactive Valves le 3.9N-9 Stress Criteria for ASME Code Class 2 and 3 Piping le 3.9N-10 Design Criteria for Active Pumps le 3.9N-11 Active Pumps le 3.9N-12 Active Valves le 3.9N-13 Maximum Deflections Allowed for Reactor Internal Support Structures le 3.10N-1 Seismic Category I Instrumentation and Electrical Equipment in Westinghouse NSSS Scope of Supply le 3.11N-1 Safety-Related Equipment in Westinghouse NSSS Scope of Supply (Historical, not subject to future updating) le 3A.1.2-1 Thin-Wall Cylinder, Pertinent Parameters le 3A.1.2-2 Exact and Computer Stresses for Thin-wall Cylinder le 3A.1.4-1 Infinitely Long Solid Cylinder, Pertinent Parameters le 3A.1.5-1 Input Thermal Parameter Functions for TAC2D Sample Problem le 3A.1.6-1 Peak Acceleration and Displacement le 3A.1.6-2 Horizontal Amplified Response Spectra le 3A.1.10-1 Pertinent Parameters of a Cylindrical Shell le 3A.1.10-2 Summary of Results le 3A.1.11-1 Test Problem Data le 3A.1.11-2 A Comparison of Hand and Computer Program Results le 3A.2.1-1 Infinitely Long Solid Cylinder, Pertinent Parameters le 3A.2.4-1 Comparison of Results of SLOSH vs AEC Analysis*

le 3A.2.6-1 Comparison of Experimental Data with Analytical Data Using LIMITA 3

mber Title le 3A.3-1 Comparison of Support Reaction Due to Thermal, Anchor Movement, and External Force Loading le 3A.3-2 Comparison of Deflections and Rotations Due to Thermal, Anchor Movement, and External Force Loading le 3A.3-3 Comparison of Stress Due To Thermal, Anchor Movement, and External Force Loading le 3A.3-4 Comparison of Internal Forces Due To Deadweight Analysis le 3A.3-5 Comparison of Deflections and Rotation Due to Deadweight Analysis le 3A.3-6 Comparison of Stresses Due to Deadweight Analysis le 3A.3-7 Comparison of Natural Frequencies le 3A.3-8 Comparison of Natural frequencies le 3A.3-9 Comparison of Class 1 Pipe Stress Analysis le 3A.3-10 Individual Pair Usage Factor for Point No. 30 le 3A.3-11 Comparison of PITRUST With Franklin Institute Program CYLNOZ and Hand Calculation le 3A.3-12 Comparison of PITRUST With Reference 8 Results le 3A.3-13 Comparison of PILUG Computer Program Output with Hand Calculations le 3A.3-14 Summary of Comparison of SAVAL Computer Output with Hand Calculation As-Designed Condition le 3A.3-15 Summary of Comparison of SAVAL Computer Output with Hand Calculation Reinforced Condition (1 1/4 Pad) le 3A.3-16 Nodal Force Comparison le 3A.3-17 Input Data for WATHAM le 3A.3-18 Comparison of NODAL Force Calculation at Time = 2.34 Seconds le 3A.3-19 Comparison of PITRIFE Computer Program Output With STRUDL-II Output

mber Title le 3A.3-20 Comparison of PITRIFE Computer Program Output With Hand Calculations le 3A.3-21 BENDCORD Program--Verification Problem le 3A.3-22 Pipe 1, Segment 1 Force Versus Time for Run Number S2807011 le 4.1-1 Reactor Design Parameter Table le 4.1-2 Analytical Techniques In Core Design le 4.1-3 Design Loading Conditions For Reactor Core Components le 4.2-1 Fuel Assembly Component Stresses le 4.3-1 Reactor Core Description (First Cycle) le 4.3-2 Nuclear Design Parameters (First Cycle) le 4.3-3 Typical Reactivity Requirements For Rod Cluster Control Assemblies le 4.3-4 Omitted le 4.3-5 Axial Stability Index Pressurized Water Reactor Core With A 12-Foot Height le 4.3-6 Typical Neutron Flux Levels (n/cm2-sec) At Full Power le 4.3-7 Typical Comparison of Measured And Calculated Doppler Defects le 4.3-8 Omitted le 4.3-9 Omitted le 4.3-10 Typical Comparison of Measured And Calculated AG-IN-CD Rod Worth le 4.3-11 Typical Comparison of Measured And Calculated Moderator Coefficients At HZP, BOL le 4.4-1 Thermal And Hydraulic Design Parameters (1) le 4.4-2 Void Fractions At Nominal Reactor Conditions With Design Hot Channel Factors

mber Title le 4.4-3 Radiation Levels From HJTC Probe (R/Hr) le 5.1-1 System Design and Operating Parameters le 5.2-1 Applicable Code Addenda for Class 1 Reactor Coolant System Components le 5.2-2 Primary and Auxiliary Components Material Specifications le 5.2-3 Reactor Vessels Internal Material Specifications le 5.2-4 Reactor Coolant Water Chemistry Specification le 5.2-5 Safety Valve Support Bracket Loads le 5.2-6 Relief Valves Referenced to Code Case N-242 le 5.2-7 Millstone Unit No. 3 rtpts Values (F) le 5.3-1 Reactor Vessel Non-Destructive Examination le 5.3-2 Reactor Vessel Fracture Toughness Properties le 5.3-3 Reactor Vessel Beltline Region Material Chemical Composition (wt Percent) le 5.3-4 Adjusted Referenced Temperature (ART) Values (F) le 5.3-5 Reactor Vessel Design Parameters le 5.4-1 Reactor Coolant Pump Design Parameters le 5.4-2 Reactor Coolant Pump Non-Destructive Examination Program le 5.4-3 Steam Generator Design Data le 5.4-4 Steam Generator Nondestructive Examination Program le 5.4-5 Reactor Coolant Piping Design Parameters le 5.4-6 Reactor Coolant Piping Quality Assurance Program le 5.4-7 Design Bases for Residual Heat Removal System Operation le 5.4-8 Residual Heat Removal System Component Data

mber Title le 5.4-9 Residual Heat Removal System - Cold Shutdown Operations-Failure Modes and Effects Analysis le 5.4-10 Pressurizer Design Data le 5.4-11 Reactor Coolant System Design Pressure Settings le 5.4-12 Pressurizer Quality Assurance Program le 5.4-13 Pressure Relief Tank Design Data le 5.4-14 Relief Valve Discharge to the Pressurizer Relief Tank le 5.4-15 Reactor Coolant System Design Parameters le 5.4-16 Non-Destructive Examination Program Reactor Coolant System Valves le 5.4-17 Pressurizer Valves Design Parameters le 5.4-18 Equipment Supports, Loading Combinations, and Design Allowable Stresses le 5.4-19 Reactor Vessel Head Vent System Equipment Design Parameters le 6.1-1 Typical Materials Employed for Components of ESF Systems le 6.1-2 Parameters for Ultimate Sump pH Calculation (1) le 6.1-3 Painted Surface Area Inside Containment le 6.1-4 Other Organic Materials Used Inside Containment le 6.2-1 Containment Peak Pressure and Temperature Results Following a Main Steam Line Break Inside Containment le 6.2-2 Passive Heat Sinks (1) le 6.2-3 Containment Design Evaluation Parameters le 6.2-4 LOCA Peak Pressure Results le 6.2-5 LOCA Peak Pressure - DEHL Break - Initial Condition Sensitivity le 6.2-6 LOCA Sequence of Events - Containment Peak Pressure

mber Title le 6.2-6A LOCA Peak Temperature Results le 6.2-6B LOCA Sequence of Events - Containment Peak Temperature le 6.2-6C LOCA - Containment Depressurization Results - DEPS - Break le 6.2-6D LOCA Sequence of Events - Containment Depressurization le 6.2-6E LOCA-Containment Sump Water Temperature at RSS Pump Start le 6.2-6F LOCA-Accident Chronology for Pump Suction Double Ended Rupture-Limiting Case for Containment Sump Temperature le 6.2-6G Accident Chronology for Full Double-Ended Rupture Main Steam Line Break at 0% Power-Limiting Case for Containment Pressure le 6.2-6H Accident Chronology for Full Double-Ended Rupture Main Steam Line Break at 102% Power-Limiting Case for Containment Temperature le 6.2-7 System Parameters Initial Conditions for LOCA Mass and Energy Release Analysis le 6.2-7A LOCA Mass and Energy Analysis Core Decay Heat Fraction le 6.2-8 Double Ended Hot Leg Break Blowdown Mass and Energy Release le 6.2-9 Double Ended Pump Suction Break with Minimum ECCS Flows Blowdown Mass and Energy Release le 6.2-10 Double Ended Pump Suction Break with Maximum ECCS Flows Blowdown Mass and Energy Release le 6.2-11 Double Ended Cold Leg Break with Minimum ECCS Flow Blowdown Mass and Energy Releases le 6.2-12 Deleted by PACKAGE FSC MP3-UCR-2013-008 le 6.2-13 3.0 Ft2 Pump Suction Split Break with Minimum ECCS Flows Blowdown Mass and Energy Releases le 6.2-14 Double Ended Hot Leg Minimum ECCS Flows Reflood Mass and Energy Releases

mber Title le 6.2-15 Double Ended Pump Suction Break with Minimum ECCS Flows Reflood Mass and Energy Releases le 6.2-16 Double Ended Pump Suction Break with Maximum ECCS Flows Reflood Mass and Energy Releases le 6.2-17 Double Ended Cold Leg Break with Minimum ECCS Flows Reflood Mass and Energy Releases le 6.2-18 Deleted by PACKAGE FSC MP3-UCR-2013-008 le 6.2-19 3.0 Ft2 Suction Split Break with Minimum ECCS Flows Reflood Mass and Energy Releases le 6.2-20 Double Ended Hot Leg Break with Minimum ECCS Flows Reflood Principal Parameters le 6.2-21 Double Ended Pump Suction Break with Minimum ECCS Flows Reflood Principal Parameters le 6.2-21A Double Ended Pump Suction Break with Maximum ECCS Flows Reflood Principal Parameters le 6.2-21B Double Ended Cold Leg Break with Minimum ECCS Flows Reflood Principal Parameters le 6.2-21C Deleted by PACKAGE FSC MP3-UCR-2013-008 le 6.2-21D 3.0 Square Feet Pump Suction Split Break with Minimum ECCS Flows Reflood Principal Parameters le 6.2-21E Double Ended Hot Leg Break with Minimum ECCS Flows Mass Balance le 6.2-21F Double Ended Hot Leg Break with Minimum ECCS Flows Energy Balance le 6.2-21G Double Ended Pump Suction Break with Minimum ECCS Flows Mass Balance le 6.2-21H Double Ended Pump Suction Break with Minimum ECCS Flows Energy Balance le 6.2-21I Double Ended Pump Suction Break with Maximum ECCS Flows Mass Balance

mber Title le 6.2-21J Double Ended Pump Suction Break with Maximum ECCS Flows Energy Balance le 6.2-21K Double Ended Cold Leg Break with Minimum ECCS Flows Mass Balance le 6.2-21L Double Ended Cold Leg Break with Minimum ECCS Flows Energy Balance le 6.2-21M Deleted by PACKAGE FSC MP3-UCR-2013-008 le 6.2-21N Deleted by PACKAGE FSC MP3-UCR-2013-008 le 6.2-21O 3.0 ft2 Pump Suction Split Break with Minimum ECCS Flows Mass Balance le 6.2-21P 3.0 Square Feet Pump Suction Split Break with Minimum ECCS Flows Energy Balance le 6.2-22 Deleted by Change PKG FSC 07-MP3-038 le 6.2-23 Main Steam Line Break Mass and Energy Releases Inside Containment -

Initial Conditions Assumptions le 6.2-24 Deleted by Change PKG FSC 07-MP3-038 le 6.2-25 Deleted by Change PKG FSC 07-MP3-038 le 6.2-26 Steam Generator Cubicle Peak Differential Pressures Feedwater Line Break le 6.2-27 THREED Input for Analysis at Pressurizer Cubicle le 6.2-28 THREED Input for Analysis of Steam Generator Cubicle B le 6.2-29 Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-30 Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-31 Mass and Energy Release Rates for a Spray Line DER in the Pressurizer Cubicle le 6.2-32 Deleted by Change PKG FSC 07-MP3-038 le 6.2-32A Mass and Energy Release Rates for a Surge Line DER in the Pressurizer Cubicle

mber Title le 6.2-33 Pressurizer Cubicle Peak Differential Pressures le 6.2-34 Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-35 Mass and Energy Release Rates for a Double Ended Guillotine Break of the Pressurizer Surge Line (Used for a 196.6 Square Inch Hot Leg LDR in the Steam Generator Cubicle) le 6.2-36 Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-36A Mass and Energy Release Rates for a Feedwater Line SES in the Steam Generator Cubicle le 6.2-36B Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-37 Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-37A Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-37B Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-38 Steam Generator Cubicle Peak Differential Pressures, Pressurizer Surge Line LDR le 6.2-39 Steam Generator Cubicle Peak Differential Pressures, Residual Heat Removal Line LDR le 6.2-40 Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-41 Deleted by PKF FSC MP3-UCR-2009-006 le 6.2-42 Deleted by PKG FSC MP3-UCR-2009-006 le 6.2-43 Subcompartment Design and Maximum Calculated Differential Pressures le 6.2-44 Omitted le 6.2-45 Deleted by Change PKG FSC 07-MP3-038 le 6.2-46 Deleted by Change PKG FSC 07-MP3-038 le 6.2-47 Deleted by Change PKG FSC 07-MP3-038

mber Title le 6.2-48 Deleted by Change PKG FSC 07-MP3-038 le 6.2-49 Deleted by Change PKG FSC 07-MP3-038 le 6.2-50 Deleted by Change PKG FSC 07-MP3-038 le 6.2-51 Deleted by Change PKG FSC 07-MP3-038 le 6.2-52 Deleted by Change PKG FSC 07-MP3-038 le 6.2-53 Deleted by Change PKG FSC 07-MP3-038 le 6.2-54 Deleted by Change PKG FSC 07-MP3-038 le 6.2-55 Deleted by Change PKG FSC 07-MP3-038 le 6.2-56 Deleted by Change PKG FSC 07-MP3-038 le 6.2-57 Deleted by Change PKG FSC 07-MP3-038 le 6.2-58 Deleted by Change PKG FSC 07-MP3-038 le 6.2-59 Balance of Plant Parameters Used in Steam Line Break Mass and Energy Release Calculation le 6.2-60 Parameters for ECCS Containment Backpressure Analysis le 6.2-61 Containment Heat Removal Systems Component Data le 6.2-62 Containment Heat Removal Systems - Consequences of Components Malfunctions le 6.2-63 Supplementary Leak Collection and Release System Principal Component and Design Parameters le 6.2-64 Containment Enclosure Building Design Parameters le 6.2-65 Containment Penetration (12) le 6.2-66 Omitted le 6.2-67 Hydrogen Recombiner System Design Parameter le 6.2-68 Deleted by FSARCR 05-MP3-010

mber Title le 6.2-69 Deleted by FSARCR 05-MP3-010 le 6.2-70 System Alignment for Type A Tests le 6.2-71 Pipe Insulation Inside Containment (8 Inches and Larger) le 6.2-72 DECLG Mass and Energy Releases for the Limiting Transient le 6.2-73 Deleted by Change PKG FSC 07-MP3-038 le 6.2-74 Deleted by Change PKG FSC 07-MP3-038 le 6.2-75 Deleted By FSARCR 02-MP3-017 le 6.2-76 Deleted By FSARCR 02-MP3-017 le 6.2-77 Passive Heat Sink Data for Minimum Post LOCA Containment Pressure Analysis (1) le 6.2-78 Input Data for Minimum Containment Pressure Analysis le 6.3-1 Emergency Core Cooling System Component Parameters le 6.3-2 Emergency Core Cooling System Relief Valve Data le 6.3-3 Motor Operated Isolation Valves in the Emergency Core Cooling System le 6.3-4 Materials Employed for Emergency Core Cooling System Components le 6.3-5 Single Active Failure Analysis for Emergency Core Cooling System Components le 6.3-6 Emergency Core Cooling System Recirculation Piping Passive Failure Analysis

  • le 6.3-7 Switchover Procedure

Active Components

mber Title le 6.3-11 Net Positive Suction Head for Emergency Core Cooling System Pumps le 6.4-1 Control Room Component Performance Characteristics for Habitability Systems le 6.5-1 Comparison of ESF Filter Systems with Respect to Regulatory Guide 1.52, Rev. 2 Positions le 6.6-1 Inservice Inspection Program Class 2 & 3 Systems le 7.1-1 Listing of Applicable Criteria le 7.2-1 List of Reactor Trips le 7.2-2 Protection System Interlocks le 7.2-3 Reactor Trip System Instrumentation le 7.2-4 Reactor Trip Correlation le 7.3-1 Interlocks for Engineered Safety Features Actuation System le 7.3-2 Engineered Safety Features Actuation System Instrumentation le 7.3-3 Safety Injection Signal le 7.3-4 Containment Isolation Phase A le 7.3-5 Steam Line Isolation le 7.3-6 Feedwater Isolation le 7.3-7 Control Building Isolation le 7.3-8 Containment Depressurization Actuation le 7.3-9 Containment Isolation Phase B le 7.3-10 Instrumentation and Control Systems for Engineered Safety Features and Essential Auxiliary Supporting Systems le 7.4-1 Instruments and Controls Outside Control Room for Cold Shutdown le 7.5-1 Accident Monitoring Instrumentation List

mber Title le 7.7-1 Plant Control System Interlocks le 8.1-1 Class IE System Load Identification and Function le 8.1-2 Acceptance Criteria for Electric Power le 8.3-1 Omitted le 8.3-2 Cable in Trays le 8.3-3 Nonsafety-Related Equipment Connected to Safety-Related Buses le 8.3-4 125V DC Safety Related Bus Loading le 8.3-5 Omitted le 8.3-6 Electrical Equipment not Requiring Internal Cable Separation le 9.1-1 Fuel Pool Cooling and Purification System Principal Component Design Characteristics le 9.1-2 Performance Characteristics of the Fuel Pool Cooling System (One Fuel Pool Cooler Operating) le 9.2-1 Service Water System Flow Requirements le 9.2-2 Service Water System Heat Transfer Requirements le 9.2-3 Automatic Operation of Service Water System Valves le 9.2-4 Consequence of Component Failure le 9.2-5 Reactor Plant Component Cooling System Major Component Design Data le 9.2-6 Consequences of Component Failures Reactor Plant Component Cooling Water System le 9.2-7 Chilled Water System Heat Loads and Flow Rates le 9.2-8 Chilled Water System Major Component Design Data le 9.2-9 Neutron Shield Tank Cooling System Component Data Summary le 9.2-10 Charging Pumps Cooling System Component Data Summary

mber Title le 9.2-11 Consequences of Component Failures, Charging Pumps Cooling Subsystem le 9.2-12 Safety Injection Pumps Cooling System Component Data Summary le 9.2-13 Consequences of Component Failures - Safety Injection Pumps Cooling Subsystem le 9.2-14 Condensate Demineralizer Component Cooling Water System (3CCD)

Design Data le 9.2-15 Design Data for Major Components in the Water Treating Systems le 9.2-16 Primary Grade Water System Major Component Design Data le 9.2-17 Primary Grade Water Chemistry Specifications le 9.3-1 Sampling Points - Reactor Plant le 9.3-2 Sampling Points - Turbine Plant le 9.3-3 Post-Accident Sampling System Principal Components Design and Parameters le 9.3-4 Chemical and Volume Control System Design Parameters le 9.3-5 Principal Component Data Summary le 9.3-6 Failure Mode and Effects Analysis Chemical and Volume Control System Active Components - Normal Plant Operation and Safe Shutdown le 9.3-7 Boron Recovery System Principal Component Design and Performance Characteristics le 9.3-8 Assumptions Used in Activity Discharge Calculations le 9.3-9 Boron Recovery System Failure Analysis le 9.4-1 Indoor Design Temperatures for Control Building le 9.4-2 Control Building Component Performance Characteristics for Air Conditioning, Heating, Cooling, and Ventilation Systems le 9.4-3 Design Data for Major Components in Fuel Building Ventilation System

mber Title le 9.4-4 Auxiliary Building Ventilation System Principal Components and Design Parameters le 9.4-5 Turbine Building Ventilation System Principal Components and Approximate Parameters le 9.4-6 Engineered Safety Features Building Principal Components with Approximate Design Parameters le 9.4-7 Engineered Safety Features Building Ventilation System Consequences of Component Failures le 9.4-8 Containment Air Filtration Subsystem Principal Components Design and Approximate Parameters le 9.4-9 Containment Air Recirculation System Principal Components Design and Approximate Parameters le 9.4-10 Containment Air Recirculation System Operation Modes and Approximate Design Conditions of Air Recirculation Fan Coolers le 9.4-11 Containment Purge Air Subsystem Principal Components and Approximate Parameters le 9.4-12 CRDM Cooling System Principal Components and Approximate Parameters le 9.4-13 Waste Disposal Building Heating and Ventilation System le 9.5-1 Compliance with Fire Protection Technical Requirements le 9.5-2 Emergency Diesel Generator Cooling Water System Leakage Summary Per Diesel*

le 9.5-3 Design Data for Motor Components in Emergency Generator Cooling Water Systems le 9.5-4 Design Data for the Major Components of Emergency Generator - Diesel Lubricating Oil System le 9.5-5 Gaseous Hydrogen Storage Tubes le 9.5-6 Equipment Supplied by the Nitrogen System

mber Title le 9.5-7 Nitrogen System Major Component Design Data le 9.5-8 Design Data for Major Components in the Containment Vacuum System le 9.5-9 Emergency Generator Auxiliary System Component Characteristics le 9.5-10 Cooling Water System Leakages le 10.1-1 Steam and Power Conversion System Principle Design and Performance Characteristics le 10.3-1 Materials of Main Steam and Feedwater Valves and Piping le 10.3-2 Materials of Main Steam Safety Valves le 10.3-3 Materials of Main Steam Pressure Relieving Valves le 10.3-4 Materials of Main Steam/Feedwater Valves le 10.4-1 Circulating Water and Associated Systems Design and Performance Characteristics le 10.4-2 Design Data Condensate Polishing System le 10.4-3 Condensate and Feedwater System Equipment Design parameters le 10.4-4 Equipment Design Parameters le 10.4-5 Equipment Design Parameters le 10.4-6 Condenser: Physical Characteristics and Performance Requirements (1) le 10.4-7 Deleted by PKG FSC MP3-UCR-2010-012 le 11.1-1 Iodine and Noble Gas Inventory in Reactor Core - Original License Basis (1)

(Historical) le 11.1-2 Reactor Coolant Equilibrium Concentrations - Original License Basis (Historical) le 11.1-2A Design Reactor Coolant Equilibrium Concentrations at 3723 MWt

mber Title le 11.1-3 Parameters Used in the Calculation of Reactor Coolant, Secondary Side Liquid, and Secondary Side Steam Fission and Activation Product Activity -

Original License Basis le 11.1-3A Parameters Used in the Calculation of Design Reactor Fission and Activation Product Activity le 11.1-4 Tritium Production le 11.1-5 Reactor Coolant N-16 Activity (1) le 11.1-6 Secondary Side Liquid Equilibrium Concentrations Original License Basis (Historical) le 11.1-7 Secondary Side Steam Equilibrium Concentrations - Original License Basis (Historical) le 11.2-1 Liquid Waste Management System Daily Input Flows le 11.2-2 Liquid Waste Management System Design Data le 11.2-3 Tank Overflow Protection le 11.2-4 Expected Radioactive Liquid Concentrations From Each Liquid Release Stream (Ci/ml) (1) Following Treatment (Historical) le 11.2-5 Expected Annual Radioactive Liquid Releases Prior to Dilution in the Circulating Water Discharge System and Prior to Inclusion of Anticipated Operational Occurrences (1) (Historical) le 11.2-6 Expected Annual Radioactive Liquid Releases After Dilution in the Circulating Water Discharge System and Inclusion of Anticipated Operational Occurrences (1) (Historical) le 11.2-7 Design (1) Radioactive Liquid Concentrations From Each Liquid Release Stream (Ci/gm) Following Treatment (2) le 11.2-8 Design (1) Annual Radioactive Liquid Releases Prior to Addition of Anticipated Operational Occurrences and Dilution in the Circulating Water Discharge System

mber Title le 11.2-9 Design (1) Annual Radioactive Liquid Releases Following Addition of Anticipated Operational Occurrences and Dilution in the circulating Water Discharge System le 11.2-10 Fraction of MPC Released - Design Case (1) (Historical) le 11.2-11 Assumptions Used for the Radioactive Liquid Waste System Failure (Release to Atmosphere) and for the Liquid Containing Tank Failure le 11.2-12 Boron Recovery Tank Concentrations (Ci/cc) le 11.2-13 Activity Released to Atmosphere from a Radioactive Liquid Containing Tank Failure (Boron Recovery Tank) le 11.2-14 Radioactive Concentrations in Groundwater Entering Niantic Bay Following a Rupture of Boron Recovery Tank le 11.3-1 Total Expected Radioactive Gaseous Released to Atmosphere from Millstone 3 (Historical) le 11.3-2 Radioactive Gaseous Source Term Parameters (Historical) le 11.3-3 Radioactive Gaseous Waste System le 11.3-4 Codes and Standards le 11.3-5 Expected Radioactive Gaseous Releases to Atmosphere via Ventilation Vent (Historical) le 11.3-6 Expected Radioactive Gaseous Releases to Atmosphere from Millstone 3 via Millstone Stack (Historical) le 11.3-7 Expected Radioactive Gaseous Releases to Atmosphere via Turbine Building (Historical) le 11.3-8 Design Radioactive Gaseous Releases to Atmosphere via Ventilation Vent (Historical) le 11.3-9 Design Radioactive Gaseous Releases to Atmosphere from Millstone 3 via Millstone Stack (Historical) le 11.3-10 Design Radioactive Gaseous Releases to Atmosphere via Turbine Building Roof (Historical)

mber Title le 11.3-11 Design Radioactive Gaseous Releases to Atmosphere from Millstone 3 (Historical) le 11.3-12 Assumptions Used for the Process Gas Charcoal Bed Adsorber Bypass Analysis (1) le 11.3-13 Radioisotope Releases from the Process Gas Charcoal Bed Adsorber and Associated Piping le 11.4-1 Volume of Spent Resin Generated Annually le 11.4-2 Radioactive Solid Waste System Component Data le 11.4-3 Omitted le 11.4-4 Radioactive Solid Waste Annual Shipments (1)(2) le 11.5-1 Gaseous Monitors le 11.5-2 Liquid Process Monitors le 11.5-3 Radiological Samples Taken at Reactor Plant Sample Sink le 11A.1-1 Annual Doses to Maximum Individual in the Adult Group from Gaseous Effluents le 11A.1-2 Annual Doses to Maximum Individual in the Teen Group from Gaseous Effluents le 11A.1-3 Annual Doses to Maximum Individual in the Child Group from Gaseous Effluents le 11A.1-4 Annual Doses to Maximum Individual in the Infant Group from Gaseous Effluents le 11A.1-5 Annual Doses to Maximum Individual in the Adult Group from Gaseous Effluents le 11A.1-6 Annual Doses to Maximum Individual in the Teen Group from Gaseous Effluents le 11A.1-7 Annual Doses to Maximum Individual in the Child Group from Gaseous Effluents

mber Title le 11A.1-8 Annual Doses to Maximum Individual in the Infant Group from Gaseous Effluents le 11A.1-9 Omitted le 11A.1-10 Omitted le 11A.1-11 Omitted le 11A.1-12 Omitted le 11A.1-13 Annual Doses to Maximum Individual in the Adult Group from Liquid Effluents le 11A.1-14 Annual Doses to Maximum Individual in the Teen Group from Liquid Effluents le 11A.1-15 Annual Doses to Maximum Individual in the Child Group from Liquid Effluents le 11A.1-16 Comparison of Maximum Calculated Doses from Millstone 3 Nuclear Plant with Appendix I Design Objectives le 11A.1-17 Calculated Population Dose le 11A.2-1 Dilution Factors, Travel Times from the Site, and Population Served le 11A.2-2 Parameters and Assumptions Used in Equations for Estimating Doses to Humans le 11A.2-3 Meteorological Data le 11A.2-4 Parameters and Assumptions Used in Estimating Doses to Biota le 11A.3-1 Base Case Annual Population Doses Due to Liquid Effluents (1) le 11A.3-2 Base Case Annual Population Doses Due to Gaseous Effluents (1) le 12.2-1 Parameters Used in Calculation of Design Radiation Source Inventories (HISTORICAL) le 12.2-2 Radioactive Sources in Containment Building (HISTORICAL) le 12.2-3 Radioactive Sources in the Auxiliary Building (HISTORICAL)

mber Title le 12.2-4 Radioactive Sources in the Waste Disposal Building (HISTORICAL) le 12.2-5 Radioactive Sources in the Fuel Building (HISTORICAL) le 12.2-5A Other Radioactive Sources (HISTORICAL) le 12.2-6 Inventory of an Average Fuel Assembly after 650 Days of Operation at 3,636 MWt at Shutdown and 100 Hours after Shutdown (Ci)

(HISTORICAL) le 12.2-7 Source Intensity in the Most Radioactive Fuel Assembly

  • after 650 Days of Operation at 3636 Mwt (HISTORICAL) le 12.2-8 Radionuclide Concentrations in the Spent Fuel Pool from Refueling 100 Hours after Shutdown* (HISTORICAL) le 12.2-9 Radiation Sources
  • Reactor Coolant Nitrogen-16 Activity (HISTORICAL) le 12.2-10 Assumptions Used in the Calculation of Airborne Concentrations (HISTORICAL) le 12.2-11 Airborne Concentrations Inside Major Buildings (mci/cc) (HISTORICAL) le 12.3-1 Radiation Zones le 12.3-2 Radiation Monitoring System - Area Radiation Detector Location le 12.3-3 Operator Activity Locations and Time Durations le 12.3-4 Activity Initiation Time le 12.5-1 Deleted by FSARCR 04-MP3-040 le 12.5-2 Deleted by FSARCR 04-MP3-040 le 14.2-1 Preoperational/Acceptance Test Program Test Descriptions le 14.2-2 Startup Test Descriptions le 14.2-3 Preoperational/Acceptance/Startup Tests Acceptance Criteria Sources le 15.0-1 Nuclear Steam Supply System Power Ratings

mber Title le 15.0-2 Summary of Initial Conditions and Computer Codes Used le 15.0-3 Nominal Values of Pertinent Plant Parameters Utilized in the Accident Analysis le 15.0-4 Trip Point and Time Delays to Trip Assumed in Accident Analyses le 15.0-5 Deleted by PKG FSC 07-MP3-049 le 15.0-6 Plant Systems and Equipment Required for the Mitigation of Transient and Accident Conditions le 15.0-7 Fission Product Inventory in Reactor Core le 15.0-8 Potential Dose Due to Accidents le 15.0-9 Typical Power-Temperature Distribution for Full Core le 15.0-10 Technical Specification Coolant Concentrations le 15.0-11 Atmospheric Dispersion Data Used for Design Basis Accident Analysis le 15.0-12 Reactor Coolant Iodine Concentrations Assuming Pre-Accident Iodine Spike le 15.0-13 Iodine Release Rates into Reactor Coolant Due to Concurrent Iodine Spike le 15.1-1 Time Sequence of Events for Incidents Which Cause an Increase in Heat Removal by the Secondary System le 15.1-2 Equipment Required Following a Rupture of a Main Steam Line le 15.1-3 Assumptions Used in Main Steam Line Break Analysis le 15.1-4 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.2-1 Time Sequence for Events for Incidents Which Cause a Decrease in Heat Removal by the Secondary System le 15.2-2 Natural Circulation Flow le 15.3-1 Time Sequence of Events for Incidents Which Result in a Decrease in Reactor Coolant System Flow

mber Title le 15.3-1A Time Sequence of Events for Underfrequency Event le 15.3-2 Summary of Results for Locked Rotor Transients le 15.3-3 Assumptions Used in Locked Rotor Analysis le 15.4-1 Time Sequence of Events for Incidents Which Cause Reactivity and Power Distribution Anomalies le 15.4-2 Minimum Calculated DNBR for a Typical Case of Rod Cluster Control Assembly Misalignment le 15.4-3 Parameters Used in the Analysis of the Rod Cluster Control Assembly Ejection Accident le 15.4-4 Parameters Used in Rod Ejection Accident Analysis le 15.4-5 Integrated Break Flow (lbm) in Containment le 15.4-6 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.5-1 Time Sequence of Events - CVCS Malfunction that Increases Reactor Coolant Inventory le 15.6-1 Time Sequence of Events for Inadvertent Opening of a Pressurizer Safety Valve le 15.6-2 Assumptions Used in Analysis of Failure of Small Lines Carrying Primary Coolant Outside Containment le 15.6-3 Plant Operating Range Allowed by the Best Estimate Large Break LOCA Analysis le 15.6-4 Large Break LOCA Containment Data Used for Calculation of Containment Pressure le 15.6-5 Analysis of Record Best Estimate Large Break LOCA Results le 15.6-6 Total Minimum Injected Safety Injection Flow Used in Best Estimate large Break LOCA Analysis le 15.6-7 Large Break LOCA Containment Data Used for Calculation of Containment Pressure

mber Title le 15.6-8 Peak Clad Temperature including All Penalties and benefits, Best Estimate large Break LOCA (BE LBLOCA) le 15.6-9 Assumptions Used for the Radiological Consequences of a LOCA Analysis le 15.6-10 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.6-11 Deleted by Change PKG FSC 07-MP3-054 le 15.6-12 Assumptions Used for the Control Room Habitability Analysis le 15.6-13 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.6-14 Time Sequence of Events for Incidents Which Cause a Decrease in Reactor Coolant Inventory (Small Break) le 15.6-15 Input Parameters Used in the ECCS Analysis (small Break) le 15.6-16 Small Break LOCA Results Fuel Cladding Data le 15.6-17 Small Break LOCA Safety Injection Flow Rate for 1.5 inch to 6 inch Breaks le 15.6-18 Small Break LOCA Safety Injection Flow Rate for 8.75 inch Break Before Switchover le 15.6-19 Omitted le 15.6-20 Omitted le 15.6-21 DELETED BY FSARCR 03-MP3-022 le 15.6-22 DELETED BY FSARCR 03-MP3-022 le 15.6.3-1 Operator Action Times for Design Basis Steam Generator Tube Rupture Analysis le 15.6.3-2 Steam Generator Tube Rupture Analysis Sequence of Events le 15.6.3-3 Steam Generator Tube R Mass Releases Total Mass Flow (Pounds) le 15.6.3-4 Steam Generator Tube Rupture Analysis Parameters Used in Evaluating Radiological Consequences le 15.6.3-5 Deleted by Change PKG FSC 07-MP3-054

mber Title le 15.6.3-6 Steam Generator Tube Rupture Analysis Iodine Spike Appearance Rates le 15.6.3-7 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.6.3-8 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.6.3-9 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.6.3-10 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.7-1 Omitted le 15.7-2 Table Relocated to Table 11.3-13 by FSARCR 04-MP3-017 le 15.7-3 Table Relocated to Table 11.3-13 by FSARCR 04-MP3-017 le 15.7-4 Table Relocated to Table 11.2-12 by FSARCR 04-MP3-017 le 15.7-5 Table Relocated to Table 11.2-11 by FSARCR 04-MP3-017 le 15.7-6 Table Relocated to Table 11.2-13 by FSARCR 04-MP3-017 le 15.7-7 Table Relocated to Table 11.2-14 by FSARCR 04-MP3-017 le 15.7-8 Parameters for Postulated Fuel Handling Accident le 15.7-9 Deleted by FSARCR PKG FSC 04-MP3-017 le 15.7-10 Deleted by PKG FSC 07-MP3-056 le 15.7-11 Deleted by FSARCR PKG FSC 04-MP3-017 le 19.6-1 License Renewal Commitments le 4-1 Sprinkler/Waterspray Protected Areas le 4-2 CO2 Protected Areas le 9-1 Plant Functions which Could be Affected by a Fire in Different Fire Areas and Options Available to Complete Function (Deleted)

Figure Number Figure Label Title Drawing Number Sheet 1.2-1 FIGURE 1.2-1 Not Used N/A N/A 1.2-2 FIGURE 1.2-2 Plot Plan 25212-10002 a N/A 1.2-3 FIGURE 1.2-3 (Sheets 1-3) Piping & Instrumentation Diagram Legend 25212-26900 (a) 1 OF 3 1.2-3 FIGURE 1.2-3 (Sheets 1-3) Piping & Instrumentation Diagram Legend 25212-26900 (a) 2 OF 3 1.2-3 FIGURE 1.2-3 (Sheets 1-3) Piping & Instrumentation Diagram Legend 25212-26900 (a) 3 OF 3 2.1-1 FIGURE 2.1-1 General Site Location N/A N/A 2.1-2 FIGURE 2.1-2 General Vicinity N/A N/A 2.1-3 FIGURE 2.1-3 Site Layout N/A N/A 2.1-4 FIGURE 2.1-4 Site Plan N/A N/A 2.1-5 FIGURE 2.1-5 Towns Within 10 Miles N/A N/A 2.1-6 FIGURE 2.1-6 1985 Population Distribution 0-20 km N/A N/A 2.1-7 FIGURE 2.1-7 Population Sectors for 0-10 Miles N/A N/A 2.1-8 FIGURE 2.1-8 Counties within 50 Miles N/A N/A 2.1-9 FIGURE 2.1-9 1985 Population Distribution 0-80 km N/A N/A 2.1-10 FIGURE 2.1-10 Population Sectors for 0-50 miles N/A N/A 2.1-11 FIGURE 2.1-11 Roads and Facilities in the LPZ N/A N/A 2.1-12 FIGURE 2.1-12 LPZ Population Sectors Distribution N/A N/A 2.2-1 FIGURE 2.2-1 Major Industrial, Transportation and Military Facilities N/A N/A 2.2-2 FIGURE 2.2-2 Instrument Landing Patterns at Trumbull Airport N/A N/A 2.2-3 FIGURE 2.2-3 Air Lanes Adjacent to Millstone Point N/A N/A 2.2-4 FIGURE 2.2-4 New London County-State Highways and Town Roads N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 2.2-5 FIGURE 2.2-5 Propane Concentration Outside and Inside the Control N/A N/A Room 2.3-1 FIGURE 2.3-1 Topography in the Vicinity of Millstone Point N/A N/A 2.3-2 FIGURE 2.3-2 Topographical Profiles within 5 Miles of Site N/A N/A 2.3-3 FIGURE 2.3-3 Topographical Profiles within 5 Miles of Site N/A N/A 2.3-4 FIGURE 2.3-4 Topographical Profiles within 50 Miles of Site (Sheet 1) N/A 1 OF 2 2.3-4 FIGURE 2.3-4 Topographical Profiles within 50 Miles of Site (Sheet 2) N/A 2 OF 2 2.3-5 FIGURE 2.3-5 Topographical Profiles within 50 Miles of Site (Sheet 1) N/A 1 OF 2 2.3-5 FIGURE 2.3-5 Topographical Profiles within 50 Miles of Site (Sheet 2) N/A 2 OF 2 2.3-6 FIGURE 2.3-6 General Topography - 50 Miles (Sheet 1) N/A 1 OF 2 2.3-6 FIGURE 2.3-6 General Topography - 50 Miles (Sheet 2) N/A 2 OF 2 2.3-7 FIGURE 2.3-7 Meteorological Instrument and Data Quality Assurance N/A N/A Flow Diagram 2.4-1 FIGURE 2.4-1 Facilities Located on the Site N/A N/A 2.4-2 FIGURE 2.4-2 Public Water Supplies within 20 Miles of Site N/A N/A 2.4-3 FIGURE 2.4-3 Locations of Hydrographic Field Survey Stations, June N/A N/A to October 1965 2.4-4 FIGURE 2.4-4 Tidal Currents Measured by Essex Marine Laboratory N/A N/A 2.4-5 FIGURE 2.4-5 Bottom Profiles Established by Essex Marine N/A N/A Laboratory 2.4-6 FIGURE 2.4-6 Frequency of Tidal Flooding at New London, N/A N/A Connecticut 2.4-7 FIGURE 2.4-7 Site Grade and Drainage Basins for PMP Runoff N/A N/A Analysis

Figure Number Figure Label Title Drawing Number Sheet 2.4-8 FIGURE 2.4-8 Bottom Profile Along Path of Maximum Surface Winds N/A N/A 2.4-9 FIGURE 2.4-9 Coincident Wave and Surge Slow-Speed Probable N/A N/A Maximum Hurricane 2.4-10 FIGURE 2.4-10 Coincident Wave and Surge Medium-Speed Probable N/A N/A Maximum Hurricane 2.4-11 FIGURE 2.4-11 Coincident Wave and Surge High-Speed Probable N/A N/A Maximum Hurricane 2.4-12 FIGURE 2.4-12 Locus of Hurricane Eye, Hurricane Type: Large Radius, N/A N/A Slow Speed of Translation 2.4-13 FIGURE 2.4-13 Locus of Hurricane Eye, Hurricane Type: Large Radius, N/A N/A Medium Speed of Translation 2.4-14 FIGURE 2.4-14 Locus of Hurricane Eye, Hurricane Type: Large Radius, N/A N/A High Speed of Translation 2.4-15 FIGURE 2.4-15 Wave Transects on Long Island Sound N/A N/A 2.4-16 FIGURE 2.4-16 Areas Under Effect of Wave Shoaling and Wave N/A N/A Refraction 2.4-17 FIGURE 2.4-17 Wave Refraction Diagram, Block Island Sound Grid N/A N/A 2.4-18 FIGURE 2.4-18 Wave Refraction Diagram, Millstone Grid, Angle of N/A N/A Approach South 30 Degrees East 2.4-19 FIGURE 2.4-19 Wave Refraction Diagram, Millstone Grid, Angle of N/A N/A Approach West 85 Degrees South 2.4-20 FIGURE 2.4-20 Wave Refraction Diagram, Millstone Grid, Angle of N/A N/A Approach West 45 Degrees South 2.4-21 FIGURE 2.4-21 Wave Refraction Diagram, Millstone Grid, Angle of N/A N/A Approach West 17 Degrees South

Figure Number Figure Label Title Drawing Number Sheet 2.4-22 FIGURE 2.4-22 Topography and Runup Transects, Millstone Location N/A N/A 2.4-23 FIGURE 2.4-23 Intake Transect A N/A N/A 2.4-24 FIGURE 2.4-24 Runup Transect B (West) N/A N/A 2.4-25 FIGURE 2.4-25 Runup Transect C (East) N/A N/A 2.4-26 FIGURE 2.4-26 Wave Clapotis at Intake N/A N/A 2.4-27 FIGURE 2.4-27 Inputs to One Dimensional Setdown Model N/A N/A 2.4-28 FIGURE 2.4-28 Large Radius, Probable Maximum Hurricane Isovel N/A N/A Field 2.4-29 FIGURE 2.4-29 Large Radius, Slow Speed of Translation Time Variant N/A N/A Wind Field - Millstone 2.4-30 FIGURE 2.4-30 Setdown Versus Wind Speed N/A N/A 2.4-31 FIGURE 2.4-31 Boundary of the Modeled Area N/A N/A 2.4-32 FIGURE 2.4-32 Onsite Well Locations N/A N/A 2.4-33 FIGURE 2.4-33 Probable Seepage Path From Boron Recovery Tank and N/A N/A Waste Disposal Building to Long Island Sound 2.4-34 FIGURE 2.4-34 Scupper Details - Control, Hydrogen Recombiner, and N/A N/A Containment Enclosure Buildings 2.4-35 FIGURE 2.4-35 Roof Plug Sealing Detail - Hydrogen Recombiner N/A N/A Building 2.4-36 FIGURE 2.4-36 Hatch Cover Details - Circulating Water Pumphouse N/A N/A Service Water Pump Cubicle 2.4-37 FIGURE 2.4-37 Hatch Cover Details - Control Building Mechanical N/A N/A Room 2.5.1-1 FIGURE 2.5.1-1 Regional Physiographic Map N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 2.5.1-2 FIGURE 2.5.1-2 Regional Pre-Pleistocene Sediments of the Continental N/A N/A Margin 2.5.1-3 FIGURE 2.5.1-3 Site Surficial Geology N/A N/A 2.5.1-4 FIGURE 2.5.1-4 Regional Geologic Map N/A N/A 2.5.1-5 FIGURE 2.5.1-5 Regional Geologic Section N/A N/A 2.5.1-6 FIGURE 2.5.1-6 Regional Tectonic Map N/A N/A 2.5.1-7 FIGURE 2.5.1-7 Stratigraphic Correlation Chart for the Site and N/A N/A Surrounding Region) 2.5.1-8 FIGURE 2.5.1-8 Regional Stratigraphic Correlation Chart (Sheet 1) N/A 1 OF 3 2.5.1-8 FIGURE 2.5.1-8 Regional Stratigraphic Correlation Chart (Sheet 2) N/A 2 OF 3 2.5.1-8 FIGURE 2.5.1-8 Regional Stratigraphic Correlation Chart (Sheet 3) N/A 3 OF 3 2.5.1-9 FIGURE 2.5.1-9 LANDSAT Photographs of Connecticut, Rhode Island, N/A N/A Southern Massachusetts, and Eastern New York 2.5.1-10 FIGURE 2.5.1-10 Lineament Map from LANDSAT Photographs N/A N/A 2.5.1-11 FIGURE 2.5.1-11 Regional Aeromagnetic Map N/A N/A 2.5.1-12 FIGURE 2.5.1-12 Regional Bouguer Gravity Map N/A N/A 2.5.1-13 FIGURE 2.5.1-13 Site Bedrock Geology N/A N/A 2.5.1-14 FIGURE 2.5.1-14 Tectonic Map of Eastern Connecticut N/A N/A 2.5.1-15 FIGURE 2.5.1-15 Contour Diagram of Poles to Foliation Planes - Final N/A N/A Grade 2.5.1-16 FIGURE 2.5.1-16 Contour Diagram of Poles to Joint Planes - Final Grade N/A N/A 2.5.1-17 FIGURE 2.5.1-17 Contour Plot of Bearing and Plunge of Slickensides -

N/A N/A Final Grade

Figure Number Figure Label Title Drawing Number Sheet 2.5.1-18 FIGURE 2.5.1-18 Generalized Location of Faults N/A N/A 2.5.2-1 FIGURE 2.5.2-1 Location of Seismic Stations N/A N/A 2.5.2-2 FIGURE 2.5.2-2 Epicenters of Earthquakes within 200-Mile Radius N/A N/A 2.5.2-3 FIGURE 2.5.2-3 Location of Earthquakes within the 50-Mile Radius N/A N/A 2.5.2-4 FIGURE 2.5.2-4 Isoseismal Map, Earthquake of November 9, 1727 N/A N/A 2.5.2-5 FIGURE 2.5.2-5 Isoseismal Map, Earthquake of November 18, 1755 N/A N/A 2.5.2-6 FIGURE 2.5.2-6 Isoseismal Map, Earthquake of May 16, 1791 N/A N/A 2.5.2-7 FIGURE 2.5.2-7 Isoseismal Map, Earthquake of August 10, 1884 N/A N/A 2.5.2-8 FIGURE 2.5.2-8 Isoseismal Map, Earthquake of March 1, 1925 (February N/A N/A 28, 1925 EST) 2.5.2-9 FIGURE 2.5.2-9 Isoseismal Map, Earthquakes of December 20 and 24, N/A N/A 1940 2.5.2-10 FIGURE 2.5.2-10 Tectonic Provinces N/A N/A 2.5.3-1 FIGURE 2.5.3-1 T-2 Fault Zone, Final Excavation Grade - Northern N/A N/A Section 2.5.3-2 FIGURE 2.5.3-2 T-2 Fault Zone, Final Excavation Grade - Southern N/A N/A Section 2.5.3-3 FIGURE 2.5.3-3 T-3 Fault Zone, Final Excavation Grade N/A N/A 2.5.4-1 FIGURE 2.5.4-1 Geologic Map of Final Grade, Service Water Line Walls N/A N/A

- East 2.5.4-2 FIGURE 2.5.4-2 Geologic Map of Final Grade, Service Water Line Walls N/A N/A

- West 2.5.4-3 FIGURE 2.5.4-3 Geologic Map of Final Grade, South Wall of Discharge N/A N/A Tunnel

Figure Number Figure Label Title Drawing Number Sheet 2.5.4-4 FIGURE 2.5.4-4 Geologic Map of Final Grade, North Wall of Discharge N/A N/A Tunnel 2.5.4-5 FIGURE 2.5.4-5 Geologic Map of Final Grade, East Wall of Discharge N/A N/A Tunnel 2.5.4-6 FIGURE 2.5.4-6 Geologic Map of Final Grade, Floors of Structures N/A N/A 2.5.4-7 FIGURE 2.5.4-7 Geologic Map of Final Grade, Service Water Line Floor N/A N/A

- West 2.5.4-8 FIGURE 2.5.4-8 Geologic Map of Final Grade, Pumphouse Floor N/A N/A 2.5.4-9 FIGURE 2.5.4-9 Geologic Map of Final Grade, Service Water Line Floor N/A N/A

- East 2.5.4-10 FIGURE 2.5.4-10 Geologic Map of Final Grade, Southeast Quadrant of N/A N/A Containment Walls 2.5.4-11 FIGURE 2.5.4-11 Geologic Map of Final Grade, Southwest Quadrant of N/A N/A Containment Walls 2.5.4-12 FIGURE 2.5.4-12 Geologic Map of Final Grade, Northwest Quadrant of N/A N/A Containment Walls 2.5.4-13 FIGURE 2.5.4-13 Geologic Map of Final Grade, Northeast Quadrant of N/A N/A Containment Walls 2.5.4-14 FIGURE 2.5.4-14 Geologic Map of Final Grade, Engineered Safety N/A N/A Features, Building Sump Walls 2.5.4-15 FIGURE 2.5.4-15 Geologic Map of Final Grade, Auxiliary Building Pipe N/A N/A Tunnel Pit Walls 2.5.4-16 FIGURE 2.5.4-16 Geologic Map of Final Grade, North Wall of Excavation N/A N/A 2.5.4-17 FIGURE 2.5.4-17 Geologic Map of Final Grade, Northeast and Southeast N/A N/A Pumphouse Walls

Figure Number Figure Label Title Drawing Number Sheet 2.5.4-18 FIGURE 2.5.4-18 Geologic Map of Final Grade Engineered Safety N/A N/A Features Building Wall 2.5.4-19 FIGURE 2.5.4-19 Geologic Map of Final Grade Discharge Tunnel Floor N/A N/A 2.5.4-20 FIGURE 2.5.4-20 Geological Map of Final Grade Discharge Tunnel Floor N/A N/A 2.5.4-21 FIGURE 2.5.4-21 Geological Map of Final Grade North Wall of Discharge N/A N/A Tunnel 2.5.4-22 FIGURE 2.5.4-22 Geological Map of Final Grade South Wall of Discharge N/A N/A Tunnel 2.5.4-23 FIGURE 2.5.4-23 Geologic Map of Final Grade Discharge Tunnel Floor N/A N/A 2.5.4-24 FIGURE 2.5.4-24 Geologic Map of Final Grade Discharge Tunnel Floor N/A N/A 2.5.4-25 FIGURE 2.5.4-25 Geologic Map of Final Grade West Wall of Discharge N/A N/A Tunnel 2.5.4-26 FIGURE 2.5.4-26 Geologic Map of Final Grade East Wall of Discharge N/A N/A Tunnel 2.5.4-27 FIGURE 2.5.4-27 Geologic Map of Final Grade Discharge Weir Rock Face N/A N/A 2.5.4-28 FIGURE 2.5.4-28 Corrected Blow Count Plot, Pumphouse Area Sands, N/A N/A Onshore Boring Composite 2.5.4-29 FIGURE 2.5.4-29 Corrected Blow Count Plot, Pumphouse Area Sands, N/A N/A Borings P1 to P8 Composite 2.5.4-30 FIGURE 2.5.4-30 Grain Size Distribution Curves (Sheet 1) 1 OF 4 1 OF 4 2.5.4-30 FIGURE 2.5.4-30 Grain Size Distribution Curves (Sheet 2) 2 OF 4 2 OF 4 2.5.4-30 FIGURE 2.5.4-30 Grain Size Distribution Curves (Sheet 3) 3 OF 4 3 OF 4 2.5.4-30 FIGURE 2.5.4-30 Grain Size Distribution Curves (Sheet 4) N/A N/A 2.5.4-31 FIGURE 2.5.4-31 Boring Location Plan N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 2.5.4-32 FIGURE 2.5.4-32 Plot Plan Showing Locations of the Borings and the N/A N/A Geologic Sections 2.5.4-33 FIGURE 2.5.4-33 Geologic Profile, Sections A-A', B-B' N/A N/A 2.5.4-34 FIGURE 2.5.4-34 Geologic Profile, Sections C-C', D-D', E-E' N/A N/A 2.5.4-35 FIGURE 2.5.4-35 Geologic Profile, Sections F-F" and G-G' N/A N/A 2.5.4-36 FIGURE 2.5.4-36 Top of Basal Till Contour Map N/A N/A 2.5.4-37 FIGURE 2.5.4-37 Groundwater Contour Map N/A N/A 2.5.4-38 FIGURE 2.5.4-38 Groundwater Observations in Boreholes N/A N/A 2.5.4-39 FIGURE 2.5.4-39 Bedrock Surface Contour Map N/A N/A 2.5.4-40 FIGURE 2.5.4-40 General Excavation Plan N/A N/A 2.5.4-41 FIGURE 2.5.4-41 Shorefront and Dredging Plan N/A N/A 2.5.4-42 FIGURE 2.5.4-42 Modulus vs Effective Confining Pressure, Structural Fill N/A N/A 2.5.4-43 FIGURE 2.5.4-43 Lateral Pressure Distribution N/A N/A 2.5.4-44 FIGURE 2.5.4-44 Gradation Curves for Category I Structural Fill N/A N/A 2.5.4-45 FIGURE 2.5.4-45 K2 vs Shear Strain for Beach Sands N/A N/A 2.5.4-46 FIGURE 2.5.4-46 Earthquake Induced Shear Stresses in Beach Sands N/A N/A 2.5.4-47 FIGURE 2.5.4-47 Cyclic Stress Ratio vs Confining Pressure for Beach N/A N/A Sands 2.5.4-48 FIGURE 2.5.4-48 Cyclic Stress Ratio vs Penetration Resistance of Sand N/A N/A 2.5.4-49 FIGURE 2.5.4-49 Factor of Safety Against Liquefaction of Beach Sands N/A N/A 2.5.4-50 FIGURE 2.5.4-50 Idealized Soil Profile Liquefaction Analysis of Ablation N/A N/A Till Under Discharge Tunnel 2.5.4-51 FIGURE 2.5.4-51 Geologic Profile, Section H-H N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 2.5.4-52 FIGURE 2.5.4-52 Geologic Profile, Section I-I N/A N/A 2.5.4-53 FIGURE 2.5.4-53 Location of Field Density Tests - Service Water Intake N/A N/A Line 2.5.4-54 FIGURE 2.5.4-54 Location of Field Density Test - Emergency Generator N/A N/A Enclosure and Control Building 2.5.4-55 FIGURE 2.5.4-55 Geologic Profile, Section J-J' N/A N/A 2.5.4-56 FIGURE 2.5.4-56 Geologic Profile, Section K-K' N/A N/A 2.5.4-57 FIGURE 2.5.4-57 Grain Size Distribution Curves - Pumphouse Area N/A 1 OF 2 Outwash Sands (Sheet 1) 2.5.4-57 FIGURE 2.5.4-57 Grain Size Distribution Curves - Pumphouse Area N/A 2 OF 2 Outwash Sands (Sheet 2) 2.5.4-58 FIGURE 2.5.4-58 Equivalent Numbers of Uniform Stress Cycles Based on N/A N/A Strongest Components of Ground Motion 2.5.4-59 FIGURE 2.5.4-59 Plan of Settlement Monitoring Benchmark Locations N/A N/A 2.5.4-60 FIGURE 2.5.4-60 Control Building Settlement (Sheet 1) N/A 1 OF 2 2.5.4-60 FIGURE 2.5.4-60 Control Building Settlement (Sheet 2) N/A 2 OF 2 2.5.4-61 FIGURE 2.5.4-61 Emergency Generator Enclosure Settlement N/A N/A 2.5.4-62 FIGURE 2.5.4-62 .Solid Waste Building Settlement N/A N/A 2.5.4-63 FIGURE 2.5.4-63 Liquid Waste Building Settlement N/A N/A 2.5.4-64 FIGURE 2.5.4-64 Fuel Building Settlement N/A N/A 2.5.4-65 FIGURE 2.5.4-65 Geologic Profile Section L-L' N/A N/A 2.5.4-66 FIGURE 2.5.4-66 Geologic Profile Section M-M' N/A N/A 2.5.4-67 FIGURE 2.5.4-67 Geologic Profile Section N-N' N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 2.5.4-68 FIGURE 2.5.4-68 Geologic Profile Section O-O' N/A N/A 2.5.4-69 FIGURE 2.5.4-69 Geologic Profile Section P-P' N/A N/A 2.5.4-70 FIGURE 2.5.4-70 Geologic Profile Section Q-Q' N/A N/A 2.5.4-71 FIGURE 2.5.4-71 Geologic Profile Section R-R' N/A N/A 2.5.4-72 FIGURE 2.5.4-72 Soil-Structure Interaction Emergency Generator N/A N/A Enclosure 2.5.4-73 FIGURE 2.5.4-73 Shear Modulus Curve Type 2 Soil (Structural Backfill N/A N/A and Basal Till) 2.5.4-74 FIGURE 2.5.4-74 Damping Curve Type 2 Soil (Structural Backfill and N/A N/A Basal Till) 2.5.4-75 FIGURE 2.5.4-75 Shorefront Profile Used in Liquefaction Analyses N/A N/A 2.5.5-1 FIGURE 2.5.5-1 Section through Shorefront N/A N/A 2.5.5-2 FIGURE 2.5.5-2 Typical Wedge Geometry N/A N/A 2.5.5-3 FIGURE 2.5.5-3 Design Loads for Ring Beam N/A N/A 2.5.5-4 FIGURE 2.5.5-4 Shorefront Slope Stability Section - Sloping Rock N/A N/A Profile 2.5.5-5 FIGURE 2.5.5-5 Summary of CIU Test Results - Beach Area Outwash N/A N/A Sands 2.5.5-6 FIGURE 2.5.5-6 Potential Failure Wedges West Side of Containment N/A N/A Excavation 2.5.5-7 FIGURE 2.5.5-7 Rock Surface Near North Edge of Main Steam Valve N/A N/A Building 3.2-1 FIGURE 3.2-1 Line Designation, Safety Class Boundaries N/A N/A 3.3-1 FIGURE 3.3-1 Dynamic Load Factor Curve for Tornado Pressure Drop N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 3.4-1 FIGURE 3.4-1 Circulating and Service Water Pumphouse (Sheet 1 of 4) N/A 1 OF 4 3.4-1 FIGURE 3.4-1 Circulating and Service Water Pumphouse (Sheet 2 of 4) N/A 2 OF 4 3.4-1 FIGURE 3.4-1 Circulating and Service Water Pumphouse (Sheet 3 of 4) N/A 3 OF 4 3.4-1 FIGURE 3.4-1 Circulating and Service Water Pumphouse (Sheet 4 of 4) N/A 4 OF 4 3.5-1 FIGURE 3.5-1 Turbine Placement and Orientation for Three-Unit Site N/A N/A 3.5-2 FIGURE 3.5-2 Turbine Placement and Orientation Profile N/A N/A 3.6-1 FIGURE 3.6-1 Fluid Systems Subjected to Break and Crack Analysis N/A N/A 3.6-2 FIGURE 3.6-2 Relative Locations of Safety Related Equipment, N/A N/A Elevation 3 feet 8 inches 3.6-3 FIGURE 3.6-3 Relative Locations of Safety Related Equipment, N/A N/A Elevation 24 feet 6 inches 3.6-4 FIGURE 3.6-4 Relative Locations of Safety Related Equipment, N/A N/A Elevation 51 feet 4 inches 3.6-5 FIGURE 3.6-5 Relative Locations of Safety Related Equipment, N/A N/A Section 1-1 3.6-6 FIGURE 3.6-6 Relative Locations of Safety Related Equipment, N/A N/A Section 2-2 3.6-7 FIGURE 3.6-7 Relative Locations of Safety Related Equipment, N/A N/A Sections 3-3, 4-4 3.6-8 FIGURE 3.6-8 Main Steam System N/A N/A 3.6-8 FIGURE 3.6-8 Main Steam System N/A N/A 3.6-9 FIGURE 3.6-9 Main Steam System (Continued) N/A N/A 3.6-10 FIGURE 3.6-10 Feedwater System Postulated Pipe Rupture Locations N/A N/A 3.6-11 FIGURE 3.6-11 Feedwater System Pipe Rupture Restraints N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 3.6-11 NOTES TO FIGURE 3.6-11 N/A N/A 3.6-12 FIGURE 3.6-12 Reactor Coolant System - Primary Coolant Piping N/A N/A 3.6-12 NOTES TO FIGURE 3.6-12 N/A N/A 3.6-13 FIGURE 3.6-13 Reactor Coolant System - Low Pressure Safety Injection N/A N/A and Residual Heat Removal Piping 3.6-13 NOTES TO FIGURE 3.6-13 N/A N/A 3.6-14 FIGURE 3.6-14 Reactor Coolant System - Pressurizer Cubicle Piping N/A N/A 3.6-14 NOTES TO FIGURE 3.6-14 N/A N/A 3.6-15 FIGURE 3.6-15 Chemical and Volume Control System - Charging Line N/A N/A Piping 3.6-15 NOTES TO FIGURE 3.6-15 N/A N/A 3.6-16 FIGURE 3.6-16 Chemical and Volume Control System - Letdown Line N/A N/A Piping 3.6-16 NOTES TO FIGURE 3.6-16 N/A N/A 3.6-17 FIGURE 3.6-17 Chemical and Volume Control System - Seal Water N/A N/A Injection and Piping 3.6-18 FIGURE 3.6-18 Steam Generator Blowdown System N/A N/A 3.6-18 NOTES TO FIGURE 3.6-18 N/A N/A 3.6-19 FIGURE 3.6-19 Pipe Rupture Analysis Flow Chart N/A N/A 3.6-20 FIGURE 3.6-20 Variation of Steady State Steam Blowdown vs Friction N/A N/A 3.6-21 FIGURE 3.6-21 Pipe Restraint Intermediate Structure System, N/A N/A Mathematical Model 3.6-22 FIGURE 3.6-22 Laminated Strap Restraint for Small Lines N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 3.6-23 FIGURE 3.6-23 Feedwater System Short Loop Strap near the Steam N/A N/A Generator, NET Shear Force at Node 10 3.6-24 FIGURE 3.6-24 Feedwater System Short Loop Strap near the Steam N/A N/A Generator, NET Shear Force at Node 14 3.6-25 FIGURE 3.6-25 Feedwater System Short Loop Strap near the Steam N/A N/A Generator, NET Moment Force at Node 14 3.6-26 FIGURE 3.6-26 Force Acting on the Strap Node 8 N/A N/A 3.6-27 FIGURE 3.6-27 Feedwater System Short Loop Strap near the Steam N/A N/A Generator, Energy 3.6-28 FIGURE 3.6-28 Energy Balance Analysis Model N/A N/A 3.6-29 FIGURE 3.6-29 Pipe Crush Bumper N/A N/A 3.6-30 FIGURE 3.6-30 Pipe Crush Bumper N/A N/A 3.6-31 FIGURE 3.6-31 Omni Directional Pipe Rupture Restraint N/A N/A 3.6-32 FIGURE 3.6-32 Auxiliary Feedwater System N/A N/A 3.6-33 FIGURE 3.6-33 Reactor Coolant System Small Bore Piping in Steam N/A N/A Generator Cubicles 3.7B-1 FIGURE 3.7B-1 Horizontal Design Response Spectra 0.17g SSE N/A N/A 3.7B-2 FIGURE 3.7B-2 Horizontal Design Response Spectra 0.09g 1/2 OBE N/A N/A 3.7B-3 FIGURE 3.7B-3 Horizontal Time History Response Spectra 0.5 Percent N/A N/A Damping Value 3.7B-4 FIGURE 3.7B-4 Horizontal Time History Response Spectra 1.0 Percent N/A N/A Damping Value 3.7B-5 FIGURE 3.7B-5 Horizontal Time History Response Spectra 2.0 Percent N/A N/A Damping Value

Figure Number Figure Label Title Drawing Number Sheet 3.7B-6 FIGURE 3.7B-6 Horizontal Time History Response Spectra 5.0 Percent N/A N/A Damping Value 3.7B-7 FIGURE 3.7B-7 Horizontal Time History Response Spectra 7.0 Percent N/A N/A Damping Value 3.7B-8 FIGURE 3.7B-8 Horizontal Time History Response Spectra 10 Percent N/A N/A Damping Value 3.7B-9 FIGURE 3.7B-9 Dynamic Model of the Containment Structure N/A N/A 3.7B-10 FIGURE 3.7B-10 Dynamic Model of the Main Steam Valve Building N/A N/A 3.7B-11 FIGURE 3.7B-11 Dynamic Model of the Emergency Generator Enclosure N/A N/A N-S View 3.7B-12 FIGURE 3.7B-12 Dynamic Model of the Emergency Generator Enclosure N/A N/A E-W View 3.7B-13 FIGURE 3.7B-13 Reactor Containment Mat Elevation -37 feet 3 inches N/A N/A Amplified Response Spectra N-S Excitation SSE 3.7B-14 FIGURE 3.7B-14 Reactor Containment Mat Elevation -37 feet 3 inches N/A N/A Amplified Response Spectra E-W Excitation SSE 3.7B-15 FIGURE 3.7B-15 Reactor Containment Mat Elevation -37 feet 3 inches N/A N/A Amplified Response Spectra Vertical Excitation SSE 3.7B-16 FIGURE 3.7B-16 Reactor Containment Steam Generators Support Slab Elevation 3 feet 0 inches Amplified Response Spectra N/A N/A N-S Excitation SSE 3.7B-17 FIGURE 3.7B-17 Reactor Containment Steam Generators Support Slab Elevation 3 feet 0 inches Amplified Response Spectra E- N/A N/A W Excitation SSE

Figure Number Figure Label Title Drawing Number Sheet 3.7B-18 FIGURE 3.7B-18 Reactor Containment Steam Generators Support Slab Elevation 3 feet 0 inches Amplified Response Spectra N/A N/A Vertical Excitation SSE 3.7B-19 FIGURE 3.7B-19 Reactor Containment Top of Primary Shield Wall Elevation 24 feet 6 inches Amplified Response Spectra N/A N/A N-S Excitation SSE 3.7B-20 FIGURE 3.7B-20 Reactor Containment Top of Primary Shield Wall El 24 feet 6 inches Amplified Response Spectra E-W N/A N/A Excitation SSE 3.7B-21 FIGURE 3.7B-21 1 Reactor Containment Top of Primary Shield Wall Elevation 24 feet 6 inches Amplified Response Spectra N/A N/A Vertical Excitation SSE 3.7B-22 FIGURE 3.7B-22 Reactor Containment Operation Floor Elevation 50 feet 10 inches Amplified Response Spectra N-S Excitation N/A N/A SSE 3.7B-23 FIGURE 3.7B-23 Reactor Containment Operating Floor Elevation 50 feet 10 inches Amplified Response Spectra E-W Excitation N/A N/A SSE 3.7B-24 FIGURE 3.7B-24 Reactor Containment Operating Floor Elevation 50 feet 10 inches Amplified Response Spectra Vertical N/A N/A Excitation 3.7B-25 FIGURE 3.7B-25 Reactor Containment Top of Crane Wall Elevation 109 feet 1 inch Amplified Response Spectra N-S Excitation N/A N/A SSE 3.7B-26 FIGURE 3.7B-26 Reactor Containment Top of Crane Wall Elevation 109 feet 1 inch Amplified Response Spectra E-W Excitation N/A N/A SSE

Figure Number Figure Label Title Drawing Number Sheet 3.7B-27 FIGURE 3.7B-27 Reactor Containment Top of Crane Wall Elevation 109 feet 1 inch Amplified Response Spectra Vertical N/A N/A Excitation SSE 3.7B-28 FIGURE 3.7B-28 Reactor Containment Springline Elevation 104 feet 0 N/A N/A inches Amplified Response Spectra N-S Excitation SSE 3.7B-29 FIGURE 3.7B-29 Reactor Containment Springline Elevation 104 feet 0 N/A N/A inches Amplified Response Spectra E-W Excitation SSE 3.7B-30 FIGURE 3.7B-30 Reactor Containment Springline Elevation 104 feet 0 N/A N/A inches Amplified Response Spectra Vertical Excitation 3.7B-31 FIGURE 3.7B-31 Reactor Containment Dome Apex Elevation 163 feet 4 N/A N/A inches Amplified Response Spectra N-S Excitation SSE 3.7B-32 FIGURE 3.7B-32 Reactor Containment Dome Apex Elevation 163 feet 4 N/A N/A inches Amplified Response Spectra E-W Excitation SSE 3.7B-33 FIGURE 3.7B-33 Reactor Containment Dome Apex Elevation 163 feet 4 inches Amplified Response Spectra Vertical Excitation N/A N/A SSE 3.7B-34 FIGURE 3.7B-34 Main Steam Valve Building Mat Elevation 9 feet -0 N/A N/A inches Amplified Response Spectra N-S Excitation SSE 3.7B-35 FIGURE 3.7B-35 Main Steam Valve Building Mat Elevation 9 feet 0 N/A N/A inches Amplified Response Spectra E-W Excitation SSE 3.7B-36 FIGURE 3.7B-36 Main Steam Valve Building Mat Elevation 9 feet 0 inches Amplified Response Spectra Vertical Excitation N/A N/A SSE 3.7B-37 FIGURE 3.7B-37 Main Steam Valve Building Floor Slab Elevation 41 feet 0 inches Amplified Response Spectra N-S Excitation N/A N/A SSE

Figure Number Figure Label Title Drawing Number Sheet 3.7B-38 FIGURE 3.7B-38 Main Stem Valve Building Floor Slab Elevation 41 feet 0 inches Amplified Response Spectra E-W Excitation N/A N/A SSE 3.7B-39 FIGURE 3.7B-39 Main Steam Valve Building Floor Slab Elevation 41 feet 0 inches Amplified Response Spectra Vertical Excitation N/A N/A SSE 3.7B-40 FIGURE 3.7B-40 Main Steam Valve Building Roof Slab Elevation 85 feet 4 inches Amplified Response Spectra N-S Excitation N/A N/A SSE 3.7B-41 FIGURE 3.7B-41 Main Steam Valve Building Roof Slab Elevation 85 feet 4 inches Amplified Response Spectra E-W Excitation N/A N/A SSE 3.7B-42 FIGURE 3.7B-42 Main Steam Valve Building Roof Slab Elevation 85 feet 4 inches Amplified Response Spectra Vertical Excitation N/A N/A SSE 3.7B-43 FIGURE 3.7B-43 Emergency Generator Enclosure Transfer Function of Base of Structure Elevation 9 ft-0 in for Horizontal N/A N/A Acceleration N-S Excitation SSE 3.7B-44 FIGURE 3.7B-44 Emergency Generator Enclosure Transfer Function at Floor Slab Elevation 51 feet 0 inches for Horizontal N/A N/A Acceleration N-S Excitation SSE 3.7B-45 FIGURE 3.7B-45 Emergency Generator Enclosure Transfer Function at Roof Slab Elevation 66 feet 0 inches for Horizontal N/A N/A Acceleration N-S Excitation SSE 3.7B-46 FIGURE 3.7B-46 Emergency Generator Enclosure Transfer Function at Base of Structure Elevation 9 feet 0 inches for Vertical N/A N/A Acceleration Vertical Excitation SSE

Figure Number Figure Label Title Drawing Number Sheet 3.7B-47 FIGURE 3.7B-47 Emergency Generator Enclosure Transfer Function at Floor Slab Elevation 51 feet 0 inches for Vertical N/A N/A Acceleration Vertical Excitation SSE 3.7B-48 FIGURE 3.7B-48 Emergency Generator Enclosure Transfer Function at Roof Slab Elevation 66 feet 0 inches for Vertical N/A N/A Acceleration Vertical Excitation SSE 3.7B-49 FIGURE 3.7B-49 Emergency Generator Enclosure Transfer Function at Base of Structure Elevation 9 feet 0 inches for N/A N/A Horizontal Acceleration E-W Excitation SSE 3.7B-50 FIGURE 3.7B-50 Emergency Generator Enclosure Transfer Function at Floor Slab Elevation 51 feet 0 inches for Horizontal N/A N/A Acceleration E-W Excitation SSE 3.7B-51 FIGURE 3.7B-51 Emergency Generator Enclosure Transfer Function at Roof Slab Elevation 66 feet 0 inches for Horizontal N/A N/A Acceleration E-W Excitation SSE 3.7B-52 FIGURE 3.7B-52 Emergency Generator Enclosure Floor Slab Elevation 24 feet 6 inches Amplified Response Spectra N-S N/A N/A Excitation SSE 3.7B-53 FIGURE 3.7B-53 Emergency Generator Enclosure Floor Slab Elevation 24 feet 6 inches Amplified Response Spectra E-W N/A N/A Excitation SSE 3.7B-54 FIGURE 3.7B-54 Emergency Generator Enclosure Floor Slab Elevation 24 feet 6 inches Amplified Response Spectra Vertical N/A N/A Excitation SSE 3.7B-55 FIGURE 3.7B-55 Emergency Generator Enclosure Floor Slab Elevation 51 feet 0 inches Amplified Response Spectra N-S N/A N/A Excitation SSE

Figure Number Figure Label Title Drawing Number Sheet 3.7B-56 FIGURE 3.7B-56 Emergency Generator Enclosure Floor Slab Elevation 51 ft-0 in Amplified Response Spectra E-W Excitation N/A N/A SSE 3.7B-57 FIGURE 3.7B-57 Emergency Generator Enclosure Floor Slab Elevation 51 feet 0 inches Amplified Response Spectra Vertical N/A N/A Excitation SSE 3.7B-58 FIGURE 3.7B-58 Emergency Generator Enclosure Roof Slab Elevation 66 feet 0 inches Amplified Response Spectra N-S N/A N/A Excitation SSE 3.7B-59 FIGURE 3.7B-59 Emergency Generator Enclosure Roof Slab Elevation 66 feet 0 inches Amplified Response Spectra E-W N/A N/A Excitation SSE 3.7B-60 FIGURE 3.7B-60 Emergency Generator Enclosure Roof Slab Elevation 66 feet 0 inches Amplified Response Spectra Vertical N/A N/A Excitation SSE 3.7B-61 FIGURE 3.7B-61 Emergency Generator Enclosure Diesel Generator Mat Elevation 24 feet 0 inches Amplified Response Spectra N/A N/A N-S Excitation SSE 3.7B-62 FIGURE 3.7B-62 Emergency Generator Enclosure Diesel Generator Mat Elevation 24 feet 6 inches Amplified Response Spectra N/A N/A Vertical Excitation SSE 3.7B-63 FIGURE 3.7B-63 Emergency Generator Enclosure Horizontal Acceleration Time History at Bedrock N-S Excitation N/A N/A SSE 3.7B-64 FIGURE 3.7B-64 Emergency Generator Enclosure Horizontal Acceleration Time History at Base of Structure N-S N/A N/A Excitation SSE

Figure Number Figure Label Title Drawing Number Sheet 3.7B-65 FIGURE 3.7B-65 Typical Mathematical Model of a Piping System N/A N/A 3.7B-66 FIGURE 3.7B-66 Representation of Family of Peak Responses Curves N/A N/A within Broadened Resonant Peak 3.7B-67 FIGURE 3.7B-67 Hypothetical vs Actual Response of Multiple Modes N/A N/A within Broadened Response Peak 3.7B-68 FIGURE 3.7B-68 Justification of Static Load Factor N/A N/A 3.7B-69 FIGURE 3.7B-69 Typical Amplified Response Spectra N/A N/A 3.7B-70 FIGURE 3.7B-70 Model Beams N/A N/A 3.7B-71 FIGURE 3.7B-71 Damping Value for Seismic Analysis of Piping N/A N/A 3.7N-1 FIGURE 3.7N-1 Multi-Degree of Freedom System N/A N/A 3.8-1 FIGURE 3.8-1 Containment Structure Foundation Detail N/A N/A 3.8-2 FIGURE 3.8-2 Typical Detail of Dome Cylinder Junction N/A N/A 3.8-3 FIGURE 3.8-3 Knuckle Plate N/A N/A 3.8-4 FIGURE 3.8-4 Mat Reinforcement with Radial Shear Bar Assembly N/A N/A 3.8-5 FIGURE 3.8-5 Reinforcement Around Main Steam Penetrations N/A N/A 3.8-6 FIGURE 3.8-6 Reinforcing Details Sections through Ring Beam of N/A N/A Personnel Access Lock 3.8-7 FIGURE 3.8-7 Reinforcing Details Personnel Access Lock Opening N/A N/A 3.8-8 FIGURE 3.8-8 Typical Reinforcing Details Sections through Ring N/A N/A Beam of Equipment Access Hatch 3.8-9 FIGURE 3.8-9 Reinforcing Details Equipment Access Hatch Opening N/A N/A 3.8-10 FIGURE 3.8-10 Base Plate Details Containment Enclosure Structure N/A N/A 3.8-11 FIGURE 3.8-11 Ring at Apex of Containment Structure Dome N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 3.8-12 FIGURE 3.8-12 Elevation Dome Maintenance Truss N/A N/A 3.8-13 FIGURE 3.8-13 Liner Knuckle Plate N/A N/A 3.8-14 FIGURE 3.8-14 Basic Liner Dimensions N/A N/A 3.8-15 FIGURE 3.8-15 Typical Piping Penetrations N/A N/A 3.8-16 FIGURE 3.8-16 Typical Sleeved Piping Penetration N/A N/A 3.8-17 FIGURE 3.8-17 Multiple Pipe Penetration Assembly N/A N/A 3.8-18 FIGURE 3.8-18 Unsleeved Piping Penetration N/A N/A 3.8-19 FIGURE 3.8-19 Electrical Penetration N/A N/A 3.8-20 FIGURE 3.8-20 Fuel Transfer Tube N/A N/A 3.8-21 FIGURE 3.8-21 Personnel Hatch N/A N/A 3.8-22 FIGURE 3.8-22 Equipment Hatch N/A N/A 3.8-23 FIGURE 3.8-23 Containment Structure Foundation Detail with Ring N/A 1 OF 2 Girder (Sheet 1 of 2) 3.8-23 FIGURE 3.8-23 Containment Structure Foundation Detail with Ring N/A 2 OF 2 Girder (Sheet 2 of 2) 3.8-24 FIGURE 3.8-24 Detail of Ring Girder at ESF Building (Sheet 1 of 3) N/A 1 OF 3 3.8-24 FIGURE 3.8-24 Detail of Ring Girder at ESF Building (Sheet 2 of 3) N/A 2 OF 3 3.8-24 FIGURE 3.8-24 Detail of Ring Girder at ESF Building (Sheet 3 of 3) N/A 3 OF 3 3.8-25 FIGURE 3.8-25 Containment Structure Mat Moment and Shear N/A N/A Diagrams 3.8-26 FIGURE 3.8-26 Containment Structure Mat Moment and Shear N/A N/A Diagrams

Figure Number Figure Label Title Drawing Number Sheet 3.8-27 FIGURE 3.8-27 Containment Structure Mat Moment and Shear N/A N/A Diagrams 3.8-28 FIGURE 3.8-28 Containment Structure Mat Moment and Shear N/A N/A Diagrams 3.8-29 FIGURE 3.8-29 Containment Structure Mat Moment and Shear N/A N/A Diagrams 3.8-30 FIGURE 3.8-30 Containment Structure Mat Moment and Shear N/A N/A Diagrams 3.8-31 FIGURE 3.8-31 Containment Structure Mat Moment and Shear N/A N/A Diagrams 3.8-32 FIGURE 3.8-32 Load Plot Nomenclature N/A N/A 3.8-33 FIGURE 3.8-33 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-34 FIGURE 3.8-34 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-35 FIGURE 3.8-35 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-36 FIGURE 3.8-36 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-37 FIGURE 3.8-37 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-38 FIGURE 3.8-38 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-39 FIGURE 3.8-39 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-40 FIGURE 3.8-40 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-41 FIGURE 3.8-41 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-42 FIGURE 3.8-42 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-43 FIGURE 3.8-43 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-44 FIGURE 3.8-44 Containment Structure Wall and Dome Force Resultants N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 3.8-45 FIGURE 3.8-45 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-46 FIGURE 3.8-46 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-47 FIGURE 3.8-47 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-48 FIGURE 3.8-48 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-49 FIGURE 3.8-49 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-50 FIGURE 3.8-50 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-51 FIGURE 3.8-51 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-53 FIGURE 3.8-53 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-54 FIGURE 3.8-54 Containment Structure Wall and Dome Force Resultants N/A N/A 3.8-55 FIGURE 3.8-55 Containment Structure Wall and Dome N/A N/A 3.8-56 FIGURE 3.8-56 Details of Wall Diagonals at Containment Mat N/A N/A 3.8-57 FIGURE 3.8-57 Details of Waterproof Membrane (Sheet 1 of 2)(Part 1 of (SHT 1 O N/A

2) (Part 1 OF 3.8-57 FIGURE 3.8-57 Details of Waterproof Membrane (Sheet 1 of 2)(Part 2 of (SHT 1 O N/A
2) (Part 2 OF 3.8-57 FIGURE 3.8-57 Details of Waterproof Membrane (Sheet 2 of 2) N/A 2 OF 2 3.8-58 FIGURE 3.8-58 Displacement Profile for Containment Shell Under N/A 1 OF 2 Pressure Test (Predicted) (Sheet 1 of 2) 3.8-58 FIGURE 3.8-58 Displacement Profile for Containment Shell Under N/A 2 OF 2 Pressure Test (Predicted) (Sheet 2 of 2) 3.8-59 FIGURE 3.8-59 Containment Structure, Plan Views N/A N/A 3.8-60 FIGURE 3.8-60 Containment Structure, Elevation Views N/A N/A 3.8-61 FIGURE 3.8-61 Containment Enclosure Building N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 1 of 10) N/A 1 OF 1 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 2 of 10) N/A 2 OF 1 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 3 of 10) N/A 3 OF 1 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 4 of 10) N/A 4 OF 1 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 5 of 10) N/A 5 OF 10 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 6 of 10) N/A 6 OF 10 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 7 of 10) N/A 7 OF 10 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 8 of 10) N/A 8 OF 10 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 9 of 10) N/A 9 OF 10 3.8-62 FIGURE 3.8-62 Auxiliary Building (Sheet 10 of 10) N/A 10 OF 1 3.8-63 FIGURE 3.8-63 Fuel Building (Sheet 1 of 6) N/A 1 OF 6 3.8-63 FIGURE 3.8-63 Fuel Building (Sheet 2 of 6) N/A 2 OF 6 3.8-63 FIGURE 3.8-63 Fuel Building (Sheet 3 of 6) N/A 3 OF 6 3.8-63 FIGURE 3.8-63 Fuel Building (Sheet 4 of 6) N/A 4 OF 6 3.8-63 FIGURE 3.8-63 Fuel Building (Sheet 5 of 6) N/A 5 OF 6 3.8-63 FIGURE 3.8-63 Fuel Building (Sheet 6 of 6) N/A 6 OF 6 3.8-64 FIGURE 3.8-64 Control Room Area (Sheet 1 of 4) N/A 1 OF 4 3.8-64 FIGURE 3.8-64 Control Room Area (Sheet 2 of 4) N/A 2 OF 4 3.8-64 FIGURE 3.8-64 Control Room Area (Sheet 3 of 4) N/A 3 OF 4 3.8-64 FIGURE 3.8-64 Control Room Area (Sheet 4 of 4) N/A 4 OF 4 3.8-65 FIGURE 3.8-65 Cable Tunnel N/A N/A 3.8-66 FIGURE 3.8-66 Emergency Generator Enclosure (Sheet 1 of 5) N/A 1 OF 5

Figure Number Figure Label Title Drawing Number Sheet 3.8-66 NOTES TO FIGURE 3.8-66 Data for Pipe Rupture Restraints Steam Generator N/A N/A Blowdown System 3.8-66 FIGURE 3.8-66 Emergency Generator Enclosure (Sheet 2 of 5) N/A 2 OF 5 3.8-66 FIGURE 3.8-66 Emergency Generator Enclosure (Sheet 3 of 5) N/A 3 OF 5 3.8-66 FIGURE 3.8-66 Emergency Generator Enclosure (Sheet 4 of 5) N/A 4 OF 5 3.8-66 FIGURE 3.8-66 Emergency Generator Enclosure (Sheet 5 of 5) N/A 5 OF 5 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 1 of 9) N/A 1 OF 9 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 2 of 9) N/A 2 OF 9 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 3 of 9) N/A 3 OF 9 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 4 of 9) N/A 4 OF 9 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 5 of 9) N/A 5 OF 9 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 6 of 9) N/A 6 OF 9 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 7 of 9) N/A 7 OF 9 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 8 of 9) N/A 8 OF 9 3.8-67 FIGURE 3.8-67 Engineered Safety Features Building (Sheet 9 of 9) N/A 9 OF 9 3.8-68 FIGURE 3.8-68 Main Steam Valve Building (Sheet 1 of 4) N/A 1 OF 4 3.8-68 FIGURE 3.8-68 Main Steam Valve Building (Sheet 2 of 4) N/A 2 OF 4 3.8-68 FIGURE 3.8-68 Main Steam Valve Building (Sheet 3 of 4) N/A 3 OF 4 3.8-68 FIGURE 3.8-68 Main Steam Valve Building (Sheet 4 of 4) N/A 4 OF 4 3.8-69 FIGURE 3.8-69 Circulating and Service Water Pumphouse (Sheet 1 of 4) N/A 1 OF 4 3.8-69 FIGURE 3.8-69 Circulating and Service Water Pumphouse (Sheet 2 of 4) N/A 2 OF 4 3.8-69 FIGURE 3.8-69 Circulating and Service Water Pumphouse (Sheet 3 of 4) N/A 3 OF 4

Figure Number Figure Label Title Drawing Number Sheet 3.8-69 FIGURE 3.8-69 Circulating and Service Water Pumphouse (Sheet 4 of 4) N/A 4 OF 4 3.8-70 FIGURE 3.8-70 Recombiner Building (Sheet 1 of 4) N/A 1 OF 4 3.8-70 FIGURE 3.8-70 Recombiner Building (Sheet 2 of 4) N/A 2 OF 4 3.8-70 FIGURE 3.8-70 Recombiner Building (Sheet 3 of 4) N/A 3 OF 4 3.8-70 FIGURE 3.8-70 Recombiner Building (Sheet 4 of 4) N/A 4 OF 4 3.8-71 FIGURE 3.8-71 Circulating Discharge Structure and Tunnel N/A 1 OF 4 3.8-72 FIGURE 3.8-72 Service Building (Sheet 1 of 4) N/A 1 OF 4 3.8-72 FIGURE 3.8-72 Service Building (Sheet 2 of 4) N/A 2 OF 4 3.8-72 FIGURE 3.8-72 Service Building (Sheet 3 of 4) N/A 3 OF 4 3.8-72 FIGURE 3.8-72 Service Building (Sheet 4 of 4) N/A 4 OF 4 3.8-73 FIGURE 3.8-73 Turbine Building (Sheet 1 of 5) N/A 1 OF 5 3.8-73 FIGURE 3.8-73 Turbine Building (Sheet 2 of 5) N/A 2 OF 5 3.8-73 FIGURE 3.8-73 Turbine Building (Sheet 3 of 5) N/A 3 OF 5 3.8-73 FIGURE 3.8-73 Turbine Building (Sheet 4 of 5) N/A 4 OF 5 3.8-73 FIGURE 3.8-73 Turbine Building (Sheet 5 of 5) N/A 5 OF 5 3.8-74 FIGURE 3.8-74 Solid and Liquid Waste Disposal Building (Sheet 1 of 7) N/A 1 OF 7 3.8-74 FIGURE 3.8-74 Solid and Liquid Waste Disposal Building (Sheet 2 of 7) N/A 2 OF 7 3.8-74 FIGURE 3.8-74 Solid and Liquid Waste Disposal Building (Sheet 3 of 7) N/A 3 OF 7 3.8-74 FIGURE 3.8-74 Solid and Liquid Waste Disposal Building (Sheet 4 of 7) N/A 4 OF 7 3.8-74 FIGURE 3.8-74 Solid and Liquid Waste Disposal Building (Sheet 5 of 7) N/A 5 OF 7 3.8-74 FIGURE 3.8-74 Solid and Liquid Waste Disposal Building (Sheet 6 of 7) N/A 6 OF 7 3.8-74 FIGURE 3.8-74 Solid and Liquid Waste Disposal Building (Sheet 7 of 7) N/A 7 OF 7

Figure Number Figure Label Title Drawing Number Sheet 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 1 of 12) N/A 1 OF 1 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 2 of 12) N/A 2 OF 1 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 3 of 12) N/A 3 OF 1 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 4 of 12) N/A 4 OF 1 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 5 of 12) N/A 5 OF 12 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 6 of 12) N/A 6 OF 12 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 7 of 12) N/A 7 OF 12 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 8 of 12) N/A 8 OF 12 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 9 of 12) N/A 9 OF 12 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 10 of 12) N/A 10 OF 1 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 11 of 12) N/A 11 OF 1 3.8-75 FIGURE 3.8-75 Warehouse No. 5 (Sheet 12 of 12) N/A 12 OF 1 3.8-76 FIGURE 3.8-76 Auxiliary Boiler Enclosure (Sheet 1 of 5) N/A 1 OF 5 3.8-76 FIGURE 3.8-76 Auxiliary Boiler Enclosure (Sheet 2 of 5) N/A 2 OF 5 3.8-76 FIGURE 3.8-76 Auxiliary Boiler Enclosure (Sheet 3 of 5) N/A 3 OF 5 3.8-76 FIGURE 3.8-76 Auxiliary Boiler Enclosure (Sheet 4 of 5) N/A 4 OF 5 3.8-76 FIGURE 3.8-76 Auxiliary Boiler Enclosure (Sheet 5 of 5) N/A 5 OF 5 3.8-77 FIGURE 3.8-77 Arrangement of Horizontal Shear Keys N/A N/A 3.8-78 FIGURE 3.8-78 Typical Shear Key Detail N/A N/A 3.8-79 FIGURE 3.8-79 Fuel Pool Temperature Transients N/A N/A 3.8-80 FIGURE 3.8-80 Fuel Pool--Fuel Building Temperature Conditions N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 3.8-81 FIGURE 3.8-81 Fuel Pool Temperature Transients--for Higher N/A N/A Enrichment Fuel 3.8-82 FIGURE 3.8-82 Fuel Pool Temperature Transients--Full Core Offload N/A N/A 3.8-83 FIGURE 3.8-83 Millstone Stack Elevations and Sections N/A N/A 3.8-84 FIGURE 3.8-84 Millstone Stack - Mathematical Model N/A N/A 3.9B-1 FIGURE 3.9B-1 Reactor Coolant PPG N/A N/A 3.9B-2 FIGURE 3.9B-2 Dynamic Model - Typical RCS Loop N/A N/A 3.9B-3 FIGURE 3.9B-3 Dynamic Model - Center Section N/A N/A 3.9B-4 FIGURE 3.9B-4 X2 View - Rotated Axes N/A N/A 3.9B-5 FIGURE 3.9B-5 Snubber Orientation N/A N/A 3.9N-1 FIGURE 3.9N-1 Reactor Pressure Vessel and Internals System Model N/A N/A 3.9N-2 FIGURE 3.9N-2 Deleted by PKG FSC 07-MP3-039 N/A N/A 3.9N-3 FIGURE 3.9N-3 RPV Support Model for Westinghouse Internals N/A N/A Response Analysis 3.9N-4 FIGURE 3.9N-4 Control Rod Drive Mechanism N/A N/A 3.9N-5 FIGURE 3.9N-5 Control Rod Drive Mechanism Schematic N/A N/A 3.9N-6 FIGURE 3.9N-6 Nominal Latch Clearance at Minimum and Maximum N/A N/A Clearance 3.9N-7 FIGURE 3.9N-7 Control Rod Drive Mechanism Latch Clearance N/A N/A Thermal Effect 3.9N-8 FIGURE 3.9N-8 Lower Core Support Assembly (Core Barrel Assembly) N/A N/A 3.9N-9 FIGURE 3.9N-9 Upper Core Support Assembly N/A N/A 3.9N-10 FIGURE 3.9N-10 Plan View of Upper Core Support Assembly N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 3.9N-11 FIGURE 3.9N-11 Neutron Shield Panel Design N/A N/A 3.9N-12 FIGURE 3.9N-12 Neutron Shield Panel Design Details N/A N/A 3A.1.2-1 FIGURE 3A.1.2-1 One Hundred-Element Idealization of Thin-Wall N/A N/A Cylinder 3A.1.4-1 FIGURE 3A.1.4-1 Element Plot N/A N/A 3A.1.4-2 FIGURE 3A.1.4-2 Harmonic Axisymmetric Plain Strain N/A N/A 3A.1.5-1 FIGURE 3A.1.5-1 TAC2D Sample Problem Thermal Model N/A N/A 3A.1.5-2 FIGURE 3A.1.5-2 Transient Temperatures in a Right Circular Cylinder-N/A N/A Comparison of TAC2D Results with Series Solution 3A.1.6-1 FIGURE 3A.1.6-1 Structural Model N/A N/A 3A.1.7-1 FIGURE 3A.1.7-1 Finite Element Grid for PLAXLY-FLUSH Comparison N/A N/A 3A.1.7-2 FIGURE 3A.1.7-2 Horizontal Amplified Response Spectra at Top Mass in N/A N/A Beam Structure 3A.2.3-1 FIGURE 3A.2.3-1 Target for Low Trajectory Missile N/A N/A 3A.2.11-1 FIGURE 3A.2.11-1 Cantilever Pipe Used in MIT Experiment N/A N/A 3A.3-1 FIGURE 3A.3-1 Mathematical Model for Flexibility Analysis N/A N/A Verification 3A.3-2 FIGURE 3A.3-2 NUPIPE Program Force Time-History Verification N/A N/A 3A.3-3 FIGURE 3A.3-3 Mathematical Model for Class 1 Stress Verification N/A N/A 3A.3-4 FIGURE 3A.3-4 Test Problem - SAVAL N/A N/A 3A.3-5 FIGURE 3A.3-5 Sudden Discharge of a Gas from a Pipeline through a N/A N/A Nozzle 3A.3-6 FIGURE 3A.3-6 Sudden Discharge of a Gas from a Pipeline through a Nozzle

Figure Number Figure Label Title Drawing Number Sheet 3A.3-7 FIGURE 3A.3-7 Comparison of Pressure Response at the Closed End N/A N/A 3A.3-8 FIGURE 3A.3-8 Comparison of Pressure Response at the Open End N/A N/A 3A.3-9 FIGURE 3A.3-9 Comparison of Pressure Responses by STEHAM and N/A N/A Experiment 3A.3-10 FIGURE 3A.3-10 Hydraulic Network for Verification Problem N/A N/A 3A.3-11 FIGURE 3A.3-11 Hydraulic Network for WATHAM Verification N/A N/A 3A.3-12 FIGURE 3A.3-12 Head versus Time Plot for Junction J N/A N/A 3A.3-13 FIGURE 3A.3-13 Head versus Time Plot at Valve N/A N/A 3A.3-14 FIGURE 3A.3-14 Design Input to a Problem N/A N/A 3A.3-15 FIGURE 3A.3-15 Pipe 1 Segment 1 Force-Time History N/A N/A 4.2-1 FIGURE 4.2-1 Fuel Assembly Cross Section 17 x 17 N/A N/A 4.2-2 FIGURE 4.2-2 Comparison of the 17 x 17 V5H Fuel Assembly and the N/A N/A 17 x 17 Standard Fuel Assembly 4.2-3 FIGURE 4.2-3 17 x 17 Vantage 5-H Fuel Rod Assembly N/A N/A 4.2-4 FIGURE 4.2-4 Plan View N/A N/A 4.2-5 FIGURE 4.2-5 Grid to Thimble Attachment Joints N/A N/A 4.2-6 FIGURE 4.2-6 Thimble/Insert/Top Grid Sleeve Bulge Joint Geometry N/A N/A 4.2-7 FIGURE 4.2-7 Guide Thimble to Bottom Nozzle Joint N/A N/A 4.2-8 FIGURE 4.2-8 Rod Cluster Control and Drive Rod Assembly with N/A N/A Interfacing Components 4.2-9 FIGURE 4.2-9 Deleted by FSARCR PKG FSC 08-MP3-027 N/A N/A 4.2-9a FIGURE 4.2-9a Full Length Rod Cluster Control Assembly N/A N/A (Westinghouse)

Figure Number Figure Label Title Drawing Number Sheet 4.2-9b FIGURE 4.2-9b Full Length Rod Cluster Control Assembly and N/A N/A Absorber Rod (AREVA) 4.2-10 FIGURE 4.2-10 Absorber Rod (Westinghouse) N/A N/A 4.2-11 FIGURE 4.2-11 Burnable Absorber Assembly N/A N/A 4.2-12 FIGURE 4.2-12 Not Used N/A N/A 4.2-13 FIGURE 4.2-13 Primary Source Assembly N/A N/A 4.2-14 FIGURE 4.2-14 Not Used N/A N/A 4.2-14a FIGURE 4.2-14a Single Encapsulated Secondary Source Assembly N/A N/A 4.2-14b FIGURE 4.2-14b Double Encapsulated Secondary Source Assembly N/A N/A 4.2-15 FIGURE 4.2-15 Thimble Plug Assembly N/A N/A 4.3-1 FIGURE 4.3-1 Fuel Loading Arrangement N/A N/A 4.3-2 FIGURE 4.3-2 Typical Production and Consumption of Higher Isotopes N/A N/A 4.3-3 FIGURE 4.3-3 Typical Boron Concentration Versus First Cycle Burnup N/A N/A with and without Burnable Absorber Rods 4.3-4 FIGURE 4.3-4 Typical Integral Fuel Burnable Absorber Rod N/A N/A Arrangement within an Assembly 4.3-5 FIGURE 4.3-5 Burnable Absorber Loading Pattern (Typical) N/A N/A 4.3-5a FIGURE 4.3-5a Integral Fuel Burnable Loading Pattern (Cycle 7) N/A N/A 4.3-17 FIGURE 4.3-17 Comparison of a Typical Assembly Axial Power Distribution with Core Average Axial Distribution Bank N/A N/A D Slightly Inserted 4.3-21 FIGURE 4.3-21 Typical Maximum Normalized FQ x Power Versus N/A N/A Axial Height

Figure Number Figure Label Title Drawing Number Sheet 4.3-24 FIGURE 4.3-24 Typical Comparison Between Calculated and Measured N/A N/A Relative Fuel Assembly Power Distribution 4.3-25 FIGURE 4.3-25 Comparison of Typical Calculated and Measured Axial N/A N/A Shapes 4.3-26 FIGURE 4.3-26 Typical Measured Values of FQ for Full Power Rod N/A N/A Configurations 4.3-27 FIGURE 4.3-27 Typical Doppler Temperature Coefficient at Beginning-N/A N/A of-Life and End-of-Life, Cycle 1 4.3-28 FIGURE 4.3-28 Typical Doppler - Only Power Coefficient at Beginning-N/A N/A of-Life and End-of-Life, Cycle 1 4.3-29 FIGURE 4.3-29 Typical Doppler - Only Power Defect at Beginning-of-N/A N/A Life and End-of-Life, Cycle 1 4.3-30 FIGURE 4.3-30 Typical Moderator Temperature Coefficient at N/A N/A Beginning-of-Life, Cycle 1, No Rods 4.3-31 FIGURE 4.3-31 Typical Moderator Temperature Coefficient at End-of-N/A N/A Life, Cycle 1 4.3-32 FIGURE 4.3-32 Typical Moderator Temperature Coefficient as a Function of Boron Concentration at Beginning-of-Life, N/A N/A Cycle 1, No Rods 4.3-33 FIGURE 4.3-33 Typical Hot Full Power Temperature Coefficient during N/A N/A Cycle 1 for the Critical Boron Concentration 4.3-34 FIGURE 4.3-34 Typical Total Power Coefficient at Beginning-of-Life N/A N/A and End-of-Life, Cycle 1 4.3-35 FIGURE 4.3-35 Typical Total Power Defect at Beginning-of-Life and N/A N/A End-of-Life, Cycle 1 4.3-36 FIGURE 4.3-36 Rod Cluster Control Assembly Pattern N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 4.3-37 FIGURE 4.3-37 Typical Accidental Simultaneous Withdrawal of Two Control Banks at EOL, HZP, Bank D and B Moving in N/A N/A the Same Plane 4.3-38 FIGURE 4.3-38 Design Trip Curve (Typical) N/A N/A 4.3-39 FIGURE 4.3-39 Typical Normalized Rod Worth Versus Percent N/A N/A Insertion, All Rods Out But One 4.3-40 FIGURE 4.3-40 Typical Axial Offset Versus Time, PWR Core with a 12 N/A N/A Foot Height and 121 Assemblies 4.3-41 FIGURE 4.3-41 Typical X-Y Xenon Test Thermocouple Response N/A N/A Quadrant Tilt Difference Versus Time 4.3-42 FIGURE 4.3-42 Typical Calculated and Measured Doppler Defect and Coefficients at BOL, 2-Loop Plant, 121 Assemblies, 12 N/A N/A Foot Core 4.4-1 FIGURE 4.4-1 Deleted by FSARCR PKG FSC 07-MP3-040 N/A N/A 4.4-2 FIGURE 4.4-2 TDS Versus Reynolds Number for 26 Inch Grid Spacing N/A N/A 4.4-3 FIGURE 4.4-3 Typical Normalized Radial Flow and Enthalpy N/A N/A Distribution at 4 Foot Elevation 4.4-4 FIGURE 4.4-4 Typical Normalized Radial Flow and Enthalpy N/A N/A Distribution at 8 Foot Elevation 4.4-5 FIGURE 4.4-5 Typical Normalized Radial Flow and Enthalpy N/A N/A Distribution at 12 Foot Elevation-Core Exit 4.4-6 FIGURE 4.4-6 Deleted by FSARCR PKG FSC 07-MP3-040 N/A N/A 4.4-7 FIGURE 4.4-7 Thermal Conductivity of UO2 (Data Corrected to 95 N/A N/A Percent Theoretical Density) 4.4-8 FIGURE 4.4-8 Reactor Coolant System Temperature-Percent Power N/A N/A Map

Figure Number Figure Label Title Drawing Number Sheet 4.4-9 FIGURE 4.4-9 Not Used N/A N/A 4.4-10 FIGURE 4.4-10 Distribution of Incore Instrumentation N/A N/A 4.4-11 FIGURE 4.4-11 ICC Functional Block Diagram (Train A-Train B N/A N/A Similar) 4.4-12 FIGURE 4.4-12 Typical Reactor Coolant Parameters Following Small N/A N/A Break LOCA 4.4-13 FIGURE 4.4-13 HJTCS Functional Configuration N/A N/A 4.4-14 FIGURE 4.4-14 Typical Probe/Sensor Configuration N/A N/A 4.4-15 FIGURE 4.4-15 HJTC Sensor - HJTC/Splash Shield N/A N/A 4.4-16 FIGURE 4.4-16 Electrical Diagram of HJTC N/A N/A 4.4-17 FIGURE 4.4-17 Typical Configuration (One Channel) N/A N/A 4.4-18 FIGURE 4.4-18 Heated Junction Thermocouple Probe Assembly N/A N/A 4.4-19 FIGURE 4.4-19 HJTC Probe Holder Support Tube Installation N/A N/A 4.4-20 FIGURE 4.4-20 HJTC Probe Pressure Boundary Installation N/A N/A 4.4-21 FIGURE 4.4-21 Probe Handling Hardware Configuration N/A N/A

\4.4-21 FIGURE 4.4-21 Probe Handling Hardware Configuration N/A N/A

\5.1-1 FIGURE 5.1-1 (Sheets 1-6) P&IDs Reactor Coolant System 25212-26902 (a) SH 1

\5.1-1 FIGURE 5.1-1 (Sheets 1-6) P&IDs Reactor Coolant System 25212-26902 (a) SH 2

\5.1-1 FIGURE 5.1-1 (Sheets 1-6) P&IDs Reactor Coolant System 25212-26902 (a) SH 3

\5.1-1 FIGURE 5.1-1 (Sheets 1-6) P&IDs Reactor Coolant System 25212-26902 (a) SH 4

\5.1-1 FIGURE 5.1-1 (Sheets 1-6) P&IDs Reactor Coolant System 25212-26902 (a) SH 5

Figure Number Figure Label Title Drawing Number Sheet

\5.1-1 FIGURE 5.1-1 (Sheets 1-6) P&IDs Reactor Coolant System 25212-26902 (a) SH 6

\5.1-2 FIGURE 5.1-2 Reactor Coolant System Process Flow Design N/A N/A

\5.1-2 NOTES TO FIGURE 5.1-2 N/A N/A

\5.2-1 FIGURE 5.2-1 Reactor Vessel Inspection Area N/A N/A

\5.2-2 FIGURE 5.2-2 Model F Steam Generator Inspection Area N/A N/A

\5.2-3 FIGURE 5.2-3 Pressurizer Inspection Areas N/A N/A

\5.3-1 FIGURE 5.3-1 Identification and Location of Beltline Region Material N/A N/A for the Reactor Vessel

\5.3-2 FIGURE 5.3-2 Reactor Vessel N/A N/A

\5.4-1 FIGURE 5.4-1 Reactor Coolant Pump N/A N/A

\5.4-2 FIGURE 5.4-2 Reactor Coolant Pump Estimated Performance N/A N/A Characteristics

\5.4-3 FIGURE 5.4-3 Model F Steam Generator N/A N/A

\5.4-4 FIGURE 5.4-4 Quatrefoil Tube Support Plates N/A N/A

\5.4-5 FIGURE 5.4-5 (Sheets 1-3) P&IDs Low Pressure Safety Injection /

25212-26912 (a) SH 1 OF Containment Recirculation

\5.4-5 FIGURE 5.4-5 (Sheets 1-3) P&IDs Low Pressure Safety Injection /

25212-26912 (a) SH 2 OF Containment Recirculation

\5.4-5 FIGURE 5.4-5 (Sheets 1-3) P&IDs Low Pressure Safety Injection /

25212-26912 (a) SH 3 OF Containment Recirculation 5.4-6 FIGURE 5.4-6 Residual Heat Removal System Process Flow Diagram N/A N/A (Mode A) 5.4-6 FIGURE 5.4-6 Residual Heat Removal System Process Flow Diagram N/A N/A (Mode A)

Figure Number Figure Label Title Drawing Number Sheet 5.4-7 FIGURE 5.4-7 Pressurizer Relief Tank N/A N/A 5.4-8 FIGURE 5.4-8 Pressurizer N/A N/A 5.4-9 FIGURE 5.4-9 RPV Support System N/A N/A 5.4-10 FIGURE 5.4-10 Leveling Device (Typical) RPV Support System N/A N/A 5.4-11 FIGURE 5.4-11 Vertical Supports (Typical) Reactor Coolant Pumps and N/A N/A Steam Generator 5.4-11 FIGURE 5.4-11 Vertical Supports (Typical) Reactor Coolant Pumps and N/A N/A Steam Generator 5.4-12 FIGURE 5.4-12 Lateral Support (Typical) Steam Generator N/A N/A 5.4-13 FIGURE 5.4-13 Lateral Support (Typical) Reactor Coolant Pump N/A N/A 5.4-14 FIGURE 5.4-14 Pressurizer Support (Sheet 1 of 2) 1 OF 2 N/A 5.4-14 FIGURE 5.4-14 Pressurizer Support (Sheet 2 of 2) 2 OF 2 N/A 5.4-15 FIGURE 5.4-15 Pressurizer Safety Valve Support System (Sheet 1 of 2) 1 OF 2 N/A 5.4-15 FIGURE 5.4-15 Pressurizer Safety Valve Support System (Sheet 2 of 2) 2 OF 2 N/A 6.0-1 FIGURE 6.0-1 Engineered Safety Features N/A N/A 6.2-1 FIGURE 6.2-1 Containment Pressure Response - Double Ended LOCA N/A N/A (Break Location) 6.2-2 FIGURE 6.2-2 Containment Pressure Response - Pump Suction LOCA N/A N/A (Break Size) 6.2-3 FIGURE 6.2-3 Containment Vapor Temperature Response - LOCA N/A N/A 6.2-4 FIGURE 6.2-4 Containment Liner Temperature Response N/A N/A 6.2-5 FIGURE 6.2-5 Containment Depressurization Response - LOCA N/A N/A 6.2-6 FIGURE 6.2-6 Containment Sump Temperature Response N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 6.2-7 FIGURE 6.2-7 Containment Pressure from 1.4 square foot MSLB at 0%

N/A N/A Power No Entrainment - Limiting Peak Pressure Case 6.2-8 FIGURE 6.2-8 Containment Temperature From 1.4 square foot MSLB at Full Power, No Entrainment - Limiting Peak N/A N/A Temperature Case 6.2-9 FIGURE 6.2-9 Containment Liner Temperature From 1.4 square foot at N/A N/A 0% Power, No Entrainment - Peak Temperature Case 6.2-10 FIGURE 6.2-10 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-11 FIGURE 6.2-11 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-12 FIGURE 6.2-12 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-13 FIGURE 6.2-13 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-14 FIGURE 6.2-14 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-15 FIGURE 6.2-15 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-16 FIGURE 6.2-16 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-17 FIGURE 6.2-17 Pressurizer Subcompartment Elevation View with Nodal N/A N/A Arrangement 6.2-18 FIGURE 6.2-18 Plan View for the Pressurizer Subcompartment N/A N/A Elevation 95.3 feet 6.2-18A FIGURE 6.2-18A Plan View for the Pressurizer Subcompartment N/A N/A Elevation 74.2 feet 6.2-18B FIGURE 6.2-18B Plan View for the Pressurizer Subcompartment N/A N/A Elevation 51.3 feet 6.2-18C FIGURE 6.2-18C Plan View for the Pressurizer Subcompartment N/A N/A Elevation 25.7 feet

Figure Number Figure Label Title Drawing Number Sheet 6.2-18D FIGURE 6.2-18D Plan View for the Pressurizer Subcompartment N/A N/A Elevation 12.75 feet 6.2-19 FIGURE 6.2-19 Steam Generator Subcompartment Elevation with Nodal N/A N/A Arrangement 6.2-20 FIGURE 6.2-20 Plan View for the Steam Generator Subcompartment N/A N/A Elevation 3 feet 8 inches 6.2-21 FIGURE 6.2-21 Plan View for the Steam Generator Subcompartment N/A N/A Elevation 28 feet 6 inches 6.2-22 FIGURE 6.2-22 Plan View for the Steam Generator Subcompartment N/A N/A Elevation 51 feet 4 inches 6.2-23 FIGURE 6.2-23 Upper Reactor Cavity Subcompartment Plan Elevation N/A N/A and Nodal Arrangement 6.2-24 FIGURE 6.2-24 Pressurizer Subcompartment Nodalization Diagram N/A N/A 6.2-25 FIGURE 6.2-25 Steam Generator Subcompartment Nodalization N/A N/A Diagram 6.2-26 FIGURE 6.2-26 Staggered Mesh Approximation for Nodes and Internal N/A N/A Junctions 6.2-27 FIGURE 6.2-27 General Flow Chart for THREED N/A N/A 6.2-28 FIGURE 6.2-28 Pressure Response Pressurizer Cubicle N/A N/A 6.2-28A FIGURE 6.2-28A Pressure Response Pressurizer Cubicle N/A N/A 6.2-29 FIGURE 6.2-29 Pressure Response Pressurizer Cubicle N/A N/A 6.2-29A FIGURE 6.2-29A Pressure Response Pressurizer Cubicle N/A N/A 6.2-29B FIGURE 6.2-29B Pressure Response Pressurizer Cubicle N/A N/A 6.2-29C FIGURE 6.2-29C Pressure Response Pressurizer Cubicle N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 6.2-29D FIGURE 6.2-29D Pressure Response Pressurizer Cubicle N/A N/A 6.2-30 FIGURE 6.2-30 Deleted by PKG FSC MP3-UCR-2009-006 N/A N/A 6.2-31 FIGURE 6.2-31 Pressure Response Steam Generator Cubicle N/A N/A 6.2-32 FIGURE 6.2-32 Pressure Response Steam Generator Cubicle N/A N/A 6.2-33 FIGURE 6.2-33 Deleted by PKG FSC MP3-UCR-2009-006 N/A N/A 6.2-34 FIGURE 6.2-34 Pressure Response Steam Generator Cubicle N/A N/A 6.2-34A FIGURE 6.2-34A Deleted by PKG FSC MP3-UCR-2009-006 N/A N/A 6.2-34B FIGURE 6.2-34B Deleted by PKG FSC MP3-UCR-2009-006 N/A N/A 6.2-34C FIGURE 6.2-34C Deleted by PKG FSC MP3-UCR-2009-006 N/A N/A 6.2-34D FIGURE 6.2-34D Deleted by PKG FSC MP3-UCR-2009-006 N/A N/A 6.2-35 FIGURE 6.2-35 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-36 FIGURE 6.2-36 P&ID Quench Spray and Hydrogen Recombiner N/A N/A 6.2-37 FIGURE 6.2-37 (Sheets 1-3) P&ID Low Pressure Safety Injection/

25212-26912 (a) SH 1 OF Containment Recirculation 6.2-37 FIGURE 6.2-37 (Sheets 1-3) P&ID Low Pressure Safety Injection/

25212-26912 (a) SH 2 OF Containment Recirculation 6.2-37 FIGURE 6.2-37 (Sheets 1-3) P&ID Low Pressure Safety Injection/

25212-26912 (a) SH 3 OF Containment Recirculation 6.2-38 FIGURE 6.2-38 Typical Containment Structure Sump N/A N/A 6.2-39 FIGURE 6.2-39 Spatial Droplet Size Distribution of Spraco 1713A Nozzle Applying Surface Area Correction and Spraying N/A N/A Water at 40 psig Under Laboratory Conditions 6.2-40 FIGURE 6.2-40 Containment Recirculation Pumps Characteristic Curves N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 6.2-41 FIGURE 6.2-41 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-42 FIGURE 6.2-42 Containment Recirculation Spray Coverage Bend Line (Elevation 104 feet), Elevated Temperature (275°F), N/A N/A Spray Header at Elevation 141 feet 9 inches 6.2-42 FIGURE 6.2-42 Containment Recirculation Spray Coverage Bend Line (Elevation 104 feet), Elevated Temperature (275°F), N/A N/A Spray Header at Elevation 141 feet 9 inches 6.2-44 FIGURE 6.2-44 Unobstructed Quench Spray Coverage at the Bend Line (Elevation 104 feet), Elevated Temperature (275°F), N/A N/A Spray Headers at Elevation 153 feet and 168 feet 6.2-45 FIGURE 6.2-45 Deleted by Change: PKG FSC 07-MP3-038 N/A N/A 6.2-46 FIGURE 6.2-46 Auxiliary Building Ventilation System and N/A N/A Supplementary Leak Collection & Release System 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 1 of 14) N/A 1 OF 1 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 2 of 14) N/A 2 OF 1 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 3 of 14) N/A 3 OF 1 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 4 of 14) N/A 4 OF 1 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 5 of 14) N/A 5 OF 1 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 6 of 14) N/A 6 OF 14 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 7 of 14) N/A 7 OF 14 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 8 of 14) N/A 8 OF 14 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 9 of 14) N/A 9 OF 14 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 10 of 14) N/A 10 OF 1 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 11 of 14) N/A 11 OF 1

Figure Number Figure Label Title Drawing Number Sheet 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 12 of 14) N/A 12 OF 1 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 13 of 14) N/A 13 OF 1 6.2-47 FIGURE 6.2-47 Containment Isolation System (Sheet 14 of 14) N/A 14 OF 1 6.2-48 FIGURE 6.2-48 Deleted by FSARCR 05-MP3-010 N/A N/A 6.2-49 FIGURE 6.2-49 Deleted by FSARCR 05-MP3-010 N/A N/A 6.2-50 FIGURE 6.2-50 Deleted by FSARCR 05-MP3-010 N/A N/A 6.2-51 FIGURE 6.2-51 Deleted by FSARCR 05-MP3-010 N/A N/A 6.2-52 FIGURE 6.2-52 Deleted by FSARCR 05-MP3-010 N/A N/A 6.2-53 FIGURE 6.2-53 P&ID Containment Monitoring System N/A N/A 6.2-54 FIGURE 6.2-54 Quench Spray Pumps Characteristic Curves N/A N/A 6.2-55 FIGURE 6.2-55 Deleted by FSARCR 05-MP3-010 N/A N/A 6.2-56 FIGURE 6.2-56 Containment Internal Structure Openings N/A N/A 6.2-57 FIGURE 6.2-57 Expected Long-Term Circulation Patterns in N/A N/A Containment 6.2-58 FIGURE 6.2-58 Containment Hydrogen Monitoring System N/A N/A 6.2-59 FIGURE 6.2-59 Containment Pressure Limiting Break N/A N/A 6.2-59A FIGURE 6.2-59A Deleted by FSARCR 02-MP3-017 N/A N/A 6.2-60 FIGURE 6.2-60 Condensing Wall Heat Transfer Coefficient Limiting N/A N/A Break 6.2-61 FIGURE 6.2-61 Deleted by PKG FSC 07-MP3-024 N/A N/A 6.2-62 FIGURE 6.2-62 Deleted by PKG FSC 07-MP3-024 N/A N/A 6.3-1 FIGURE 6.3-1 Safety Injection / Residual Heat Removal System N/A 1 OF 2 Process Flow Diagram (Sheet 1 of 2)

Figure Number Figure Label Title Drawing Number Sheet 6.3-1 FIGURE 6.3-1 Safety Injection / Residual Heat Removal System N/A 2 OF 2 Process Flow Diagram (Sheet 2 of 2) 6.3-1 FIGURE 6.3-1 Safety Injection / Residual Heat Removal System N/A N/A Process Flow Diagram (Sheet 2 of 2) 6.3-2 FIGURE 6.3-2 (Sheets 1-2)P&ID High Pressure Safety Injection 25212-26913 (a) SH 1 OF 6.3-2 FIGURE 6.3-2 (Sheets 1-2)P&ID High Pressure Safety Injection 25212-26913 (a) SH 2 OF 6.3-3 FIGURE 6.3-3 Residual Heat Removal Pump Performance Curve N/A N/A 6.3-4 FIGURE 6.3-4 Charging Pump Curve Assumed for Safety Analysis N/A N/A 6.3-5 FIGURE 6.3-5 High Head SI Pump Curve Assumed for Safety Analysis N/A N/A 6.3-6 FIGURE 6.3-6 Refueling Water Storage Tank Water Levels N/A N/A 6.4-1 FIGURE 6.4-1 Control Room Area N/A N/A 6.4-2 FIGURE 6.4-2 Control Room Intake and Hazardous Material Storage N/A N/A Locations 6.5-1 FIGURE 6.5-1 Post DBA Minimum Containment Sump pH N/A N/A 7.1-1 FIGURE 7.1-1 Solid State Protection System Block Diagram N/A N/A 7.1-2 FIGURE 7.1-2 Reactor Trip/ESF Actuation Mechanical Linkage for N/A N/A Dual Train Switches 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH400 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH400 Relief System

Figure Number Figure Label Title Drawing Number Sheet 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH400 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH400 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH400 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH400 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH400 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH400 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH4011 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System

Figure Number Figure Label Title Drawing Number Sheet 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH402 Relief System 7.2-1 FIGURE 7.2-1 (Sheets 1-19) P&IDs Functional Diagram, Reactor Trip System/Loop Stop Valve Interlocks/Pressurizer Pressure 25212-39001 (a) SH401 Relief System

\7.2-2 FIGURE 7.2-2 Setpoint Reduction Function for Overpower and Over-N/A N/A temperature T Trips

Figure Number Figure Label Title Drawing Number Sheet

\7.3-1 FIGURE 7.3-1 Failure Modes and Effects Analysis Quench Spray N/A N/A System

\7.3-2 FIGURE 7.3-2 Fault Tree Diagram Quench Spray System N/A N/A

\7.3-3 FIGURE 7.3-3 Typical ESF Test Circuits N/A N/A

\7.3-4 FIGURE 7.3-4 Engineered Safeguards Test Cabinet N/A N/A 7.6-1 FIGURE 7.6-1 Logic Diagram for RHS Isolation Valves N/A N/A 7.6-1 FIGURE 7.6-1 Logic Diagram for RHS Isolation Valves N/A N/A 7.6-2 FIGURE 7.6-2 Functional Block Diagram of Accumulator Isolation N/A N/A Valves 7.6-3 FIGURE 7.6-3 Automatic RHS and QSS Pump Shutoff (Sheet 1) N/A 1 OF 2 7.6-3 FIGURE 7.6-3 Automatic RHS and QSS Pump Shutoff (Sheet 2) N/A 2 OF 2 7.6-4 FIGURE 7.6-4 Reactor Coolant System Loop with Loop Stop Valves N/A N/A 7.7-1 FIGURE 7.7-1 Simplified Block Diagram of Reactor Control System N/A N/A 7.7-2 FIGURE 7.7-2 Control Bank Rod Insertion Monitor N/A N/A 7.7-3 FIGURE 7.7-3 Rod Deviation Comparator N/A N/A 7.7-4 FIGURE 7.7-4 Block Diagram of Pressurizer Pressure Control System N/A N/A 7.7-5 FIGURE 7.7-5 Block Diagram of Pressurizer Level Control System N/A N/A 7.7-6 FIGURE 7.7-6 Block Diagram of Steam Generator Water Level Control N/A N/A System 7.7-7 FIGURE 7.7-7 Block Diagram of Main Feedwater Pump Speed Control N/A N/A System 7.7-8 FIGURE 7.7-8 Block Diagram of Steam Dump Control System N/A N/A 7.7-9 FIGURE 7.7-9 Basic Flux-Mapping System N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 7.7-10 FIGURE 7.7-10 Not Used N/A N/A 7.7-11 FIGURE 7.7-11 Not Used N/A N/A 7.7-12 FIGURE 7.7-12 Not Used N/A N/A 7.7-13 FIGURE 7.7-13 Not Used N/A N/A 7.7-14 FIGURE 7.7-14 Simplified Block Diagram of Rod Control System N/A N/A 7.7-15 FIGURE 7.7-15 Control Bank B Partial Simplified Schematic Diagram N/A N/A of Power Cabinets 1 BD and 2 BD 7.8-1 FIGURE 7.8-1 Actuation Logic System Architecture N/A N/A 8.1-1 FIGURE 8.1-1 Electrical One Line Diagram N/A N/A 8.1-2 FIGURE 8.1-2 345 kV Transmission Map of Connecticut and Western N/A N/A Massachusetts 8.1-3 FIGURE 8.1-3 345 kV Switchyard N/A N/A 8.2-1 FIGURE 8.2-1 Deleted by FSARCR MP3-UCR-2016-014 N/A N/A 8.2-2 FIGURE 8.2-2 Hunts Brook Junction N/A N/A 8.2-2 FIGURE 8.2-2 Hunts Brook Junction N/A N/A 8.3-1 FIGURE 8.3-1 Routing of Redundant Circuits (Sheet 1 of 4) N/A 1 OF 4 8.3-1 FIGURE 8.3-1 Routing of Redundant Circuits (Sheet 2 of 4) N/A 2 OF 4 8.3-1 FIGURE 8.3-1 Routing of Redundant Circuits (Sheet 3 of 4) N/A 3 OF 4 8.3-1 FIGURE 8.3-1 Routing of Redundant Circuits (Sheet 1 of 4) N/A 4 OF 4 8.3-2 FIGURE 8.3-2 One Line Diagram 125VDC and 120VAC Distribution 25212-30076 (a) N/A System - Composite 8.3-3 FIGURE 8.3-3 120V AC Vital Bus and Safety Related 125V DC N/A N/A Systems

Figure Number Figure Label Title Drawing Number Sheet 8.3-4 FIGURE 8.3-4 Power Supply - Third Charging Pump N/A N/A 8.3-5 FIGURE 8.3-5 Power Supply - Third Reactor Plant Component Cooling N/A N/A Pump 8.3-6 FIGURE 8.3-6 Emergency Generator Fuel Oil Transfer Pumps N/A N/A 8.3-7 FIGURE 8.3-7 Routing of Preferred Offsite and Standby Onsite Circuits N/A N/A 8.3-8 FIGURE 8.3-8 Not Used N/A N/A 8.3-9 FIGURE 8.3-9 6.9 kV and 4160 Volt Systems N/A N/A 8.3-10 FIGURE 8.3-10 (Sheets 1-5) Emergency Generator Load Information 25212-39241 (a) SH 189 8.3-10 FIGURE 8.3-10 (Sheets 1-5) Emergency Generator Load Information 25212-39241 (a) SH 190 8.3-10 FIGURE 8.3-10 (Sheets 1-5) Emergency Generator Load Information 25212-39241 (a) SH 191 8.3-10 FIGURE 8.3-10 (Sheets 1-5) Emergency Generator Load Information 25212-39241 (a) SH 192 8.3-10 FIGURE 8.3-10 (Sheets 1-5) Emergency Generator Load Information 25212-39241 (a) SH 193 9.1-1 FIGURE 9.1-1 Pictorial View of Typical Region 3 Rack Module N/A N/A 9.1-2 FIGURE 9.1-2 Top View of 6x6 Rack Array (Region 3) N/A N/A 9.1-2A FIGURE 9.1-2A Deleted by PKG FSC 98-MP3-116 N/A N/A 9.1-3 FIGURE 9.1-3 Side View of 6x6 Rack Array (Region 3) N/A N/A 9.1-4 FIGURE 9.1-4 Not Used N/A N/A 9.1-5 FIGURE 9.1-5 Adjustable Fuel Rack Leveling Pad (Region 3) N/A N/A 9.1-6 FIGURE 9.1-6 P&ID Fuel Pool Cooling and Purification System N/A N/A 9.1-7 FIGURE 9.1-7 Bulk Pool Transient Temperature Plot (Full Core N/A N/A Offload)

Figure Number Figure Label Title Drawing Number Sheet 9.1-7A FIGURE 9.1-7A Bulk Pool Transient Temperature Plot (Emergency Core N/A N/A Offload) 9.1-8 FIGURE 9.1-8 Cooldown Curve for Normal Operation (4 Hours Loss of N/A N/A Pool Cooling) 9.1-9 FIGURE 9.1-9 Refueling Machine N/A N/A 9.1-10 FIGURE 9.1-10 Spent Fuel Bridge and Hoisting Structure N/A N/A 9.1-11 FIGURE 9.1-11 New Fuel Elevator N/A N/A 9.1-12 FIGURE 9.1-12 Fuel Transfer System N/A N/A 9.1-13 FIGURE 9.1-13 DELETED BY PKG FSC 00-MP3-045 N/A N/A 9.1-14 FIGURE 9.1-14 Spent Fuel Handling Tool N/A N/A 9.1-15 FIGURE 9.1-15 New Fuel Handling Tool N/A N/A 9.1-16 FIGURE 9.1-16 Reactor Internals Lifting Device N/A N/A 9.1-17 FIGURE 9.1-17 Quick Acting Stud Tensioner (sheet 1) N/A N/A 9.1-18 FIGURE 9.1-18 New Fuel Vault Layout N/A N/A 9.1-19 FIGURE 9.1-19 New Fuel Vault Elevation View N/A N/A 9.1-20 FIGURE 9.1-20 Fuel Assembly Transfer Limit Verses CCP Temperature N/A N/A 9.1-21 FIGURE 9.1-21 Millstone Unit 3 Spent Fuel Pool Layout N/A N/A 9.1-22 FIGURE 9.1-22 Region 1 Fuel Storage Loading Schematic N/A N/A 9.1-22A FIGURE 9.1-22A Pictorial View of Typical Region 1 Rack Module N/A N/A 9.1-22B FIGURE 9.1-22B Typical Assemblage of Region 1 Cells N/A N/A 9.1-22C FIGURE 9.1-22C Elevation View of Region 1 Rack Module N/A N/A 9.1-23 FIGURE 9.1-23 Not Used N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 9.1-23A FIGURE 9.1-23A Pictorial View of Typical Region 2 Rack Module N/A N/A 9.1-23B FIGURE 9.1-23B Typical Array of Region 2 Cells N/A N/A 9.1-23C FIGURE 9.1-23C Elevation View of Region 2 Rack Module N/A N/A 9.1-24 FIGURE 9.1-24 Support Pedestal for Region 1 and Region 2 Rack N/A N/A Modules 9.2-1 FIGURE 9.2-1 (Sheets 1-4) P&ID Service Water 25212-26933 (a) SH 1 9.2-1 FIGURE 9.2-1 (Sheets 1-4) P&ID Service Water 25212-26933 (a) SH 2 9.2-1 FIGURE 9.2-1 (Sheets 1-4) P&ID Service Water 25212-26933 (a) SH 3 9.2-1 FIGURE 9.2-1 (Sheets 1-4) P&ID Service Water 25212-26933 (a) SH 4 9.2-2 FIGURE 9.2-2 (Sheets 1-3) P&ID Reactor Plant Component Cooling 25212-26921 (a) SH 1 System 9.2-2 FIGURE 9.2-2 (Sheets 1-3) P&ID Reactor Plant Component Cooling 25212-26921 (a) SH 2 System 9.2-2 FIGURE 9.2-2 (Sheets 1-3) P&ID Reactor Plant Component Cooling 25212-26921 (a) SH 3 System 9.2-3 FIGURE 9.2-3 (Sheets 1-2) P&ID Reactor Plant Chilled Water System 25212-26922 (a) SH 1 9.2-3 FIGURE 9.2-3 (Sheets 1-2) P&ID Reactor Plant Chilled Water System 25212-26922 (a) SH 2 9.2-4 FIGURE 9.2-4 P&ID Safety Injection Pump and Neutron Shield Tank 25212-26914 (a) SH 1 Cooling Systems 9.2-5 FIGURE 9.2-5 P&ID Charging Pump Sealing and Lubrication 25212-26905 (a) 1 OF 1 9.2-6 FIGURE 9.2-6 P&ID Condensate Demineralizer Liquid Waste 25212-26929 (a) N/A 9.2-7 FIGURE 9.2-7 (Sheets 1-6) P&ID Water Treatment System 25212-26920 (a) SH 1 0F

Figure Number Figure Label Title Drawing Number Sheet 9.2-7 FIGURE 9.2-7 (Sheets 1-6) P&ID Water Treatment System 25212-26920 (a) SH 2 0F 9.2-7(2)(A) FIGURE 9.2-7(2)(A) (Sheets 1-6) P&ID Water Treatment System FSAR Figure (a) N/A (TEMPMOD) 9.2-7 SH. 2(A) 9.2-7(2)(A) FIGURE 9.2-7(2)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7(2)(A) FIGURE 9.2-7(2)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7(2)(A) FIGURE 9.2-7(2)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7(2)(A) FIGURE 9.2-7(2)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7(2)(A) FIGURE 9.2-7(2)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7 FIGURE 9.2-7 (Sheets 1-6) P&ID Water Treatment System 25212-26920 (a) SH 3 OF 9.2-7 FIGURE 9.2-7 (Sheets 1-6) P&ID Water Treatment System 25212-26920 (a) SH 4 OF 9.2-7 FIGURE 9.2-7 (Sheets 1-6) P&ID Water Treatment System 25212-26920 (a) SH 5 OF 9.2-7(5)(A) FIGURE 9.2-7(5)(A) (Sheets 1-6) P&ID Water Treatment System FSAR Figure(a) N/A (TEMPMOD) 9.2-7 SH. 5(A) 9.2-7(5)(A) FIGURE 9.2-7(5)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7(5)(A) FIGURE 9.2-7(5)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7(5)(A) FIGURE 9.2-7(5)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD)

Figure Number Figure Label Title Drawing Number Sheet 9.2-7(5)(A) FIGURE 9.2-7(5)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7(5)(A) FIGURE 9.2-7(5)(A) (Sheets 1-6) P&ID Water Treatment System N/A N/A (TEMPMOD) 9.2-7 FIGURE 9.2-7 (Sheets 1-6) P&ID Water Treatment System 25212-26920 (a) SH 6 OF 9.2-8 FIGURE 9.2-8 (Sheets 1-3) P&ID Domestic Water and Sanitary 25212-26947 (a) SH 1 OF Systems 9.2-8 FIGURE 9.2-8 (Sheets 1-3) P&ID Domestic Water and Sanitary 25212-26947 (a) SH 2 OF Systems 9.2-8 FIGURE 9.2-8 (Sheets 1-3) P&ID Domestic Water and Sanitary 25212-26947 (a) SH 3 OF Systems 9.2-9 FIGURE 9.2-9 (Sheets 1-3) P&ID Condensate System 25212-26926 (a) SH 1 OF 9.2-9 FIGURE 9.2-9 (Sheets 1-3) P&ID Condensate System 25212-26926 (a) SH 2 OF 9.2-9 FIGURE 9.2-9 (Sheets 1-3) P&ID Condensate System 25212-26926 (a) SH 3 OF 9.2-10 FIGURE 9.2-10 (Sheets 1-2) P&ID Turbine Plant Component Cooling 25212-26934 (a) SH 1 OF Water 9.2-10 FIGURE 9.2-10 (Sheets 1-2) P&ID Turbine Plant Component Cooling 25212-26934 (a) SH 2 OF Water 9.2-11 FIGURE 9.2-11 P&ID Primary Grade Water System 25212-26919 (a) SH 1 OF 9.3-1 FIGURE 9.3-1 (Sheets 1-4)P&ID Compressed Air System 25212-26938 (a) SH 1 OF 9.3-1 FIGURE 9.3-1 (Sheets 1-4)P&ID Compressed Air System 25212-26938 (a) SH 2 OF 9.3-1 FIGURE 9.3-1 (Sheets 1-4)P&ID Compressed Air System 25212-26938 (a) SH 3 OF 9.3-1 FIGURE 9.3-1 (Sheets 1-4)P&ID Compressed Air System 25212-26938 (a) SH 4 OF

Figure Number Figure Label Title Drawing Number Sheet 9.3-2 FIGURE 9.3-2 (Sheets 1-4) P&ID Reactor Plant Sampling System 25212-26944 (a) SH 1 OF 9.3-2 FIGURE 9.3-2 (Sheets 1-4) P&ID Reactor Plant Sampling System 25212-26944 (a) SH 2 OF 9.3-2 FIGURE 9.3-2 (Sheets 1-4) P&ID Reactor Plant Sampling System 25212-26944 (a) SH 3 OF 9.3-2 FIGURE 9.3-2 (Sheets 1-4) P&ID Reactor Plant Sampling System 25212-26944 (a) SH 4 OF 9.3-3 FIGURE 9.3-3 (Sheets 1-2) P&ID Turbine Plant Sampling 25212-26943 (a) SH 1 OF 9.3-3 FIGURE 9.3-3 (Sheets 1-2) P&ID Turbine Plant Sampling 25212-26943 (a) SH 2 OF 9.3-4 FIGURE 9.3-4 (Sheets 1-2) P&ID Radioactive Gaseous Waste System 25212-26909 (a) SH 1 9.3-4 FIGURE 9.3-4 (Sheets 1-2) P&ID Radioactive Gaseous Waste System 25212-26909 (a) SH 2 9.3-5 FIGURE 9.3-5 P&ID Reactor Plant Gaseous Drains 25212-26907 (a) N/A 9.3-6 FIGURE 9.3-6 (Sheets 1-3) P&ID Radioactive Liquid Waste and 25212-26906 (a) SH 1 OF Aerated Drain 9.3-6 FIGURE 9.3-6 (Sheets 1-3) P&ID Radioactive Liquid Waste and 25212-26906 (a) SH 2 OF Aerated Drain 9.3-6 FIGURE 9.3-6 (Sheets 1-3) P&ID Radioactive Liquid Waste and 25212-26906 (a) SH 3 OF Aerated Drain 9.3-7 FIGURE 9.3-7 P&ID Reactor Coolant Pump Seals (Sheet 1) 25212-26903 (a) N/A 9.3-7(1)(A) FIGURE 9.3-7(1)(A) Reactor Coolant Pump Seals (TEMP/MOD) FSAR Figure (a) N/A 9.3-7 SH. 1(A) 9.3-8 FIGURE 9.3-8 (Sheets 1-4) P&ID Chemical and Volume Control 25212-26904 (a) SH 1 OF 9.3-8 FIGURE 9.3-8 (Sheets 1-4) P&ID Chemical and Volume Control 25212-26904 (a) SH 2 OF 9.3-8 FIGURE 9.3-8 (Sheets 1-4) P&ID Chemical and Volume Control 25212-26904 (a) SH 3 OF

Figure Number Figure Label Title Drawing Number Sheet 9.3-8 FIGURE 9.3-8 (Sheets 1-4) P&ID Chemical and Volume Control 25212-26904 (a) SH 4 OF 9.3-9 FIGURE 9.3-9 (Sheets 1-3) P&ID Boron Recovery System 25212-26908 (a) SH 1 OF 9.3-9 FIGURE 9.3-9 (Sheets 1-3) P&ID Boron Recovery System 25212-26908 (a) SH 2 OF 9.3-9(2)(A) FIGURE 9.3-9(2)(A) Boron Recovery System (TEMP/MOD) FSAR Figure(a) N/A 9.3-9 SH. 2(A) 9.3-9 FIGURE 9.3-9 (Sheets 1-3) P&ID Boron Recovery System 25212-26908 (a) SH 3 OF 9.3-10 FIGURE 9.3-10 (Sheets 1-3)P&ID Post Accident Sample System 25212-26955 (a) SH 1 OF 9.3-10 FIGURE 9.3-10 (Sheets 1-3)P&ID Post Accident Sample System 25212-26955 (a) SH 2 OF 9.3-10 FIGURE 9.3-10 (Sheets 1-3)P&ID Post Accident Sample System 25212-26955 (a) SH 3 OF 9.4-1 FIGURE 9.4-1 (Sheets 1-5) P&ID Control Building Heating, 25212-26951 (a) SH 1 OF Ventilation and Air Conditioning 9.4-1 FIGURE 9.4-1 (Sheets 1-5) P&ID Control Building Heating, 25212-26951 (a) SH 2 OF Ventilation and Air Conditioning 9.4-1 FIGURE 9.4-1 (Sheets 1-5) P&ID Control Building Heating, 25212-26951 (a) SH 3 OF Ventilation and Air Conditioning 9.4-1 FIGURE 9.4-1 (Sheets 1-5) P&ID Control Building Heating, 25212-26951 (a) SH 4 OF Ventilation and Air Conditioning 9.4-1 FIGURE 9.4-1 (Sheets 1-5) P&ID Control Building Heating, 25212-26951 (a) SH 5 OF Ventilation and Air Conditioning 9.4-2 FIGURE 9.4-2 (Sheets 1-6) P&ID Reactor Plant Ventilation 25212-26948 (a) SH 1 OF 9.4-2 FIGURE 9.4-2 (Sheets 1-6) P&ID Reactor Plant Ventilation 25212-26948 (a) SH 2 OF 9.4-2 FIGURE 9.4-2 (Sheets 1-6) P&ID Reactor Plant Ventilation 25212-26948 (a) SH 3 OF

Figure Number Figure Label Title Drawing Number Sheet 9.4-2 FIGURE 9.4-2 (Sheets 1-6) P&ID Reactor Plant Ventilation 25212-26948 (a) SH 4 OF 9.4-2 FIGURE 9.4-2 (Sheets 1-6) P&ID Reactor Plant Ventilation 25212-26948 (a) SH 5 OF 9.4-2 FIGURE 9.4-2 (Sheets 1-6) P&ID Reactor Plant Ventilation 25212-26948 (a) SH 6 OF 9.4-3 FIGURE 9.4-3 (Sheets 1-5) P&IDs Turbine Plant Ventilation & ISO 25212-26950 (a) SH 1 OF Bus Duct Cooling Systems 9.4-3 FIGURE 9.4-3 (Sheets 1-5) P&IDs Turbine Plant Ventilation & ISO 25212-26950 (a) SH 2 OF Bus Duct Cooling Systems 9.4-3 FIGURE 9.4-3 (Sheets 1-5) P&IDs Turbine Plant Ventilation & ISO 25212-26950 (a) SH 3 OF Bus Duct Cooling Systems 9.4-3 FIGURE 9.4-3 (Sheets 1-5) P&IDs Turbine Plant Ventilation & ISO 25212-26950 (a) SH 4 OF Bus Duct Cooling Systems 9.4-3 FIGURE 9.4-3 (Sheets 1-5) P&IDs Turbine Plant Ventilation & ISO 25212-26950 (a) SH 5 OF Bus Duct Cooling Systems 9.4-4 FIGURE 9.4-4 (Sheets 1-3) P&ID ESF and MSV Buildings Ventilation 25212-26952 (a) SH 1 OF 9.4-4 FIGURE 9.4-4 (Sheets 1-3) P&ID ESF and MSV Buildings Ventilation 25212-26952 (a) SH 2 OF 9.4-4 FIGURE 9.4-4 (Sheets 1-3) P&ID ESF and MSV Buildings Ventilation 25212-26952 (a) SH 3 OF 9.4-5 FIGURE 9.4-5 P&ID Containment Structure Ventilation 25212-26953 (a) SH 1 OF 9.4-6 FIGURE 9.4-6 (Sheets 1-3) P&ID Service Building Ventilation 25212-26949 (a) SH 1 OF 9.4-6 FIGURE 9.4-6 (Sheets 1-3) P&ID Service Building Ventilation 25212-26949 (a) SH 2 OF 9.4-6 FIGURE 9.4-6 (Sheets 1-3) P&ID Service Building Ventilation 25212-26949 (a) SH 3 OF 9.4-7 FIGURE 9.4-7 (Sheets 1-2) P&ID Auxiliary Boiler and Ventilation 25212-26936 (a) SH 1 OF

Figure Number Figure Label Title Drawing Number Sheet 9.4-7 FIGURE 9.4-7 (Sheets 1-2) P&ID Auxiliary Boiler and Ventilation 25212-26936 (a) SH 2 OF 9.4-8 FIGURE 9.4-8 (Sheets 1-3) P&ID Hot Water Heating System 25212-26937 (a) SH 1 OF 9.4-8 FIGURE 9.4-8 (Sheets 1-3) P&ID Hot Water Heating System 25212-26937 (a) SH 2 OF 9.4-8 FIGURE 9.4-8 (Sheets 1-3) P&ID Hot Water Heating System 25212-26937 (a) SH 3 OF 9.4-9 FIGURE 9.4-9 P&ID Technical Support Center, Heating, Ventilation 25212-26956 (a) SH 1 OF and Air Conditioning 9.5-1 FIGURE 9.5-1 Fire Protection System (Now in FPER Figure 4-1) N/A N/A 9.5-2 FIGURE 9.5-2 P&ID Emergency Generator Fuel Oil System 25212-26917 (a) SH 1 OF 9.5-3 FIGURE 9.5-3 P&ID Emergency Diesel Related Systems (Sheets 1-5) 25212-26916 (a) SH 1 OF 9.5-3 FIGURE 9.5-3 P&ID Emergency Diesel Related Systems (Sheets 1-5) 25212-26916 (a) SH 2 OF 9.5-3 FIGURE 9.5-3 P&ID Emergency Diesel Related Systems (Sheets 1-5) 25212-26916 (a) SH 3 OF 9.5-3 FIGURE 9.5-3 P&ID Emergency Diesel Related Systems (Sheets 1-5) 25212-26916 (a) SH 4 OF 9.5-3 FIGURE 9.5-3 P&ID Emergency Diesel Related Systems (Sheets 1-5) 25212-26916 (a) SH 5 OF 9.5-4 FIGURE 9.5-4 Fire Protection System (Now in FPER Figure 4-1) N/A N/A 9.5-5 FIGURE 9.5-5 P&ID Nitrogen and Hydrogen System (Sheets 1-3) 25212-26939 (a) SH 1 OF 9.5-5 FIGURE 9.5-5 P&ID Nitrogen and Hydrogen System (Sheets 1-3) 25212-26939 (a) SH 2 OF 9.5-5 FIGURE 9.5-5 P&ID Nitrogen and Hydrogen System (Sheets 1-3) 25212-26939 (a) SH 3 OF 9.5-6 FIGURE 9.5-6 Not Used N/A N/A 9.5-7 FIGURE 9.5-7 Site Water Fire Protection N/A N/A 10.1-1 FIGURE 10.1-1 Fundamental Diagram N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 10.1-2 FIGURE 10.1-2 Rated Heat Balance 25212-23050 (a) SH 9 10.1-3 FIGURE 10.1-3 Deleted by PKG FSC 03-MP3-027 N/A N/A 10.2-1 FIGURE 10.2-1 P&ID Electro-Hydraulic Control 25212-26940 (a) N/A 10.2-2 FIGURE 10.2-2 (Sheets 1-3) P&ID Turbine Generator and Feed Pump 25212-26941 (a) SH 1 OF Oil Systems 10.2-2 FIGURE 10.2-2 (Sheets 1-3) P&ID Turbine Generator and Feed Pump 25212-26941 (a) SH 2 OF Oil Systems 10.2-2 FIGURE 10.2-2 (Sheets 1-3) P&ID Turbine Generator and Feed Pump 25212-26941 (a) SH 3 OF Oil Systems 10.2-3 FIGURE 10.2-3 P&ID Turbine Generator Support Systems 25212-26942 (a) SH 1 OF 10.3-1 FIGURE 10.3-1 (Sheets 1-6) P&ID Main Steam and Reheat 25212-26923 (a) SH 1 OF 10.3-1 FIGURE 10.3-1 (Sheets 1-6) P&ID Main Steam and Reheat 25212-26923 (a) SH 2 OF 10.3-1 FIGURE 10.3-1 (Sheets 1-6) P&ID Main Steam and Reheat 25212-26923 (a) SH 3 OF 10.3-1 FIGURE 10.3-1 (Sheets 1-6) P&ID Main Steam and Reheat 25212-26923 (a) SH 4 OF 10.3-1 FIGURE 10.3-1 (Sheets 1-6) P&ID Main Steam and Reheat 25212-26923 (a) SH 5 OF 10.3-1 FIGURE 10.3-1 (Sheets 1-6) P&ID Main Steam and Reheat 25212-26923 (a) SH 6 OF 10.3-2 FIGURE 10.3-2 (Sheets 1-3) P&ID Turbine Plant Miscellaneous Drains 25212-26945 (a) SH 1 OF 10.3-2 FIGURE 10.3-2 (Sheets 1-3) P&ID Turbine Plant Miscellaneous Drains 25212-26945 (a) SH 2 OF 10.3-2 FIGURE 10.3-2 (Sheets 1-3) P&ID Turbine Plant Miscellaneous Drains 25212-26945 (a) SH 3 OF 10.3-3 FIGURE 10.3-3 P&ID Chemical Feed 25212-26931 (a) SH 1 OF 10.3-3(1)(A) FIGURE 10.3-3(1)(A) Deleted by PKG FSC 98-MP3-126 N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 10.3-4 FIGURE 10.3-4 Main Steam Isolation Valve N/A N/A 10.4-1 FIGURE 10.4-1 (Sheets 1-3) P&ID Condensate System 25212-26926 (a) SH 1 OF 10.4-1 FIGURE 10.4-1 (Sheets 1-3) P&ID Condensate System 25212-26926 (a) SH 2 OF 10.4-1 FIGURE 10.4-1 (Sheets 1-3) P&ID Condensate System 25212-26926 (a) SH 3 OF 10.4-2 FIGURE 10.4-2 (Sheets 1-2) P&ID Condenser Air Removal System and 25212-26927 (a) SH 1 0F Waterbox Priming 10.4-2 FIGURE 10.4-2 (Sheets 1-2) P&ID Condenser Air Removal System and 25212-26927 (a) SH 2 OF Waterbox Priming 10.4-3 FIGURE 10.4-3 P&ID Extraction Steam and Turbine Generator Gland 25212-26924 (a) SH 1 OF Seal and Exhaust (Sheets 1-2) 10.4-3 FIGURE 10.4-3 P&ID Extraction Steam and Turbine Generator Gland 25212-26924 (a) SH 2 OF Seal and Exhaust (Sheets 1-2) 10.4-4 FIGURE 10.4-4 P&ID Circulating Water System (Sheets 1-2) 25212-26932 (a) SH 1 OF 10.4-4 FIGURE 10.4-4 P&ID Circulating Water System (Sheets 1-2) 25212-26932 (a) SH 2 OF 10.4-5 FIGURE 10.4-5 P&ID Condensate Demineralizer - Mixed Bed 25212-26928 (a) SH 1 OF (Sheets 1-5) 10.4-5 FIGURE 10.4-5 P&ID Condensate Demineralizer - Mixed Bed 25212-26928 (a) SH 2 OF (Sheets 1-5) 10.4-5 FIGURE 10.4-5 P&ID Condensate Demineralizer - Mixed Bed 25212-26928 (a) SH 3 OF (Sheets 1-5) 10.4-5 FIGURE 10.4-5 P&ID Condensate Demineralizer - Mixed Bed 25212-26928 (a) SH 4 OF (Sheets 1-5) 10.4-5 FIGURE 10.4-5 P&ID Condensate Demineralizer - Mixed Bed 25212-26928 (a) SH 5 OF (Sheets 1-5)

Figure Number Figure Label Title Drawing Number Sheet 10.4-6 FIGURE 10.4-6 P&ID Feedwater System (Sheets 1-4) 25212-26930 (a) SH 1 OF 10.4-6 FIGURE 10.4-6 P&ID Feedwater System (Sheets 1-4) 25212-26930 (a) SH 2 OF 10.4-6 FIGURE 10.4-6 P&ID Feedwater System (Sheets 1-4) 25212-26930 (a) SH 3 OF 10.4-6 FIGURE 10.4-6 P&ID Feedwater System (Sheets 1-4) 25212-26930 (a) SH 4 OF 10.4-7 FIGURE 10.4-7 P&ID Feedwater Heater and Main Steam Reheat Vents 25212-26925 (a) SH 1 OF and Drains (Sheets 1-3) 10.4-7 FIGURE 10.4-7 P&ID Feedwater Heater and Main Steam Reheat Vents 25212-26925 (a) SH 2 OF and Drains (Sheets 1-3) 10.4-7 FIGURE 10.4-7 P&ID Feedwater Heater and Main Steam Reheat Vents 25212-26925 (a) SH 3 OF and Drains (Sheets 1-3) 10.4-8 FIGURE 10.4-8 Not Used N/A N/A 10.4-9 FIGURE 10.4-9 P&ID Auxiliary Steam, Feedwater and Condensate 25212-26935 (a) SH 1 OF (Sheets 1-3) 10.4-9(1)(A) FIGURE 10.4-9(1)(A) Auxiliary Steam, Feedwater and Condensate (TEMP/

25212-26935 (a) SH 1 OF MOD 3-97-061) 10.4-9 FIGURE 10.4-9 P&ID Auxiliary Steam, Feedwater and Condensate 25212-26935 (a) SH 2 OF (Sheets 1-3) 10.4-9 FIGURE 10.4-9 P&ID Auxiliary Steam, Feedwater and Condensate 25212-26935 (a) SH 3 OF (Sheets 1-3) 10.4-10 FIGURE 10.4-10 Minimum Auxiliary Feedwater Flow to Four Steam N/A N/A Generators, Loss of Normal Feedwater Event 10.4-11 FIGURE 10.4-11 Minimum AFW Flow to Three Effective Steam N/A N/A Generators, Feedwater Line Break Event

Figure Number Figure Label Title Drawing Number Sheet 10.4-12 FIGURE 10.4-12 Minimum Auxiliary Feedwater Flow to Two Steam Generators, Better Estimate Loss of Normal Feedwater N/A N/A Event for Reliability Analysis 11.2-1 FIGURE 11.2-1 P&ID Radioactive Liquid Waste and Aerated Drains 25212-26906 (a) SH 1 OF (Sheets 1-3) 11.2-1 FIGURE 11.2-1 P&ID Radioactive Liquid Waste and Aerated Drains 25212-26906 (a) SH 2 OF (Sheets 1-3) 11.2-1 FIGURE 11.2-1 P&ID Radioactive Liquid Waste and Aerated Drains 25212-26906 (a) SH 3 OF (Sheets 1-3) 11.2-2 FIGURE 11.2-2 Condensate Demineralizer Liquid Waste 25212-26929 (a) N/A 11.2-3 FIGURE 11.2-3 Expected Radioactive Liquid Waste Source and N/A N/A Discharge Paths 11.3-1 FIGURE 11.3-1 P&ID Radioactive Gaseous Waste System (Sheets 1-2) 25212-26909 (a) SH 1 OF 11.3-1 FIGURE 11.3-1 P&ID Radioactive Gaseous Waste System (Sheets 1-2) 25212-26909 (a) SH 2 OF 11.3-2 FIGURE 11.3-2 Ventilation System Composite Drawing Normal N/A N/A Operation 11.4-1 FIGURE 11.4-1 P&ID Radioactive Solid Waste (Sheets 1-2) 25212-26910 (a) SH 1 OF 11.4-1 FIGURE 11.4-1 P&ID Radioactive Solid Waste (Sheets 1-2) 25212-26910 (a) SH 2 OF 11.4-2 FIGURE 11.4-2 (Historical) Radioactive Solid Waste System Expected N/A N/A Quantities 11.4-3 FIGURE 11.4-3 (Historical) Radioactive Solid Waste System Design N/A N/A Quantities 12.2-1 FIGURE 12.2-1 Arrangement - Operating Personnel Access and Egress N/A N/A 12.2-2 FIGURE 12.2-2 Arrangement - Operating Personnel Access and Egress N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 12.2-3 FIGURE 12.2-3 Arrangement - Operating Personnel Access and Egress N/A N/A 12.2-4 FIGURE 12.2-4 I131 Concentration Containment N/A N/A 12.3-1 FIGURE 12.3-1 Design Basis Radiation Zones for Shielding (Normal N/A N/A Operations) 12.3-2 FIGURE 12.3-2 Design Basis Radiation Zones for Shielding (Normal N/A N/A Operations) 12.3-3 FIGURE 12.3-3 Design Basis Radiation Zones for Shielding (Normal N/A N/A Operations) 12.3-4 FIGURE 12.3-4 Design Basis Radiation Zones for Shielding (Normal N/A N/A Operations) 12.3-5 FIGURE 12.3-5 This figure moved to Section 11.5 (Figure 11.5-2) N/A N/A 12.3-6 FIGURE 12.3-6 Design Basis Radiation Zones for Shielding (Shutdown/

N/A N/A Refueling) 12.3-7 FIGURE 12.3-7 Design Basis Radiation Zones for Shielding (Shutdown/

N/A N/A Refueling) 12.3-8 FIGURE 12.3-8 Design Basis Radiation Zones for Shielding (Shutdown/

N/A N/A Refueling) 12.3-9 FIGURE 12.3-9 Design Basis Radiation Zones for Shielding (Shutdown/

N/A N/A Refueling) 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 1) N/A SH 1 OF 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 2) N/A SH 2 OF 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 3) N/A SH 3 OF 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 4) N/A SH 4 OF 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 5) N/A SH 5 OF

Figure Number Figure Label Title Drawing Number Sheet 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 6) N/A SH 6 OF 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 7) N/A SH 7 OF 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 8) N/A SH 8 OF 12.3-10 FIGURE 12.3-10 Routes to Post-Accident Vital Areas (Sheet 9) N/A SH 9 OF 12.3-11 FIGURE 12.3-11 Fuel Transfer Tube Shielding N/A N/A 12.3-12 FIGURE 12.3-12 Upper Reactor Cavity Neutron Shield N/A N/A 12.5-1 FIGURE 12.5-1 Figure has been deleted N/A N/A 13.1-1 FIGURE 13.1-1 Deleted by PKG FSC 01-MP3-013 N/A N/A 13.5-1 FIGURE 13.5-1 Control Room Area N/A N/A 14.2-1 FIGURE 14.2-1 Startup Activities Logic Diagrams N/A N/A 14.2-2 FIGURE 14.2-2 Startup Organization Chart N/A N/A 14.2-3 FIGURE 14.2-3 Test Procedure Preparation N/A N/A 14.2-4 FIGURE 14.2-4 Test Procedure Performance N/A N/A 14.2-5 FIGURE 14.2-5 Preoperational Test Phase N/A N/A 14.2-6 FIGURE 14.2-6 Initial Startup Test Phase N/A N/A 14.2-6 FIGURE 14.2-6 Initial Startup Test Phase N/A N/A 15.0-1 FIGURE 15.0-1 Illustration of Overtemperature and Overpower T N/A N/A Protection 15.0-1 A FIGURE 15.0-1 A Deleted by FSARCR PKG FSC 02-MP3-017 N/A N/A 15.0-2 FIGURE 15.0-2 Doppler Power Coefficient Used in Accident Analysis N/A N/A 15.0-3 FIGURE 15.0-3 RCCA Position Versus Time to Dashpot N/A N/A 15.0-4 FIGURE 15.0-4 Normalized Rod Worth Versus Percent Inserted N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 15.0-5 FIGURE 15.0-5 Normalized RCCA Bank Reactivity Worth Versus Drop N/A N/A Time 15.0-6 FIGURE 15.0-6 Deleted by FSARCR PKG FSC 07-MP3-049 N/A N/A 15.0-7 FIGURE 15.0-7 Abbreviations N/A N/A 15.0-8 FIGURE 15.0-8 Excessive Heat Removal Due to Feedwater Systems N/A N/A Malfunction 15.0-9 FIGURE 15.0-9 Excessive Load Increase N/A N/A 15.0-10 FIGURE 15.0-10 Depressurization of Main Steam System N/A N/A 15.0-11 FIGURE 15.0-11 Loss of External Load/Turbine Trip N/A N/A 15.0-12 FIGURE 15.0-12 Loss of Offsite Power to Station Auxiliaries N/A N/A 15.0-13 FIGURE 15.0-13 Loss of Normal Feedwater N/A N/A 15.0-14 FIGURE 15.0-14 Major Rupture of a Main Feedwater Line N/A N/A 15.0-15 FIGURE 15.0-15 Loss of Forced Reactor Coolant Flow N/A N/A 15.0-16 FIGURE 15.0-16 Uncontrolled Rod Cluster Control Assembly Bank N/A N/A Withdrawal 15.0-17 FIGURE 15.0-17 Dropped Rod Cluster Control Assembly N/A N/A 15.0-18 FIGURE 15.0-18 Single Rod Cluster Control Assembly Withdrawal at N/A N/A Full Power 15.0-19 FIGURE 15.0-19 Not Used 15.0-20 FIGURE 15.0-20 Not Used 15.0-21 FIGURE 15.0-21 Rupture of Control Rod Drive Mechanism Housing N/A N/A (Rod Ejection) 15.0-22 FIGURE 15.0-22 Inadvertent ECCS Operation at Power N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 15.0-23 FIGURE 15.0-23 Accidental Depressurization of Reactor Coolant System N/A N/A 15.0-24 FIGURE 15.0-24 Steam Generator Tube Rupture N/A N/A 15.0-25 FIGURE 15.0-25 Loss of Coolant Accident N/A N/A 15.0-26 FIGURE 15.0-26 CVCS Letdown Line Rupture N/A N/A 15.0-27 FIGURE 15.0-27 GWPS Gas Decay Tank Rupture N/A N/A 15.0-28 FIGURE 15.0-28 Floor Drain Tank Failure N/A N/A 15.0-29 FIGURE 15.0-29 Fuel Handling Accident in Fuel Building N/A N/A 15.0-30 FIGURE 15.0-30 Fuel Handling Accident Inside Containment N/A N/A 15.0-31 FIGURE 15.0-31 Spent Fuel Cask Drop Accident N/A N/A 15.1-1 FIGURE 15.1-1 Feedwater Control Valve Malfunction N/A N/A 15.1-1 A FIGURE 15.1-1 A Deleted by FSARCR PKG FSC 02-MP3-017 N/A N/A 15.1-2 FIGURE 15.1-2 Feedwater Control Valve Malfunction N/A N/A 15.1-2 A FIGURE 15.1-2 A Deleted by FSARCR PKG FSC 02-MP3-017 N/A N/A 15.1-3 FIGURE 15.1-3 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-4 FIGURE 15.1-4 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-5 FIGURE 15.1-5 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-6 FIGURE 15.1-6 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-7 FIGURE 15.1-7 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-8 FIGURE 15.1-8 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-9 FIGURE 15.1-9 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-10 FIGURE 15.1-10 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-11 FIGURE 15.1-11 Typical(1)Keffective Versus Temperature N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 15.1-12 FIGURE 15.1-12 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A 15.1-12 A FIGURE 15.1-12 A Deleted by FSARCR PKG FSC 02-MP3-017 N/A N/A 15.1-13 FIGURE 15.1-13 Deleted by FSARCR PKG FSC 07-MP3-050 N/A N/A N/A N/A 15.1-13 A FIGURE 15.1-13 A Deleted by FSARCR PKG FSC 02-MP3-017 15.1-14 FIGURE 15.1-14 TYPICAL (1)Doppler Power Feedback N/A N/A 15.1-15 FIGURE 15.1-15 1.4 SQ. FT. Steamline Rupture Offsite Power Available N/A N/A 15.1-15 A FIGURE 15.1-15 A 1.4 SQ. FT STEAMLINE RUPTURE OFFSITE N/A N/A POWER AVAILABLE 15.1-16 FIGURE 15.1-16 1.4 SQ. FT. Steamline Rupture Offsite Power Available N/A N/A 15.1-16 A FIGURE 15.1-16 A 1.4 SQ. FT. STEAMLINE RUPTURE OFFSITE N/A N/A POWER AVAILABLE 15.1-17 FIGURE 15.1-17 1.4 SQ. FT. Steamline Rupture Offsite Power Available N/A N/A 15.1-17 A FIGURE 15.1-17 A 1.4 SQ. FT. STEAMLINE RUPTURE OFFSITE N/A N/A POWER AVAILABLE 15.2-1 FIGURE 15.2-1 Turbine Trip - RCS Overpressurization Case N/A N/A 15.2-1A FIGURE 15.2-1A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-2 FIGURE 15.2-2 Turbine Trip - RCS Overpressurization Case N/A N/A 15.2-2A FIGURE 15.2-2A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-3 FIGURE 15.2-3 Turbine Trip-DNBR Case N/A N/A 15.2-3A FIGURE 15.2-3A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-4 FIGURE 15.2-4 Turbine Trip-DNBR Case N/A N/A 15.2-4A FIGURE 15.2-4A Deleted by FSARCR 02-MP3-017 N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 15.2-5 FIGURE 15.2-5 Turbine Trip-MSS Over pressurization Case N/A N/A 15.2-5A FIGURE 15.2-5A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-6 FIGURE 15.2-6 Turbine Trip-MSS Over pressurization Case N/A N/A 15.2-6A FIGURE 15.2-6A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-7 FIGURE 15.2-7 Deleted by FSARCR PKG FSC 07-MP3-051 N/A N/A 15.2-7A FIGURE 15.2-7A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-8 FIGURE 15.2-8 Deleted by FSARCR PKG FSC 07-MP3-051 N/A N/A 15.2-8A FIGURE 15.2-8A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-9 FIGURE 15.2-9 Loss of Normal Feedwater with Offsite Power Available N/A N/A 15.2-9A FIGURE 15.2-9A Loss of Normal Feedwater without Offsite Power N/A N/A Available 15.2-10 FIGURE 15.2-10 Loss of Normal Feedwater with Offsite Power Available N/A N/A 15.2-10A FIGURE 15.2-10A Loss of Normal Feedwater without Offsite Power N/A N/A Available 15.2-11 FIGURE 15.2-11 Loss of Normal Feedwater with Offsite Power Available N/A N/A 15.2-11A FIGURE 15.2-11A Loss of Normal Feedwater without Offsite Power N/A N/A Available 15.2-12 FIGURE 15.2-12 Loss of Normal Feedwater with Offsite Power Available N/A N/A 15.2-12A FIGURE 15.2-12A Loss of Normal Feedwater without Offsite Power N/A N/A Available 15.2-13 FIGURE 15.2-13 Main Feedline Rupture with Offsite Power Available N/A N/A 15.2-13A FIGURE 15.2-13A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-14 FIGURE 15.2-14 Main Feedline Rupture with Offsite Power Available N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 15.2-14A FIGURE 15.2-14A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-15 FIGURE 15.2-15 Main Feedline Rupture with Offsite Power Available N/A N/A 15.2-15A FIGURE 15.2-15A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-16 FIGURE 15.2-16 Main Feedline Rupture with Offsite Power Available N/A N/A 15.2-16A FIGURE 15.2-16A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-17 FIGURE 15.2-17 Main Feedline Rupture with Offsite Power Available N/A N/A 15.2-17A FIGURE 15.2-17A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-18 FIGURE 15.2-18 Main Feedline Rupture with Offsite Power Available N/A N/A 15.2-18A FIGURE 15.2-18A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-19 FIGURE 15.2-19 Main Feedline Rupture without Offsite Power Available N/A N/A 15.2-19A FIGURE 15.2-19A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-20 FIGURE 15.2-20 Main Feedline Rupture without Offsite Power Available N/A N/A 15.2-20A FIGURE 15.2-20A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-21 FIGURE 15.2-21 Main Feedline Rupture without Offsite Power Available N/A N/A 15.2-21A FIGURE 15.2-21A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-22 FIGURE 15.2-22 Main Feedline Rupture without Offsite Power Available N/A N/A 15.2-22A FIGURE 15.2-22A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-23 FIGURE 15.2-23 Main Feedline Rupture without Offsite Power Available N/A N/A 15.2-23A FIGURE 15.2-23A Deleted by FSARCR 02-MP3-017 N/A N/A 15.2-24 FIGURE 15.2-24 Main Feedline Rupture without Offsite Power Available N/A N/A 15.2-24A FIGURE 15.2-24A Deleted by FSARCR 02-MP3-017 N/A N/A 15.3-1 FIGURE 15.3-1 Flow Transients, One Pump Coasting Down N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 15.3-2 FIGURE 15.3-2 Nuclear Power and Pressurizer Pressure Transients, One N/A N/A Pump Coasting Down 15.3-3 FIGURE 15.3-3 Average and Hot Channel Heat Flux Transient, One N/A N/A Pump Coasting Down 15.3-4 FIGURE 15.3-4 DNBR Versus Time, One Pump Coasting Down N/A N/A 15.3-5 FIGURE 15.3-5 Core Flow Coastdown, Four Pumps Coasting Down N/A N/A 15.3-6 FIGURE 15.3-6 Nuclear Power & Pressurizer Pressure Transients, Four N/A N/A Pumps Coasting Down 15.3-7 FIGURE 15.3-7 Average & Hot Channel Transients, Four Pumps N/A N/A Coasting Down 15.3-8 FIGURE 15.3-8 DNBR versus Time, Four Pumps Coasting Down N/A N/A 15.3-9 FIGURE 15.3-9 Flow Transients, One Locked Rotor N/A N/A 15.3-9 A FIGURE 15.3-9 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.3-10 FIGURE 15.3-10 RCS Pressure, One Locked Rotor N/A N/A 15.3-10 A FIGURE 15.3-10 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.3-11 FIGURE 15.3-11 Nuclear Power, Average and Core Average Heat Flux N/A N/A Transients, One Locked Rotor 15.3-11 A FIGURE 15.3-11 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.3-12 FIGURE 15.3-12 Maximum Clad Temperature at Hot Spot, One Locked N/A N/A Rotor 15.3-12 A FIGURE 15.3-12 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.3-13 FIGURE 15.3-13 Core Flow Transient, Four Pumps Experiencing N/A N/A Frequency Decay

Figure Number Figure Label Title Drawing Number Sheet 15.3-14 FIGURE 15.3-14 Nuclear Power and Pressurizer Pressure Transients, Four N/A N/A Pumps Experiencing Frequency Decay 15.3-15 FIGURE 15.3-15 Average and Hot Channel Heat Flux Transients, Four N/A N/A Pumps Experiencing Frequency Decay 15.3-16 FIGURE 15.3-16 DNBR versus Time, Four Pumps Experiencing N/A N/A Frequency Decay 15.4-1 FIGURE 15.4-1 Neutron and Thermal Flux Transients for Uncontrolled N/A N/A RCCA Withdrawal from a Subcritical Condition 15.4-2 FIGURE 15.4-2 Omitted N/A N/A 15.4-3 FIGURE 15.4-3 Fuel and Clad Temperature Transients for Uncontrolled N/A N/A RCCA Withdrawal from a Subcritical Condition 15.4-4 FIGURE 15.4-4 Uncontrolled RCCA Bank Withdrawal from Full Power with Minimum Reactivity Feedback (100 PCM/sec N/A N/A Withdrawal Rate) 15.4-4 A FIGURE 15.4-4 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-5 FIGURE 15.4-5 Uncontrolled RCCA Bank Withdrawal from Full Power with Minimum Reactivity Feedback (100 PCM/sec N/A N/A Withdrawal Rate) 15.4-5 A FIGURE 15.4-5 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-6 FIGURE 15.4-6 Uncontrolled RCCA Bank Withdrawal from Full Power with Minimum Reactivity Feedback (100 PCM/sec N/A N/A Withdrawal Rate) 15.4-6 A FIGURE 15.4-6 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-7 FIGURE 15.4-7 Uncontrolled RCCA Bank Withdrawal from Full Power with Minimum Reactivity Feedback (1.5 PCM/sec N/A N/A Withdrawal Rate)

Figure Number Figure Label Title Drawing Number Sheet 15.4-7 A FIGURE 15.4-7 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-8 FIGURE 15.4-8 Uncontrolled RCCA Bank Withdrawal from Full Power with Minimum Reactivity Feedback (1.5 PCM/sec N/A N/A Withdrawal Rate) 15.4-8 A FIGURE 15.4-8 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-9 FIGURE 15.4-9 Uncontrolled RCCA Bank Withdrawal from Full Power with Minimum Reactivity Feedback (1.5 PCM/sec N/A N/A Withdrawal Rate) 15.4-9 A FIGURE 15.4-9 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-10 FIGURE 15.4-10 Minimum DNBR versus Reactivity Insertion Rate Rod N/A N/A Withdrawal from Full Power 15.4-10 A FIGURE 15.4-10 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-11 FIGURE 15.4-11 Minimum DNBR versus Reactivity Insertion Rate Rod N/A N/A Withdrawal from 60% RTP 15.4-11 A FIGURE 15.4-11 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-12 FIGURE 15.4-12 Minimum DNBR versus Reactivity Insertion Rate Rod N/A N/A Withdrawal from 10% RTP 15.4-13 FIGURE 15.4-13 Dropped Rod Cluster Control Assembly, Manual N/A N/A Control 15.4-14 FIGURE 15.4-14 Dropped Rod Cluster Control Assembly, Manual N/A N/A Control 15.4-15 FIGURE 15.4-15 Not Used N/A N/A 15.4-16 FIGURE 15.4-16 Not Used N/A N/A 15.4-17 FIGURE 15.4-17 Not Used N/A N/A 15.4-18 FIGURE 15.4-18 Not Used N/A N/A

Figure Number Figure Label Title Drawing Number Sheet 15.4-19 FIGURE 15.4-19 Not Used N/A N/A 15.4-19 FIGURE 15.4-19 Not Used N/A N/A 15.4-21 FIGURE 15.4-21 Interchange Between Region 1 and Region 3 Assembly N/A N/A 15.4-22 FIGURE 15.4-22 Interchange Between Region 1 and Region 2 Assembly, Burnable Poison Rods Being Retained by the Region 2 N/A N/A Assembly 15.4-23 FIGURE 15.4-23 Interchange Between Region 1 and Region 2 Assembly, Burnable Poison Rods Being Retained by the Region 1 N/A N/A Assembly 15.4-24 FIGURE 15.4-24 Enrichment Error: A Region 2 Assembly Loaded into N/A N/A the Core Central Position 15.4-25 FIGURE 15.4-25 Loading a Region 2 Assembly into a Region 1 Position N/A N/A Near Core Periphery 15.4-26 FIGURE 15.4-26 Nuclear Power Transient BOL HFP RCCA Ejection N/A N/A 15.4-26 A FIGURE 15.4-26 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-27 FIGURE 15.4-27 Hot Spot Fuel and Clad Temperature versus Time - BOL N/A N/A HFP RCCA Ejection 15.4-27 A FIGURE 15.4-27 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.4-28 FIGURE 15.4-28 Nuclear Power Transient EOL HZP RCCA Ejection N/A N/A (Two RCPs Running) 15.4-29 FIGURE 15.4-29 Hot Spot Fuel and Clad Temperature versus Time - EOL N/A N/A HZP RCCA Ejection (Two RCPs Running) 15.4-30 FIGURE 15.4-30 Reactor Coolant System Integrated Break Flow N/A N/A Following a Rod Ejection Accident

Figure Number Figure Label Title Drawing Number Sheet 15.5-1 FIGURE 15.5-1 Inadvertent Operation of ECCS, Pressurizer Pressure N/A N/A versus Time 15.5-2 FIGURE 15.5-2 Inadvertent Operation of ECCS, Pressurizer Level N/A N/A versus Time 15.5-3 FIGURE 15.5-3 CVCS Malfunction that Increases Reactor Coolant Inventory, Nuclear Power and Vessel Average N/A N/A Temperature versus Time 15.6-1 FIGURE 15.6-1 Inadvertent Opening of a Pressurizer Safety Valve N/A N/A 15.6-1 A FIGURE 15.6-1 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.6-2 FIGURE 15.6-2 Inadvertent Opening of a Pressurizer Safety Valve N/A N/A 15.6-2 A FIGURE 15.6-2 A Deleted by FSARCR 02-MP3-017 N/A N/A 15.6-3 FIGURE 15.6-3 Deleted by FSARCR 02-MP3-017 N/A N/A 15.6.3-1 FIGURE 15.6.3-1 Pressurizer Level N/A N/A 15.6.3-2 FIGURE 15.6.3-2 Reactor Coolant System Pressure N/A N/A 15.6.3-3 FIGURE 15.6.3-3 Secondary Pressure N/A N/A 15.6.3-4 FIGURE 15.6.3-4 Ruptured Loop Hot and Cold Leg RCS Temperatures N/A N/A 15.6.3-5 FIGURE 15.6.3-5 Intact Loop Hot and Cold Leg RCS Temperatures N/A N/A 15.6.3-6 FIGURE 15.6.3-6 Primary to Secondary Break Flow Rate N/A N/A 15.6.3-7 FIGURE 15.6.3-7 Differential Pressure Between Reactor Coolant System N/A N/A and Ruptured Steam Generator 15.6.3-8 FIGURE 15.6.3-8 Ruptured Steam Generator Water Volume N/A N/A 15.6.3-9 FIGURE 15.6.3-9 Ruptured Steam Generator Water Mass N/A N/A 15.6.3-10 FIGURE 15.6.3-10 Ruptured Steam Generator Mass Release Rate to the N/A N/A Atmosphere

Figure Number Figure Label Title Drawing Number Sheet 15.6.3-11 FIGURE 15.6.3-11 Intact Steam Generators Mass Release Rate to the N/A N/A Atmosphere 15.6.3-12 FIGURE 15.6.3-12 Flashed Break Flow N/A N/A 15.6-4 FIGURE 15.6-4 Sequence of Events for Large Break LOCA Analysis N/A N/A 15.6-5 FIGURE 15.6-5 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-6 FIGURE 15.6-6 Code Interface Description for Small Break LOCA N/A N/A Model 15.6-7 FIGURE 15.6-7 Small Break Power Shape N/A N/A 15.6-8 FIGURE 15.6-8 Limiting PCT Case PCT and PCT Location N/A N/A 15.6-8 A FIGURE 15.6-8 A Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-9 FIGURE 15.6-9 Limiting PCT Case Vessel Side Break Flow N/A N/A 15.6-10 FIGURE 15.6-10 Limiting PCT Case Loop Side Break Flow N/A N/A 15.6-11 FIGURE 15.6-11 Limiting PCT Case Broken and Intact Loop Void N/A N/A Fraction 15.6-12 FIGURE 15.6-12 Limiting PCT Case Hot Assembly Top Third of Core N/A N/A Vapor Flow 15.6-13 FIGURE 15.6-13 Limiting PCT Case Pressurizer Pressure N/A N/A 15.6-14 FIGURE 15.6-14 Limiting PCT Case Lower Plenum Collapsed Liquid N/A N/A Level 15.6-15 FIGURE 15.6-15 Limiting PCT Case Vessel Fluid Mass N/A N/A 15.6-16 FIGURE 15.6-16 Limiting PCT Case Loop 2 Accumulator Flow N/A N/A 15.6-17 FIGURE 15.6-17 Limiting PCT Case Loop 2 Safety Injection Flow N/A N/A 15.6-18 FIGURE 15.6-18 Limiting PCT Case Core Average Channel Collapsed N/A N/A Liquid Level

Figure Number Figure Label Title Drawing Number Sheet 15.6-19 FIGURE 15.6-19 Limiting PCT Case Loop 2 Downcomer Collapsed N/A N/A Liquid Level 15.6-20 FIGURE 15.6-20 BELOCA Analysis Axial Power Shape Operating Space N/A N/A Envelope 15.6-21 FIGURE 15.6-21 Lower Bound Containment Pressure N/A N/A 15.6-22 FIGURE 15.6-22 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-23 FIGURE 15.6-23 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-24 FIGURE 15.6-24 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-25 FIGURE 15.6-25 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-26 FIGURE 15.6-26 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-27 FIGURE 15.6-27 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-28 FIGURE 15.6-28 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-28 FIGURE 15.6-28 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-30 FIGURE 15.6-30 Deleted by FSARCR PKG FSC 07-MP3-054 N/A N/A 15.6-31 FIGURE 15.6-31 Reactor Coolant System Pressure (4 inch Break) N/A N/A 15.6-32 FIGURE 15.6-32 Core Mixture Level (4 inch Break) N/A N/A 15.6-33 FIGURE 15.6-33 Clad Temperature Transient at Peak Temperature N/A N/A Elevation (4 inch Break) 15.6-34 FIGURE 15.6-34 Core Exit Steam Flow Rate (4 inch Break) N/A N/A 15.6-35 FIGURE 15.6-35 Clad Surface Heat Transfer Coefficient at Peak Clad N/A N/A Temperature Elevation (4 inch Break) 15.6-36 FIGURE 15.6-36 Fluid Temperature at Peak Clad Temperature Elevation N/A N/A (4 inch Break)

Figure Number Figure Label Title Drawing Number Sheet 15.6-37 FIGURE 15.6-37 Reactor Coolant System Pressure (1.5 inch Break) N/A N/A 15.6-38 FIGURE 15.6-38 Reactor Coolant System Pressure (2 inch Break) N/A N/A 15.6-39 FIGURE 15.6-39 Reactor Coolant System Pressure (3 inch Break) N/A N/A 15.6-40 FIGURE 15.6-40 Reactor Coolant System Pressure (6 inch Break) N/A N/A 15.6-41 FIGURE 15.6-41 Reactor Coolant System Pressure (8.75 inch Break) N/A N/A 15.6-42 FIGURE 15.6-42 Core Mixture Level (1.5 inch Break) N/A N/A 15.6-43 FIGURE 15.6-43 Core Mixture Level (2 inch Break) N/A N/A 15.6-44 FIGURE 15.6-44 Figures 15.6-44 through 62 Deleted by FSARCR PKG N/A N/A FSC 02-MP3-017 15.B-1 FIGURE 15.B-1 Figures Deleted by FSARCR 02-MP3-017 N/A N/A 3-1 FPER FIGURE: 3-1 Fire Protection Organizational Chart (Deleted) N/A N/A 4-1 FPER FIGURE: 4-1 (Sheets 1-6) P&ID Fire Protection 25212-26946 (a) SH 1 OF 4-1 FPER FIGURE: 4-1 (Sheets 1-6) P&ID Fire Protection 25212-26946 (a) SH 2 OF 4-1 FPER FIGURE: 4-1 (Sheets 1-6) P&ID Fire Protection 25212-26946 (a) SH 3 OF 4-1 FPER FIGURE: 4-1 (Sheets 1-6) P&ID Fire Protection 25212-26946 (a) SH 4 OF 4-1 FPER FIGURE: 4-1 (Sheets 1-6) P&ID Fire Protection 25212-26946 (a) SH 5 OF 4-1 FPER FIGURE: 4-1 (Sheets 1-6) P&ID Fire Protection 25212-26970 (a) SH 1 77A FPER FIGURE: 77A Fire Hazard Analysis Elevation 3 Feet 8 Inches 25212-24260 (a) N/A 77B FPER FIGURE: 77B Fire Hazard Analysis Elevation 24 Feet 6 inches 25212-24261 (a) N/A 77C FPER FIGURE: 77C Fire Hazard Analysis Elevation 38 Feet 6 inches 25212-24262 (a) N/A 77D FPER FIGURE: 77D Fire Hazard Analysis Elevation 52 Feet 6 inches 25212-24263 (a) N/A

Figure Number Figure Label Title Drawing Number Sheet 77E FPER FIGURE: 77E Fire Hazard Analysis Elevation (Roof Plan) 25212-24264 (a) N/A 77F FPER FIGURE: 77F Fire Hazard Analysis Elevation (Sections) 25212-24265 (a) N/A 8-1 FPER FIGURE: 8-1 Process Control Transfer Scheme (Typical) N/A N/A 8-2 FPER FIGURE: 8-2 Process Instrumentation Transfer Scheme N/A N/A

a. Incorporated by reference this engineering controlled drawing is, coincidentally, an MPS-3 FSAR figure. Refer to the controlled plant drawing for the revision.
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