ML22193A081
Text
MILLSTONE POWER STATION UNIT 2 INAL SAFETY ANALYSIS REPORT Revision 4006/30/22
Revision 4006/30/22 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.
39.03 03/31/22 MP2-UCR-2021-007 2.5.4.2.1.A.12, 2.5.4.2.1.B.2.c, Service Water Pump Motor Restoration Flood Water 2.5.4.2.1.B.3.c Level CR1171836 39.03 03/31/22 MP2-UCR-2022-002 Table 14.6.3-4, Table 14.6.3-5 Corrects transcription errors identified by the NRC CR1191354 39.02 01/27/22 MP2-UCR-2016-017 Tables 6.2-1, 6.4-1, 9.4-1, 9.5-2, Change to allow ANSI class ratings other than 600 o and 11.1-1 800 to be used in various systems.
CA 3033065 39.02 01/27/22 MP2-UCR-2018-013 7.5.7 MP2 Loose Parts Monitoring System Replacement MP2-17-00158-000 39.02 01/27/22 MP2-UCR-2020-007 Figure 8.1-1D 345kV Switch 15G-10T-4 Replacement MP2-19-01182 39.02 01/27/22 MP2-UCR-2020-009 8.5.22, 8.5.4.1 MP2 Battery Charger Replacement (201A/DC1)
MP2-19-01174 39.02 01/27/22 MP2-UCR-2021-005 3.3.4, Table 14.1.5.2-6, Figures Millstone Unit 2 Cycle 28 Updates to Millstone Uni 14.0.7-1, 14.0.7-5, 14.0.7-6 Final Safety Analysis Report EVAL-ENG-RSE-M2C28, Revision 0 39.02 01/27/22 MP2-UCR-2021-006 Table 5.2-11 MP2 10CFR50 Appendix J Scope Reduction Shutdown Cooling Penetration 10 ETE-MP-2021-1088 39.01 09/30/21 MP2-UCR-2018-017 7.8 FSAR change to update Communications System fo replacement of Trunked Radio System.
MPG-15-01007, CR499765
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.
39.01 09/30/21 MP2-UCR-2021-002 Table 7.5-3 Update MP2 FSAR Accident Monitoring Instrumen Table 7.5-3 ETE-MP-2020-1068 Revision 3906/30/21 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.
39 03/31/21 MP2-UCR-2020-011 7.11, 12.10 Addition of 50.69 Program P3 Technical Specification Amendment 337 Risk-Informed Categorization and Treatment of Structure Systems, and Components of Nuclear Power Reacto 39 03/31/21 MP2-UCR-2021-001 14.6.1.4, 14.6.1.15, 14.6.1.6, Removal of Inadvertent Opening of a Power Operat 14.6.6, 14.6.7, Tables 14.6-1 Relief Valve in Mode 2 from the Millstone Unit 2 and 14.6.1-2 FSAR ETE-NAF-2020-0118 39 03/31/21 MP2-UCR-2021-003 1.10, 12.8 Incorporating Quality Assurace Program Descriptio by Reference CA8102163 38.02 03/31/21 MP2-UCR-2016-011 8.1.2.2.c MP2 FSAR Update To Document The Addition Of T Open Phase Detection Relay Schemes On The High Voltage Side Of The Generator Step-up And Rsst Transformers.
MP2-15-01026, MP2-17-00156
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.
38.02 03/31/21 MP2-UCR-2016-013 1.2.12.d, 11.1.3.1, 11.1.3.2, Update the affected sections due to the removal of 11.1.5.1, Table 11.1-1, Figures demineralizers T141A, T141B, T141C, and the 1.2-9, 9.12-1, 10.3-1, 11.1-4, installation of the Energy Solutions ALPS/AIM and 11.1-3, 11.2-5 SEDS systems.
MP2-14-01169, MP2-15-01044, DC MP2-15-01045 38.02 03/31/21 MP2-UCR-2016-014 Table 11.1-1 Update Liquid and Aerated Waste Valve information allow other stainless steel material grads and other ANSI ratings.
MP2-14-01169 38.02 03/31/21 MP2-UCR-2018-015 Appendix 5.E.VI Add NUPIPE II computer code to UFSAR Appendi 5E.VI MP2-17-00178 38.02 03/31/21 MP2-UCR-2019-001 14.1.5.3, 14.6.3.6.2, Table Updated Main Steam Line Break and Steam Genera 14.1.5.3-1 , 14.1.5.3-2, 14.6.3-4 Tube Rupture Dose Consequences.
through 14.6.3-6 ETE-NAF-2019-0010, CR 1094790, CR 1103271 38.02 03/31/21 MP2-UCR-2019-007 9.8.2.2.3.5 Permanently Bypass RFM Aux. Hoist Load Cell Interlock, M2H12.
MP2-19-01136 38.02 03/31/21 MP2-UCR-2020-001 Figure 8.1-1D 345kV Switch 15G-18T-8 Replacement.
MP3-18-01094 38.02 03/31/21 MP2-UCR-2020-008 5.2.8.4.1, 5.2.8.4.2 Revision of "MP2 Tendon Surveillance Program Description".
LBDCR 19-MP2-009
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.
38.02 03/31/21 MP2-UCR-2020-010 7.8.3 Replacing ENRS (ARCOS) with DEENS (Everbrid MP-20-04 EP-AA-101-Attachment 2, 50.54(q) for change from Emergency Notification & Respons System (ENRS) to Dominion Energy Emergency Notification System (DEENS) 38.01 09/30/20 MP2-UCR-2015-010 8.6.2.2, 5.6.4.1 Reflects replacement of inverters (INV 2, INV4, INV6).
MP2-14-01158 38.01 09/30/20 MP2-UCR-2015-020 Figure 8.1-1D Reflects revised discussion regarding piping weld examination method(s).
LBDCR 14-MP2-019 38.01 09/30/20 MP2-UCR-2016-005 7.2.3.2.2 Delete the word "reed" in the first paragraph in MP2 FSAR section 7.2.3.2.2.
MP2-15-01097 38.01 09/30/20 MP2-UCR-2020-004 6.7.2 Update Unit 2 FSAR to reflect changes for License Amendment No. 338.
License Amendment No. 338 Revision 3806/30/20 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.
38 06/30/20 MP2-UCR-2019-030 8.3 Increasing the TRM required Diesel Fuel Oil Storag for T-148.
ETE-MP-2020-1002
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.
38 06/30/20 MP2-UCR-2020-002 3.3.1.1.2, 3.3.4, 3.5.2.2.1, 3.5.5, Millstone Unit 2 Cycle 27 Updates to Millstone Uni Figure 14.0.7-1, Figure 14.0.7- Final Safety Analysis Report.
5, Figure 14.0.7-6, Table EVAL-ENG-RSE-M2C27 14.1.5.2-6 38 06/30/20 MP2-UCR-2020-003 5.2.6.1.1, 8.7.1.2, 8.7.2.2 Update the MP2 FSAR to reflect IEEE Standard 31 1976 as applicable to replacement medium voltage electrical containment penetration modules.
MP2-19-01025 37.03 03/31/20 MP2-UCR-2019-006 9.2.4.1 Interm Retirement of MP2 Boric Acid Heat Tracing Circuits.
ETE-MP-2019-1081 37.03 03/31/20 MP2-UCR-2018-010 1.2.5, 1.4.3.1, 4.3.2, Table 4.3- Updating The FSAR to Accurately Reflect The New 2, Table 10.2-1 Unit 2 Main Steam Moisture Content.
MP2-19-01066 37.03 03/31/20 MP2-UCR-2019-011 8.5.1.2 Changing of the Unit 2 Vital Battery Discharge Testi and Battery Charger Load Testing frequencies.
ETE-MP-2019-1055 37.02 12/30/19 MP2-UCR-2017-017 Figure 14.0.7-5 Departure from Nucleate Boiling Limiting Conditio for Operation Verification Results.
ETE-NAF-2017-0169
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.
37.02 12/3019 MP2-UCR-2019-005 4.3.8.1.1, 4.3.8.3.1, Trend Recorder Description.
7.5.1.2.1.1.a, 7.5.1.2.1.1.c, MP2-17-00101, DCR M2-96064, M2-05003 7.5.1.2.2, 7.5.5.1, 7.5.5.3, 7.5.5.4, 7.5.6.2.2.2.6, 7.5.6.3.2.1.8, 7.5.6.3.2.2.7, 7.6.2.2.2 37.01 09/30/19 MP2-UCR-2017-010 2.5.4.2.1 AOP 2560 - Actions Due to Intake Water Level Elevation Approaching 16-6 37.01 09/3019 MP2-UCR-2019-002 7.3.4.2.3 SAR section 7.3.4.2.3 not consistent with Specificati 7604-M-480, Specification For Engineered Safety Actuation Systems for The Millstone Point Compan Millstone Nuclear Power Station Unit 2 Waterford Connecticut.
STI-M2-2018-001 Revision 3706/27/19 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.
36.2 12/31/18 MP2-UCR-2018-001 8.6.2.2 Unit 2 inverter replacement.
MP2-14-01130 36.2 12/31/18 MP2-UCR-2018-005 7.4.7.2.2 Millstone Unit 2 Main Control Room Recorders Replacement on panel C-05.
MP2-17-00171
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.
36.2 12/31/18 MP2-UCR-2018-011 8.1.2.2 Generator Backup Audio-Tone Equipment Replacement.
MP2-18-00102 36.2 12/31/18 MP2-UCR-2018-012 Table 11.1-1 Correction of Volume of Waste Gas Surge Tank in FSAR Table 11.1.-1.
CR1078780, CR1091106 36.2 12/31/18 MP2-UCR-2018-014 14.0.7.2, 14.0.7-5, Millstone Unit 2 Cycle 26 Updates to Millstone Uni Figure 14.0.7-6, Final Safety Analysis Report.
Table 14.1.5.2-6 EVAL-ENG-RESE-M2C26 36.2 12/31/18 MP2-UCR-2018-016 Table 14.6.3-5 Specification of the Basis for the Steam Generator Partition Factor for Particulates.
ETE-NAF-2018-0099 36.1 09/27/18 MP2-UCR-2015-017 8.4.2.1, 8.5.1.1, 8.5.2.1, 8.5.2.2, Reflects removal of 125 VDC lighting loads from Vi 8.5.3.1, 8.5.3.2 Station Batteries & installation of LED lighting.
MP2-14-01185
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.
36.1 09/27/18 MP2-UCR-2018-007 14.1.5.2.5.1.4, 14.1.5.2.5.1.6, MPS2 FSAR Update for Post-Scram Main Steam Li 14.1.5.2.6.2.1, 14.1.5.2.6.2.3, Break with Decreased MTC and Revised AFW Flow Table 14.1.5.2-5, Distribution.
Table 14.1.5.2-6, ETE-NAF-2018-0019 Table 14.1.5.2-8, Figure 14.1.5.2.-9, Figure 14.1.5.2.-10, Figure 14.1.5.2.-11, Figure 14.1.5.2.-12, Figure 14.1.5.2.-13, Figure 14.1.5.2.-14, Figure 14.1.5.2.-15, Figure 14.1.5.2.-16 36.1 09/27/18 MP2-UCR-2018-009 14.6.5.2, Table 14.6.5.2-7 MPS3 FSAR Update to the Small Break Loss of Coolant Accident (SBLOCA) Results Due to Error Correction.
ETE-NAF-2018-0060
Revision 3606/28/18 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.
36 06/28/18 MP2-UCR-2017-005 10.4.5.5 Update FSAR Section 10.4.5.5 to read as follows: "T plant can carry 55 percent load with one-half of the feedwater heaters out of service and isolated from th system, with only one condensate pump in operation and with only one SGFP in service".
LA3022214 36 06/28/18 MP2-UCR-2018-002 Table 1.3-1, Table 11.1-1 Correction of Volume of Waste Gas Test Tank in FS table 11.1-1 CR1078780 and CR1080672 36 06/28/18 MP2-UCR-2018-006 Table 4.6-2 Update to MPS2 Pressurizer RTNDT values determined through Drop Weight Testing.
AREVA CR 2017-2164 35.3 03/29/18 MP2-UCR-2017-017 Table 14.0.7-5, Figure 14.0.7-5 Departure from Nucleate Boiling Limiting Conditio for Operation Verification Results.
ETE: ETE-NAF-2017-0169 CA3060853 35.3 03/29/18 MP2-UCR-2018-003 Table 9.11-2 Change Pressure Values on Table 9.11-2 for Instrum Air Receiver Tanks T-51E and T-51F.
DC: MP2-17-00175 35.2 12/28/17 MP2-UCR-2017-013 9.2.3.3, 11.1.3.1 Modify U3 FSAR to correct item related to previous degasifier related FSAR change.
FSARCR: 98-MP2-167 35.2 12/28/17 MP2-UCR-2017-014 9.2.2.1 Modify U2 FSAR to correct item related to VCT lev controls related to a previous FSAR change.
FSARCR: 97-MP2-66
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.
35.1 09/28/17 MP2-UCR-2016-001 1.A, 8.1.2.2, 8.1.2.3 Eversource 15G Breaker Failure Relay Replacemen ETE-MP-2015-1186 35.1 09/28/17 MP2-UCR-2016-018 8.1.1.2, 8.1.2.1, 8.1.2.2, Eversource Energy proposes to reconfigure the 345 Fig 8.1-1B, Fig 8.1-1C, Millstone - Haddam - Besesk 348 line. ETE-MP-20 Fig 8.1-1D 1135 35.1 09/28/17 MP2-UCR-2016-019 7.6.5.4.1 App R fire panel door lock removal.
CR1045068 35.1 09/28/17 MP2-UCR-2016-020 7.5.5.3 Plant Process Computer Data Diode Installation.
MP2-16-01035 35.1 09/28/17 MP2-UCR-2017-001 Figure 6.5-1, Table 6.5-2 Replacement of C CAR Fan M2F14C.
MP2-17-01004
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.
35.1 09/28/17 MP2-UCR-2017-002 1.4.2, 3.1, 3.2.3, 3.3.1, 3.3.1.1, This SAR Change Request updates the Millstone Un 3.3.1.1.1, 3.3.1.1.2, 3.3.1.3.1, 2 FSAR for the Cycle 25 core design and supporting 3.3.1.3.2, 3.3.4 Refs, Table 3.3- safety analyses.
1, Figure 3.3-1A, Figure 3.3- ETE-NAF-2017-0001, EVAL-ENG-RSE-M2C25 1B, 3.4.2, 3.4.3.2.3, 3.5.1.1, 3.5.2.1.2, 3.5.2.1.3, 3.5.3.3.1, 3.5.3.3.4, Table 3.5-1, 9.5.2.1, 9.5.3.1, 9.5.4.1, 14.0.2, 14.0.7.1, 14.0.10, Table 14.0.2-2, Table 14.0.7-4, Table 14.0.7-5, Figure 14.0.7-1, Figure 14.0.7-2, Figure 14.0.7-5, Figure 14.0.7-6, 14.1.5.1.6.1, 14.1.5.1.6.1.3, 14.1.5.1.7, 14.1.5.2.5.1.4, 14.1.5.2.5.1.6, 14.1.5.2.6.1.1, 14.1.5.2.6.1.2, 14.1.5.2.6.1.3, Table 14.1.5.1-5, Table 14.1.5.1-6, able 14.1.5.1-7, Figure 14.1.5.1-1, Figure 14.1.5.1-2
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.
35.1 09/28/17 MP2-UCR-2017-002 Figure 14.1.5.1-3, This SAR Change Request updates the Millstone Un (cont) Figure 14.1.5.1-4, 2 FSAR for the Cycle 25 core design and supporting Figure 14.1.5.1-5, safety analyses.
Figure 14.1.5.1-6, ETE-NAF-2017-0001, EVAL-ENG-RSE-M2C25 Table 14.1.5.2-4, Table 14.1.5.2-5, Table 14.1.5.2-6, Table 14.1.5.2-7, Figure 14.1.5.2-2, Figure 14.1.5.2-3, Figure 14.1.5.2-4, Figure 14.1.5.2-5, Figure 14.1.5.2-6, Figure 14.1.5.2-7, Figure 14.1.5.2-8, Figure 14.1.5.2-9, Table 14.2.4-3, Figure 14.2.4-1, Figure 14.2.4-2, Figure 14.2.4-3, Figure 14.2.4-4, Figure 14.2.4-5, 14.4.6.5, 14.4.6.6, 14.4.10 Refs, Table 14.4.6-2, Table 14.4.6-3, Table 14.4.6-4, 14.6.5, 14.6.5.1 through 14.6.5.8, 14.6.5.4 through 14.6.5.4.8 (new)
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.
35.1 09/28/17 MP2-UCR-2017-002 14.6.6 Refs, Table 14.6.5.1-3, This SAR Change Request updates the Millstone Un (cont) Table 14.6.5.1-4, 2 FSAR for the Cycle 25 core design and supporting Table 14.6.5.1-5, safety analyses.
Table 14.6.5.1-6, ETE-NAF-2017-0001, EVAL-ENG-RSE-M2C25 Table 14.6.5.1-7, Table 14.6.5.1-8, Figures 14.6.5.1-1 through Figure 14.6.5.1-17, Tables 14.6.5.4-1 through Table 14.6.5.4-7, Figures 14.6.5.4-1 through Figures 14.6.5.4-19 35.1 09/28/17 MP2-UCR-2017-006 4.3.8.5.11 Update to reflect that during normal operation, strainers for the B and C RCPs are operated with the strainer baskets removed and the A and D RCPs do have strainers.
MP2-17-01033 35.1 09/28/17 MP2-UCR-2017-007 7.3.1.2.8 Engineered Safety Feature Actuation UFSAR Response Time Change.
ETE-MP-2015-1030 35.1 09/28/17 MP2-UCR-2017-008 4.3.2, 4.3.5 MP2 Plant Process Computer Replacement addition FSAR changes missed during the initial project.
MP2-13-01067 35.1 09/28/17 MP2-UCR-2017-009 8.3.3.1 Implementation of Revised Combustible Gas (Hydrogen) Control Requirements in Containment additional FSAR changes missed during the initial project.
M2-04009
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.
35.1 09/28/17 MP2-UCR-2017-011 9.10.2.1 Editorial correction to MP2 FSAR. Change last 2 sentences of 4th paragraph of 9.10.2.1 on page 9.10-Pump Running and trouble signals for pump P-82 a available in the Unit 2 (Should be Unit 3) Control Room.
DM3-01-0064-00 35.1 09/28/17 MP2-UCR-2017-012 14.8.2.1.2 Modify FSAR sections 10.4.5.5 and 14.8.2.1.2 to correct editorial errors.
LA3022214, CR1047811 Revision 3506/29/17 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 06/29/17 Administrative As identified in the 2017 NRC Major Revision issued for the purpose of 2017 NRC Submittal List of Changed Pages Submittal. Updated footer on all pages to reflect and submitted Summary of Revision 35.
Change.
35 06/29/17 MP2-UCR-2017-004 10.3.4.2, Table 10.3-1 LA3022214 - Modify FSAR Section 10.3.4.2 Tests a Inspection to read See Section 5.2.7.4.1 in lieu o 5.2.8.4.2.
35 06/29/17 MP2-UCR-2015-025 14.0.11, 14.6.1.1, 14.6.1.6 Confirmatory Order EA-13-188, AREVA analysis AN 3406, Rev. 0 - Remove credit for charging from the lo term portion of the inadvertent opening of the PORV (IOPORV) event.
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.
34.3 03/30/17 MP2-UCR-2016-008 9.5.1.1, 9.5.2.1, 9.5.3.1 The NRC requested additional information be provid in the FSAR to describe the procedural controls in pl to maintain the Millstone 2 Spent Fuel Pool temperat below 150°F. LAR 15-571 34.2 12/22/16 MP2-UCR-2016-016 14.6.5.2, 14.6.5.2.5, 14.6.5.2.5.1, This SAR change request updates the Small Break L 14.6.5.2.5.2, 14.6.5.2.5.3, of Coolant Accident (SBLOCA) analysis presented in 14.6.5.2.5.4, 14.6.5.2.5.5, FSAR Section 14.6.5.2.
14.6.5.2.5.8, 14.6.5.2.5.9, 14.6.5.2.6, 14.6.5.2.7, 14.6.5.2.8, Figures 14.6.5.2-1, 14.6.5.2-2, 14.6.5.2-3, 14.6.5.2-4, 14.6.5.2-5, 14.6.5.2-6, 14.6.5.2-7, 14.6.5.2-8, 14.6.5.2-9, 14.6.5.2-10, 14.6.5.2-11, 14.6.5.2-12, 14.6.5.2-13, 14.6.5.2-14, 14.6.5.2-15, 14.6.5.2-16, 14.6.5.2-17, 14.6.5.2-18, 14.6.5.2-19, 14.6.5.2-20, 14.6.5.2-21, 14.6.5.2-22, Tables 14.6.5.2-3, 14.6.5.2-4, 14.6.5.2-5, 14.6.5.2-6, 14.6.5.2-7 34.2 12/22/16 MP2-UCR-2016-012 15.2.1.21 MP3 HVK Chiller Service Water Thermal Performan Testing Elimination.
34.2 12/22/16 MP2-UCR-2016-010 15.2.1.2 Cancellation of Millstone 2 Boraflex Monitoring Program.
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.
34.2 12/22/16 MP2-UCR-2016-009 11.E.1 RM-8123 and RM-8262 are described incorrectly in FSAR. This change removes the reference to a gamm geiger muller detector chamber type and replace it wi the correct beta scintillator type detector.
34.2 12/22/16 MP2-UCR-2016-003 9.3.2.3 Update Subsection 9.3.2.3 to reflect changes made by DCN DM2-00-0166-07 that eliminated the packing leak-off lines on M22-SI-306.
34.2 12/22/16 MP2-UCR-2015-007 1.2.10.4, 1.A, 9.8.2.1.1, 9.8.2.1.2, Reflects changes associated with LBDCR 12-MP2-0 9.8.2.2.2, Figure 9.8-7, Figure 9.8-8A, Figure 9.8-8B, Figure 9.8-8C, 14.7.4.1 34.2 12/22/16 MP2-UCR-2013-017 Table 6.7-1, Table 9.9-11 Reflects correction of technical value in the respectiv tables.
34.1 9/29/16 MP2-UCR-2016-007 Chapter 1 section 1.A; Chapter 8 Unit 2 SLOD Removal (LBDCR 15-MP2-006)
List of Figures; Chapter 8 Section 8.1.1.4, 8.1.2.1; 8.1.2.2; 8.1.2.3 and Figure 8.1-1A; 8.1-1B 34.1 9/29/16 MP2-UCR-2016-006 Section 14.8.2.2.4 Millstone 2 NRC License Amendment 326, Millston Power Station Unit 2 - Issuance of Amendment to Revise Technical Specifications for Containment Lea Rate Testing (CAC No. MF5838), March 31, 2016 (ADAMS Accession Number ML16068A312).
34.1 9/29/16 MP2-UCR-2016-004 Table 11.2-1 Correct typo identified by CR1017686.
reviation H Aerated Drain Header AS Auxiliary Exhaust Actuation Signal S Auxiliary Exhaust System WS Anticipated Transient Without Scram L Beginning of Life R Boiling Water Reactor A Control Element Assembly DM Control Element Drive Mechanism DS Control Element Drive System R Code of Federal Regulations S Containment Isolation Actuation Signal FS Control Room Filtration System AS Containment Spray Actuation Signal S Containment Spray System CS Chemical and Volume Control System H Containment Vent Header A Design Basis Accident E Design Basis Earthquake B Departure from Nucleate Boiling BR Departure from Nucleate Boiling Ratio L Division of Reactor Licensing Enclosure Building FR Enclosure Building Filtration Region FS Enclosure Building Filtration System
reviation CS Emergency Core Cooling System L End of Life S Engineered Safety Features Control System Degrees Fahrenheit Fire Protection System Fuel Transfer Feed Water P High Mechanical Performance SI High Pressure Safety Injection P High Thermal Performance Instrument Air Inside Diameter CA Loss of Coolant Accident I Low Pressure Safety Injection C Maximum Permissible Concentration L Mean Sea Level S Main Steam System U Metric Tons Uranium D Megawatt Days T Non-Destructive Testing TT Nil Ductility Transition Temperature Nitrogen Supply SS Nuclear Steam Supply System E Operating Basis Earthquake
reviation Outside Diameter Purge Air H Primary Drain Header T Primary Drain Tank M Parts Per Million MP Preoperational Vibration Monitoring Program R Pressurized Water Reactor CCW Reactor Building Closed Cooling Water CCWS Reactor Building Closed Cooling Water System S Reactor Coolant System S Radioactive Waste System ST Refueling Water Storage Tank Station Air BS Steam Generator Blowdown System S Safety Injection Actuation Signal Safety Injection System AS Sump Recirculation Actuation Signal ST Spent Resin Storage Tank Sampling System CCWS Turbine Building Closed Cooling Water System H Waste Gas Header EC Westinghouse Rector Evaluation Center R Westinghouse Test Reactor
APTER 1: INTRODUCTION AND
SUMMARY
Table of Contents List of Tables List of Figures Introduction....................................................................................................... 1.1-1 Summary Description ....................................................................................... 1.2-1 Comparison with Other Plants .......................................................................... 1.3-1 Principal Architectural And Engineering Criteria for Design .......................... 1.4-1 Research and Development Requirements ....................................................... 1.5-1 Identification of Contractors ............................................................................. 1.6-1 General Design Changes Since Issuance of Preliminary Safety Analysis Report.....
1.7-1 Advisory Committee on Reactor Safeguards Special Interest Items [This Section Provides Historical Information Provided to the ACRS at the Time of Initial Licensing and Was Not Intended to Be Updated.] ........................................... 1.8-1 Topical Reports................................................................................................. 1.9-1 Material Incorporated by Reference ............................................................... 1.10-1 AEC General Design Criteria for Nuclear Power Plants ................................. 1.A-1 APTER 2: SITE AND ENVIRONMENT Table of Contents List of Tables List of Figures General Description .......................................................................................... 2.1-1 Population, Land Use and Water Use ............................................................... 2.2-1 Meteorology...................................................................................................... 2.3-1 Geology............................................................................................................. 2.4-1 Hydrology ......................................................................................................... 2.5-1
tion Title Page Seismology........................................................................................................ 2.6-1 Subsurface and Foundations ............................................................................. 2.7-1 Environmental Monitoring Program................................................................. 2.8-1 Environmental Radiation Monitoring Program ................................................ 2.9-1 APTER 3: REACTOR Table of Contents List of Tables List of Figures Summary Description ....................................................................................... 3.1-1 Design Bases..................................................................................................... 3.2-1 Mechanical Design ........................................................................................... 3.3-1 Nuclear Design and Evaluation ........................................................................ 3.4-1 Thermal-Hydraulic Design ............................................................................... 3.5-1 Analysis of Reactor Vessel Internals ............................................................... 3.A-1 APTER 4: REACTOR COOLANT SYSTEM Table of Contents List of Tables List of Figures General System Description ............................................................................. 4.1-1 Design Basis ..................................................................................................... 4.2-1 System Component Design............................................................................... 4.3-1 Materials Compatibility .................................................................................... 4.4-1 System Design Evaluation ................................................................................ 4.5-1 Tests and Inspections ........................................................................................ 4.6-1
tion Title Page Seismic Analysis of Reactor Coolant System.................................................. 4.A-1 APTER 5: STRUCTURES Table of Contents List of Tables List of Figures General.............................................................................................................. 5.1-1 Containment General Description .................................................................... 5.2-1 Enclosure Building ........................................................................................... 5.3-1 Auxiliary Building ............................................................................................ 5.4-1 Turbine Building............................................................................................... 5.5-1 Intake Structure................................................................................................. 5.6-1 External Class I Tanks ...................................................................................... 5.7-1 Seismic Design ................................................................................................. 5.8-1 Construction Practice and Quality Assurance .................................................. 5.9-1 Description of Finite Element Method Used in Containment Analysis .......... 5.A-1 Justification For Load Factors and Load Combinations Used in Design Equations of Containment .................................................................................................5.B-1 Justification For Capacity Reduction Factors () Used in Determining Capacity of Containment......................................................................................................5.C-1 Expanded Spectrum of Tornado Missiles ........................................................ 5.D-1 Computer Program List and Descriptions ........................................................5.E-1 1 Computer Program Applicability and Validation ..........................................5.E.1-1 2 Computer Program Test Problem Solutions ..................................................5.E.2-1 3 Computer Program Test Problem Similarities...............................................5.E.3-1 Containment Water Intrusion Into Tendon Gallery During Construction (1) ... 5.F-1
tion Title Page APTER 6: ENGINEERED SAFETY FEATURES SYSTEMS Table of Contents List of Tables List of Figures General.............................................................................................................. 6.1-1 Refueling Water Storage Tank and Containment Sump................................... 6.2-1 Safety Injection System .................................................................................... 6.3-1 Containment Spray System............................................................................... 6.4-1 Containment Air Recirculation and Cooling System ....................................... 6.5-1 Containment Post-Accident Hydrogen Control System ................................... 6.6-1 Enclosure Building Filtration System............................................................... 6.7-1 APTER 7: INSTRUMENTATION AND CONTROL Table of Contents List of Tables List of Figures Introduction....................................................................................................... 7.1-1 Reactor Protective System ................................................................................ 7.2-1 Engineered Safety Features Actuation System ................................................. 7.3-1 Regulating Systems........................................................................................... 7.4-1 Instrumentation System .................................................................................... 7.5-1 Operating Control Stations ............................................................................... 7.6-1 Control Room Annunciation............................................................................. 7.7-1 Communication Systems .................................................................................. 7.8-1 Anticipated Transients Without Scram Circuitry ............................................. 7.9-1
tion Title Page Auxiliary Steam Line Break Detection/isolation System ............................... 7.10-1 Environmental Qualification of Electrical Equipment Important to Safety ... 7.11-1 APTER 8: ELECTRICAL SYSTEMS Table of Contents List of Tables List of Figures Electrical Drawings Submitted to AEC for Review ......................................... 8.0-1 Electric Power................................................................................................... 8.1-1 4160-Volt and 6900-Volt Systems ................................................................... 8.2-1 Emergency Generators...................................................................................... 8.3-1 480 Volt System................................................................................................ 8.4-1 Battery System .................................................................................................. 8.5-1 Alternating Current Instrumentation and Control............................................. 8.6-1 Wire, Cable and Raceway Facilities ................................................................. 8.7-1 APTER 9: AUXILIARY SYSTEMS Table of Contents List of Tables List of Figures General.............................................................................................................. 9.1-1 Chemical and Volume Control System ............................................................ 9.2-1 Shutdown Cooling System................................................................................ 9.3-1 Reactor Building Closed Cooling Water System ............................................. 9.4-1 Spent Fuel Pool Cooling System ...................................................................... 9.5-1 Sampling System .............................................................................................. 9.6-1
tion Title Page Cooling Water Systems .................................................................................... 9.7-1 Fuel and Reactor Component Handling Equipment ......................................... 9.8-1 Plant Ventilation Systems ................................................................................. 9.9-1 Fire Protection System.................................................................................... 9.10-1 Compressed Air System.................................................................................. 9.11-1 Water Treatment System ................................................................................ 9.12-1 Auxiliary Steam System ................................................................................. 9.13-1 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 3 Main Steam Supply System ........................................................................... 10.3-1 Other Features of Steam and Power Conversion System ............................... 10.4-1 APTER 11: RADIOACTIVE WASTE PROCESSING AND RADIATION PROTECTION SYSTEMS Table of Contents List of Tables List of Figures Radioactive Waste Processing Systems.......................................................... 11.1-1 Radiation Protection ....................................................................................... 11.2-1 A Source Terms for Radioactive Waste Processing and Releases to the Environment 11.A-1 B Radioactive Waste Processing of Releases to Environment ...............................................................................................11.B-1
tion Title Page C Doses From Radioactive Releases and Cost-Benefit Analysis ..........................................................................................................11.C-1 D Expected Annual Inhalation Doses and Estimated Air Concentrations of Radioactive Isotopes for MP2 Facilities .......................... 11.D-1 E Airborne Activity Sampling System for Containment, Spent Fuel and Radwaste Atmospheres ...................................................................................................11.E-1 APTER 12: CONDUCT OF OPERATIONS Table of Contents Organizational Structure ................................................................................. 12.1-1 Training Program ............................................................................................ 12.2-1 Emergency Planning ....................................................................................... 12.3-1 Review and Audit ........................................................................................... 12.4-1 Plant Procedures ............................................................................................. 12.5-1 Records ........................................................................................................... 12.6-1 7 Physical Security Plans ................................................................................... 12.7-1 Quality Assurance Program ............................................................................ 12.8-1 Deleted by Pkg FSC MP2-UCR-2011-014..................................................... 12.9-1 APTER 13: INITIAL TESTS AND OPERATION Table of Contents List of Tables List of Figures Description of the Startup Test Program ........................................................ 13.1-1 Startup Test Program Organization and Responsibilities ............................................................................................... 13.2-1 Administrative Conduct of the Startup Test Program .................................... 13.3-1 Millstone Startup Group Training Program.................................................... 13.4-1
tion Title Page Initial Inspection and Component Testing Phase ........................................... 13.5-1 Preoperational and Acceptance Test Program ................................................ 13.6-1 Hot Functional Test Program.......................................................................... 13.7-1 Initial Fuel Loading ........................................................................................ 13.8-1 Initial Criticality.............................................................................................. 13.9-1 0 Low Power Physics Testing.......................................................................... 13.10-1 1 Power Ascension Testing.............................................................................. 13.11-1 2 Piping Operational Testing ........................................................................... 13.12-1 3 Active Valves Operational Testing............................................................... 13.13-1 A Preoperational Test Descriptions ................................................................... 13.A-1 APTER 14: SAFETY ANALYSIS Table of Contents List of Tables List of Figures General............................................................................................................ 14.0-1 Increase in Heat Removal By the Secondary System..................................... 14.1-1 Decrease in Heat Removal by the Secondary System .................................... 14.2-1 Decrease in Reactor Coolant System Flow..................................................... 14.3-1 Reactivity and Power Distribution Anomalies ............................................... 14.4-1 Increases in Reactor Coolant System Inventory ............................................. 14.5-1 Decreases in Reactor Coolant Inventory ........................................................ 14.6-1 Radioactive Releases From a Subsystem or Component................................ 14.7-1 Millstone Unit 2 FSAR Events Not Contained in the Standard Review Plan 14.8-1
tion Title Page APTER 15: LICENSE RENEWAL Table of Contents List of Tables Introduction..................................................................................................... 15.0-1 Overview of Aging Management Programs ................................................... 15.1-1 Programs That Manage The Effects of Aging on Structures and Components Within the Scope of License Renewal ................................ 15.2-1 Time-Limited Aging Analysis ........................................................................ 15.3-1 TLAA Support Programs................................................................................ 15.4-1 Exemptions ..................................................................................................... 15.5-1 6 License Renewal Commitments ..................................................................... 15.6-1
le 1.1-1 Licensing History le 1.2-1 Summary of Codes and Standards for Components of Water-Cooled Nuclear Power Units (1) le 1.3-1 Comparison with Other Plants le 1.4-1 Seismic Class I Systems and Components le 1.8-1 Comparison of Preoperational Vibration Monitoring Program Design Parameters le 1.9-1 Topical Reports le 2.3-1 Distances from Release Point to Receptors le 2.3-2 (Deleted) le 2.5-1 Effect of Hurricane Generated Surge and Waves on Unit Number 2 Structures le 2.5-2 Design Wave Conditions le 2.5-3 Roof Surface Area and Number and Size of Roof Drains le 2.5-4 All Catch Basins for Elevation Area Draining Into and Runoff Flowing In and Out of a Catch Basin le 3.2-1 Stress Limits for Reactor Vessel Internal Structures le 3.3-1 Mechanical Design Parameters
- le 3.3-2 Pressurized Water Reactor Primary Coolant Water Chemistry Recommended Specifications le 3.4-1 Fuel Characteristics for a Representative Reload Core le 3.4-2 Neutronics Characteristics for a Representative Reload Core le 3.4-3 Representative Shutdown Margin Requirements le 3.5-1 Nominal Reactor and Fuel Design Parameters le 3.5-2 Design Operating Hydraulic Loads on Vessel Internals le 3.5-3 Uncertainty Sources for DNBR Calculations (Deleted)
mber Title le 3.A-1 Natural Frequencies for Vertical Seismic Analysis Mathematical Model le 3.A-2 Seismic Stresses in Critical Reactor Internals Components for the Design Basis Earthquake le 4.1-1 Reactor Coolant System Volumes le 4.2-1 Principal Design Parameters of Reactor Coolant System le 4.2-2A Table of Loading Combinations and Primary Stress Limits le 4.2-2B Table of Loading Combinations and Primary Stress Limits for the Replace-ment Reactor Vessel Head and Replacement pressurizer le 4.2-3 Reactor Coolant System Code Requirements le 4.2-4 Comparison with Safety Guide 26 le 4.3-1 Reactor Vessel Parameters le 4.3-2 Steam Generator Parameters le 4.3-3 Main Steam Safety Valve Parameters le 4.3-4 Tech Pub Review PKG for T4.3-4Reactor Coolant Pump Parameters le 4.3-5 Reactor Coolant Piping Parameters le 4.3-6 Pressurizer Parameters le 4.3-7 Quench Tank Parameter le 4.3-8 Pressurizer Spray (RC-100E, RC-100F) Valve Parameters le 4.3-9 Power-Operated Relief Valve Isolation Valve Parameters (RC-403, RC-405) le 4.3-10 Pressurizer Power-Operated Relief Valve Parameters (RC-402, RC-404) le 4.3-11 Pressurizer Safety Valve Parameters (RC-200, RC-201) le 4.3-12 Active and Inactive Valves in the Reactor Coolant System Boundary le 4.4-1 Materials Exposed to Coolant
mber Title le 4.4-2 Reactor Coolant Chemistry le 4.5-1 Reactor Coolant System Component Nozzles, Nozzle Sizes and Nozzle Materials le 4.5-2 Reactor Coolant System Heatup and Cooldown Limits le 4.6-1 RTNDT Determination for Reactor Vessel Base Metal Millstone Unit Number 2 le 4.6-2 Charpy V-Notch and Drop Weight Test Values - Pressurizer Millstone Unit Number 2 le 4.6-3 Charpy V-notch and Drop Weight Test Values - Steam Generator le 4.6-4 Charpy V-notch Values - Piping le 4.6-5 Plate and Weld Metal Chemical Analysis le 4.6-6 Beltline Mechanical Test Properties - Reactor Vessel Surveillance Materials le 4.6-7 Tensile Test Properties - Reactor Vessel Surveillance Materials le 4.6-8 Summary of Specimens Provided for Each Exposure Location le 4.6-9 Capsule Removal Schedule le 4.6-10 Inspection of Reactor Coolant System Components During Fabrication and Construction le 4.6-11 Reactor Coolant System Inspection C-E Requirements le 4.6-12 Reactor Coolant System Inspection C-E Requirements (Continued) le 4.6-13 RTPTS Values at 54 EFPY le 4.6-14 Adjusted Reference Temperatures (ART) Projections le 4.A-1 Natural Frequencies and Dominant Degrees of Freedom le 4.A-2 Seismic Loads on Reactor Coolant System Components for Operational Basis Earthquake le 5.2-1 Containment Structure Analysis Summary
mber Title le 5.2-2 Containment Structure Analysis Summary - Dead Load, Initial Prestress and Live Load (D+KF+L) le 5.2-3 Containment Structure Analysis Summary - Dead Load, Initial Prestress and Live Load (D+F+L+1.15P) le 5.2-4 Containment Structure Analysis Summary - Dead Load, Initial Prestress and Live Load, Operating Temperature and OBE (D+F+L+T0+E) le 5.2-5 Containment Structure Analysis Summary - Dead Load, Prestress, Live Load, 100% Accident Pressure and Accident Temperature (D+F+L+1.0P+T1) le 5.2-6 Containment Structure Analysis Summary - Dead Load, Prestress, Operating Temperature, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE (D+F+T0+H+R+E1) le 5.2-6A Deleted by FSARCR 04-MP2-016 le 5.2-7 Containment Structure Analysis Summary - Dead Load, Prestress, 100%
Accident Pressure, Thermal Expansion Forces of Pipes, Pipe Rupture Forces and DBE (D+F+1.0P+H+T1+E1) le 5.2-8 Containment Structure Analysis Summary - Dead Load, Prestress, 125%
Accident Pressure, 125% Thermal Expansion Forces of Pipes, Accident Temperature and 125% DBE (D+F+1.25P+1.25H+T1+1.25E) le 5.2-9 Containment Structure Analysis Summary - Dead Load, Prestress, 150%
Accident Pressure, and Accident Temperature (D+F+1.5P+T1) le 5.2-10 Spectrum of Potential Missiles From Inside the Containment le 5.2-11 Containment Structure Isolation Valve Information le 5.2-12 Containment Penetration Piping le 5.2-13 Major(1) Containment Isolation Valves le 5.2-14 Typical Leak Rate Measurement System Instrumentation
mber Title le 5.2-15 Typical Containment Resistance Temperature Detectors and Dewcell Sensor Volume Weight Fractions le 5.5-1 Maximum Actual Stresses - Turbine Building le 5.8-1 Material Damping Values le 5.9-1 Aggregate Tests le 5.9-2 Cement Tests le 5.9-3 Fly Ash Tests le 5.9-4 Typical Chemical Analysis of Fly Ash Used le 5.9-5 Allowable Void Limits for Cadwelding le 5.D-1 Impactive Velocities (fps) of Missiles of Different CdA/W Factors as Picked from the Ground by the Design Tornado le 5.D-2 Kinetic Energy per Ft2 of Impact Area le 5.D-3 Radius vs. Velocity FPS/MPH (D=0.882 psi/V1 = 27 mph) le 5.D-4 Radius vs. Velocity FPS/MPH (D=3 psi/V1 = 60 mph) le 5.D-5 Velocities of Various Missiles le 5.D-6 Test Data Summary le 5.D.A-1A Relative Conservatism in Steps A, B, and C le 5.D.A-2A le 5.D.A-3A le 6.1-1 Pipe Rupture Protection Requirements le 6.1-2 Omitted le 6.1-3 Design Non-Seismic Category I Components Located Inside Containment and Enclosure Building
mber Title le 6.1-4 Pipe Rupture Criteria Applicability (Outside Containment) Based on Normal Operating Plant Conditions le 6.2-1 Refueling Water Storage Tank and Containment Sump le 6.3-1 Omitted le 6.3-2 Principal Design Parameters of the Safety Injection System le 6.3-3 Shutdown Cooling Heat Exchanger Data le 6.3-4 Omitted le 6.3-5 Internal Dimensions of Containment Sump Recirculation Piping and Valves le 6.3-6 Safety Injection System Failure Mode Analysis High Pressure Safety Injection le 6.3-7 Administrative Error Analysis-Safety Injection System Valves le 6.3-8 Failure Modes and Effects Analysis for Boron Precipitation Control le 6.4-1 Containment Spray System Component Design Parameters le 6.4-2 Containment Spray System Failure Mode Analysis le 6.5-1 Containment Air Recirculation and Cooling Units Materials of Construction le 6.5-2 Containment Air Recirculation and Cooling Units Performance Data le 6.5-3 Containment Air Recirculation and Cooling System le 6.6-1 Containment Post Accident Hydrogen Control Systems Component Description le 6.6-2 Deleted by FSARCR 04-MP2-018 le 6.6-3 Omitted le 6.6-4 Post-Incident Recirculation System Failure Mode Analysis le 6.7-1 Enclosure Building Filtration System Component Description le 6.7-2 Enclosure Building Filtration System Failure Mode Analysis
mber Title le 7.2-1 Reactor Trip and Pretrip Set Points le 7.2.1.1-I Parameters Affecting Fuel Design Limit le 7.2.1.1-II Pertinent NSSS parameters and Monitored Variables le 7.2.1.1-III Trip Functions le 7.2.1.1-IV Trip Variable Monitored le 7.3.2.2-1 ESAS Failure Mode Analysis for Containment Pressure Channels le 7.4-1 Prohibits on CEAs le 7.5-1 Major Process Instrumentation le 7.5-2 Omitted le 7.5-3 Regulatory Guide 1.97 (Rev. 2) Accident Monitoring Instrumentation le 7.5-4 Area Radiation Monitors le 7.5-5 Liquid Process/Effluent Radiation Monitors le 7.5-6 Airborne Process/Effluent Radiation Monitors le 7.5-6A Process Radiation Monitors (Steam) le 7.5-7 CEA Position Light Matrix le 7.6-1 Major Equipment Normally Used for Hot Shutdown le 7.6-2 Major Equipment Normally Used for Cold Shutdown le 8.3-1 Diesel Fuel Oil System Mode Analysis le 8.3-2 A Emergency Diesel Generator Loading le 8.3-3 B Emergency Diesel Generator Loading le 8.5-1 Battery Service Profile for Batteries 201A and 201B le 8.7-1 Cable Characteristics le 8.7-2 Omitted
mber Title le 8.7-3 Omitted le 8.7-4 Facility Identification le 9.2-1 Chemical and Volume Control System Parameters le 9.2-2 Reactor Coolant and Demineralized Water Chemistry le 9.2-3 Regenerative Heat Exchanger le 9.2-4 Letdown Control Valves le 9.2-5 Letdown Heat Exchanger le 9.2-6 Ion Exchangers le 9.2-7 Letdown Filters le 9.2-8 Volume Control Tank le 9.2-9 Charging Pumps le 9.2-10 Concentrated Boric Acid Preparation and Storage le 9.2-11 Boric Acid Pumps and Strainers le 9.3-1 Shutdown Cooling Heat Exchangers Design Basis Parameters le 9.3-2 Shutdown Cooling System Design Parameters le 9.4-1 Reactor Building Closed Cooling Water System Components le 9.4-2 Reactor Building Closed Cooling Water System Failure Mode Analysis le 9.4-3 Minimum Required RBCCW Flow to Essential Safety-Related Loads LOCA Injection and Recirculation Operations le 9.5-1 Spent Fuel Pool Monitoring Equipment le 9.5-2 Components of Spent Fuel Pool Cooling System le 9.7-1 Circulating Water System Components le 9.7-2 Service Water System Components
mber Title le 9.7-3 Turbine Building Closed Cooling Water System Components le 9.7-4 Service Water Cooling System le 9.8-1 Transfer Tube Isolation Valve le 9.8-2 Spent Fuel Pool Platform Crane le 9.8-3 Spent Fuel Cask Crane le 9.8-4 Failure Mode Analysis le 9.8-5 Radiation Levels from Heated Junction Thermocouple (R/Hr) le 9.9-1 Control Element Drive Mechanism Cooling System le 9.9-2 Containment and Enclosure Building Purge System le 9.9-3 Containment Auxiliary Circulation System le 9.9-4 Containment Penetration Cooling System le 9.9-5 Penetration Air Cooling Requirements le 9.9-6 Radwaste Ventilation System le 9.9-7 Nonradioactive Ventilation System le 9.9-8 Engineered Safety Features Room Air Recirculation System le 9.9-9 Fuel Handling Ventilation System le 9.9-10 Main Exhaust System le 9.9-11 Control Room Air Conditioning System le 9.9-12 Diesel Generator Ventilation Systems le 9.9-13 Turbine Building Ventilation System le 9.9-14 Access Control Area Air Conditioning System le 9.9-15 Balance of Unit Ventilation System
mber Title le 9.9-16 Engineered Safety Features Room Air Recirc. System Failure Mode Analysis le 9.9-17 Control Room Air Conditioning System Failure Mode Analysis le 9.9-18 Diesel Generator Ventilation System Failure Mode Analysis le 9.9-19 Vital Switchgear Ventilation System Component Description le 9.9-20 Auxiliary Chilled Water System Component Description le 9.9-21 Vital Chilled Water System Component Description le 9.9-22 Indoor Design Temperatures for Significant Plant Areas le 9.11-1 Compressed Air System Component Description le 9.11-2 Gas Receiver Tanks Safety Evaluation le 9.12-1 Water Treatment System Components le 10.1-1 Deleted le 10.2-1 Turbine Generator Component Description le 10.3-1 Major Components of Main Steam System le 10.3-2 Omitted le 10.3-3 Operating Details for Valve Systems Protecting Steam Generations of Overpressure le 10.4-1 Major Components of the Condensate and Feedwater System le 10.4-2 Failure Analysis of Steam Generator Blowdown System Components le 11.1-1 Radioactive Waste Processing System Component Description le 11.1-2 Sources and Expected Volumes of Solid Wastes le 11.1-3 Radioactivity levels of solid wastes (See Note) le 11.1-4 Curie Inventory of Solid Waste Shipped from Millstone Unit 2 (See Note)
mber Title le 11.1-5 Assumptions for Waste Gas Decay Tank Accident le 11.2-1 Source Terms for Shielding Design le 11.A-1 Design-Basis and Expected Primary Coolant Activity Concentrations le 11.A-2 Calculated Reactor Core Activities le 11.A-3 Expected Annual Effluent Releases (Curies Per Year), by Radionuclide, from Each Release Point le 11.A-4 Expected Annual Liquid Effluent Activity Releases (Curies/Year), by Radionuclide, from Each Waste Stream le 11.A-5 Expected Annual Liquid Effluent Concentrations (Diluted and Undiluted),
by Radionuclide, from Each Waste System le 11.A-6 Design Basis Radionuclide Concentrations in Liquid Effluent, in Fractions of 10 CFR Part 20 Concentration Limits le 11.A-7 Design-Basis Radionuclide Airborne Concentrations at the Site Boundary From All Gaseous Effluent Release Points Combined, in Fractions of 10 CFR Part 20 Concentration Limits le 11.A-8 Total Annual Design-Basis and Expected Releases of Radioactive Liquid Waste to the Environment From All Sources Combined, in Curies Per Year le 11.A-9 Total Annual Design Basis and Expected Releases of Airborne Radioactive Waste to the Environment From All Release Points Combined, in Curies Per Year le 11.A-10 Basis for Reactor Coolant System Activity NUREG-0017 gale Code Input le 11.B-1 Inputs to PWR-GALE Code le 11.C-1 Comparison of Calculated Annual Maximum Individual Doses with 10 CFR Part 50 Appendix I Design Objectives le 11.C-2 Annual Total Body and Thyroid Doses to the Population Within 50 Miles of the Millstone Site, In Man-Rem, From Expected Liquid and Airborne Effluent Releases
mber Title le 11.D-1 Containment Building Airborne Concentrations le 11.D-2 Auxiliary Building Airborne Concentrations le 11.D-3 Turbine Building Airborne Concentrations le 13.12-1 Seismic Category I-ASME Section III Classes 1 and 2 Piping Systems le 14.0-1 Reactor Operating Modes For Millstone Unit 2 le 14.0-2 Disposition of Events Summary le 14.0.1-1 Accident Category Used For Each Analyzed Event le 14.0.2-1 Plant Operating Conditions le 14.0.2-2 Nominal Fuel Design Parameters le 14.0.3-1 Core Power Distribution (Table Deleted) le 14.0.4-1 Range of Key Initial Condition Operating Parameters le 14.0.5-1 Reactivity Parameters (Table Deleted) le 14.0.7-1 Analytical Trip Setpoints le 14.0.7-2 Uncertainties Applied at HFP Condition in Local Power Density Limiting Safety System Settings Calculations le 14.0.7-3 Uncertainties Applied at HFP Condition in the Thermal Margin/Low Pressure Limiting Safety System Settings Calculations le 14.0.7-4 Uncertainties Applied at HFP Condition in the Local Power Density Limiting Condition for Operation Calculations le 14.0.7-5 Uncertainties Applied in Departure from Nucleate Boiling Limiting Condition for Operation Calculations le 14.0.8-1 Component Capacities and Setpoints le 14.0.9-1 Overview of Plant Systems and Equipment Available for Transient and Accident Conditions le 14.0.12-1 Nomenclature Used in Plotted Results
mber Title le 14.1.1-1 Available Reactor Protection for the Decrease in Feedwater Temperature Event le 14.1.1-2 Disposition of Events for the Decrease in Feedwater Temperature Event le 14.1.2-1 Available Reactor Protection for the Increase in Feedwater Flow Event le 14.1.2-2 Disposition of Events for the Increase in Feedwater Flow Event le 14.1.3-1 Available Reactor Protection for the Increase in Steam Flow Event le 14.1.3-2 Disposition of Events for the Increase in Steam Flow Event le 14.1.3-3 Initial Conditions for the Increase in Steam Flow Event le 14.1.3-4 Event Summary for the Increase in Steam Flow Event le 14.1.3-5 Peak Reactor Power Levels for Increase in Steam Flow Event le 14.1.4-1 Available Reactor Protection for the Inadvertent Opening of a Steam Generator Relief or Safety Valves le 14.1.4-2 Disposition of Events for the Inadvertent Opening of a Steam Generator Relief or Safety Valve Event le 14.1.5.1-1 Available Reactor Protection for Steam System Piping Failures Inside and Outside of Containment le 14.1.5.1-2 Disposition of Events for Steam System Piping Failures Inside and Outside Containment le 14.1.5.1-3 S-RELAP5 Thermal-Hydraulic Input (Pre-Scram Steam Line Break) le 14.1.5.1-4 Actuation Signals and Delays (Pre-Scram Steam Line Break) le 14.1.5.1-5 S-RELAP5 Neutronics Input and Assumptions (Pre-Scram Steam Line Break) le 14.1.5.1-6 MDNBR and Peak Reactor Power Level Summary (Pre-Scram Steam Line Break) le 14.1.5.1-7 LHGR-Limiting Pre-Scram Steam Line Break Sequence of Events: HFP 0.20ft2 Asymmetric Break Inside Containment with Offsite Power Available
mber Title le 14.1.5.1-8 MDNBR-Limiting Pre-Scram Steam Line Break Sequence of Events: HFP 3.51ft2 Asymmetric Break Inside Containment with Loss of Offsite Power le 14.1.5.2-1 Available Reactor Protection for Steam System Piping Failures Inside and Outside of Containment, Post-Scram Analysis le 14.1.5.2-2 Disposition of Events for Steam System Piping Failures Inside and Outside of Containment, Post-Scram Analysis le 14.1.5.2-3 SRELAP5 -Thermal-Hydraulic Input (Post-Scram Steam Line Break) le 14.1.5.2-4 Actuation Signals and Delays (Post-Scram Steam Line Break) le 14.1.5.2-5 S-RELAP5 Neutronics Input and Assumptions (Post-Scram Steam Line Break) le 14.1.5.2-6 Post-Scram Steam Line Break Analysis Summary le 14.1.5.2-7 LHGR-Limiting Sequence of Events - HZP Offsite Power Available le 14.1.5.2-8 MDNBR-Limiting Post-Scram Steam Line Break Analysis Summary le 14.1.5.3-1 Assumptions Used in Main Steam Line Break Analysis le 14.1.5.3-2 Summary of Millstone 2 MSLB Accident Doses le 14.1.5.3-3 Deleted by FSARCR PKG FSC 07-MP2-006 le 14.2.1-1 Available Reactor for the Loss of External Load Event le 14.2.1-2 Disposition of Events for the Loss of External Load Event le 14.2.1-3 Event Summary for the Loss of External Load Event (Primary Overpressurization Case) le 14.2.1-4 Event Summary for the Loss of External Load Event (Secondary Overpressurization Case) le 14.2.1-5 Event Summary for the Loss of External Load Event (Minimum Departure from Nucleate Boiling Ratio Case) le 14.2.2-1 Available Reactor Protection for the Turbine Trip Event le 14.2.2-2 Disposition of Events for the Turbine Trip Event
mber Title le 14.2.4-1 Available Reactor Protection for the Closure of the Main Steam Isolation Valves Events le 14.2.4-2 Disposition of Events for the Closure of the Main Steam Isolation Valves Events le 14.2.4-3 Event Summary for the Main Steam Isolation Valve Closure Event (Lower Steam Flow Case) le 14.2.7-1 Available Reactor Protection for the Loss of Normal Feedwater Flow Event le 14.2.7-2 Disposition of Events for the Loss of Normal Feedwater Flow Event le 14.2.7-3 Sequence of Events for Minimum Steam Generator Inventory Case: One Motor-Driven AFW Pump Fails to Start with Offsite Power and Steam Dumps le 14.2.7-4 Sequence of Events for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails to Start le 14.3.1-1 Available Reactor Protection for the Loss of Forced Reactor Coolant Flow Event le 14.3.1-2 Disposition of Events for the Loss of Forced Reactor Coolant Flow Event le 14.3.1-3 Event Summary for the Loss of Forced Reactor Coolant Flow le 14.3.3-1 Available Reactor Protection for the Reactor Coolant Pump Rotor Seizure Event le 14.3.3-2 Disposition of Events for the Reactor Coolant Pump Rotor Seizure Event le 14.3.3-3 Event Summary for the Reactor Coolant Pump Rotor Seizure le 14.4.1-1 Available Reactor Protection for the Uncontrolled Control Rod/Bank Withdrawal from a Subcritical or Low-Power Startup Condition Event le 14.4.1-2 Disposition of Events for the Uncontrolled Control Rod/Bank Withdrawal from a Subcritical or Low-Power Startup Condition Event le 14.4.1-3 Event Summary for the Uncontrolled Bank Withdrawal from Low-Power Event
mber Title le 14.4.2-1 Available Reactor Protection for the Uncontrolled Control Rod/Bank Withdrawal at Power Event le 14.4.2-2 Disposition of Events for the Uncontrolled Control Rod/Bank Withdrawal at Power Event le 14.4.2-3 Event Summary for the Uncontrolled Rod/Bank Withdrawal Event for the Limiting 100% Power Case le 14.4.3.1-1 Available Reactor Protection for the Dropped Control Rod/Bank Event le 14.4.3.1-2 Disposition of Events for the Dropped Control Rod/Bank Event le 14.4.3.1-3 Event Summary for the Limiting Dropped Control Rod/Bank Case le 14.4.3.5-1 Available Reactor Protection for the Single Control Rod Withdrawal Event le 14.4.3.5-2 Disposition of Events for the Single Control Rod Withdrawal Event le 14.4.4-1 Available Reactor Protection le 14.4.4-2 Disposition of Events for the Startup of an Inactive Loop Event le 14.4.6-1 Available Reactor Protection for Chemical and Volume Control System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant Event le 14.4.6-2 Disposition of Events for the Chemical and Volume Control System Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant Event le 14.4.6-3 Summary of Results for the Boron Dilution Event Asymmetric Dilution Front Model le 14.4.6-4 Summary of Results for the Boron Dilution Event Instantaneous Mixing Mode le 14.4.8-1 Available Reactor Protection for the Spectrum of Control Rod Ejection Accidents le 14.4.8-2 Disposition of Events for the Spectrum of Control Rod Ejection Accidents le 14.4.8-3 Event Summary for a Control Rod Ejection (Maximum Pressurization Case)
mber Title le 14.4.8-4 Event Summary for a Control Rod Ejection Minimum Departure from Nucleate Boiling Ratio Case le 14.4.8-5 dnBounding Beginning of Cycle/End of Cycle Ejected Rod Analysis le 14.4.8-6 CREA Radiological Analysis Assumptions le 14.4.8-7 Radiological Consequences of a CREA le 14.6.1-1 Available Reactor Protection for the Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve Event le 14.6.1-2 Disposition of Events for the Inadvertent Opening of a Pressurized Water Reactor Pressurizer Relief Valve Event le 14.6.1-3 Event Summary for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve le 14.6.3-1 Available Reactor Protection for the Radiological Consequences of Steam Generator Tube Rupture Event le 14.6.3-2 Disposition of Events for the Radiological Consequences of Steam Generator Tube Rupture Event le 14.6.3-3 Sequence of Events for the Steam Generator Tube Rupture Event le 14.6.3-4 Mass Releases for the Steam Generator Tube Rupture Accident le 14.6.3-5 Assumptions for the Radiological Evaluation for the Steam Generator Tube Rupture Event le 14.6.3-6 Summary - Radiological Consequences of the Steam Generator Tube Rupture Event le 14.6.5.1-1 Available Reactor Protection for the Large Break Loss of Coolant Accident le 14.6.5.1-2 Disposition of Events for the Large Break Loss of Coolant Accident le 14.6.5.1-3 Millstone Unit 2 Realistic Large Break Loss of Coolant Accident Analysis
- Plant Parameter Values and Ranges le 14.6.5.1-4 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis -
Statistical Distribution Used for Process Parameters
mber Title le 14.6.5.1-5 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis - Passive Heat Sinks and Material Properties In Containment Geometry le 14.6.5.1-6 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis -
Compliance with 10 CFR 50.46(b) le 14.6.5.1-7 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis -
Summary of Major Parameters for the Demonstration Case le 14.6.5.1-8 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis -
Calculated Event Times for the Demonstration Case*
le 14.6.5.2-1 Available Reactor Protection for the Small Break Loss of Coolant Accident le 14.6.5.2-2 Disposition of Events for the Small Break Loss of Coolant Accident le 14.6.5.2-3 Millstone Unit 2 Small Break Loss of Coolant Accident System Analysis Parameters le 14.6.5.2-4 Deleted by FSCR MPS-UCR-2016-016 le 14.6.5.2-5 Calculated Event Times for Small Break Loss-of-Coolant Accident le 14.6.5.2-6 Analysis Results for Small Break Loss-of-Coolant Accident le 14.6.5.2-7 Peak Clad Temperature Including All Penalties and Benefits - Small Break LOCA le 14.6.5.3-1 Core and System Parameters Used in the LTC Analysis le 14.6.5.4-1 Available Reactor Protection for the Large Break Loss of Coolant Accident le 14.6.5.4-2 Disposition of Events for the Large Break Loss of Coolant Accident le 14.6.5.4-3 Millstone Unit 2 System Analysis Parameters (Large Break Loss of Coolant Accident Analysis) le 14.6.5.4-4 Millstone Unit 2 Large Break Loss of Coolant Accident Analysis le 14.6.5.4-5 Millstone Unit 2 Large Break LOCA Analysis le 14.6.5.4-6 Millstone Unit 2 Large Break LOCA Analysis
mber Title le 14.6.5.4-7 Peak Clad Temperature Including All Penalties and Benefits - Large Break LOCA le 14.7.1-1 Deleted by FSARCR PKG FSC 07-MP2-006 le 14.7.4-1 Assumption for Fuel Handling Accident in the Spent Fuel Pool le 14.7.4-2 Assumption for Fuel Handling Accident in Containment le 14.7.4-3 Deleted by FSARCR 02-MP2-015 le 14.7.5-1 Assumptions for Spent Fuel Cask Tip Accident le 14.8.2-1 Containment Design Parameters le 14.8.2-2 Initial Conditions for Pressure Analyses le 14.8.2-3 Minimum Containment Heat Sink Data le 14.8.2-4 Sequence of Events, MP2-MSLB: Loss of Offsite Power and the Failure of Vital Bus VA-10 or VA-20 from 102% Power le 14.8.2-5 Engineered Safety Features Performance for MSLB Containment Analysis le 14.8.4-1 Loss of Coolant Accident (Off site Assumptions) le 14.8.4-2 Summary of Doses for Loss of Coolant Accident le 14.8.4-3 Loss of Coolant Accident (Control Room Assumptions) le 14.8.4-4 Atmospheric Dispersion Data for Millstone Unit 2 Control Room le 14.8.4-5 Dose to Millstone Unit 2 Control Room Operators le 15.3-1 Containment Tendon Prestress le 15.6-1 License Renewal Commitments
Figure Number Figure Label Title Drawing Number She 1.2-1 FIGURE 1.2-1 Site Layout N/A 1.2-2 FIGURE 1.2-2 Plot Plan 25203-10003 (a) 1.2-3 FIGURE 1.2-3 General Arrangement, Turbine Building Plan at Operating Floor Elevation 54 Feet 6 Inches 25203-27011 (a) 1.2-5 FIGURE 1.2-5 General Arrangement, Turbine Building Plan at Ground Floor Elevation 14 Feet 6 Inches 25203-27012 (a) 1.2-5 FIGURE 1.2-5 General Arrangement, Turbine Building Plan at Ground Floor Elevation 14 Feet 6 Inches 25203-27013 (a) 1.2-6 FIGURE 1.2-6 General Arrangement Containment Plan at Floor Elevation 14 feet 6 inches and Elevation 36 feet 6 inches 25203-27014 (a) 1.2-7 FIGURE 1.2-7 General Arrangement Auxiliary Building Plan at Elevation 36 feet 6 inches and Elevation 38 feet 6 inches 25203-27015 (a) 1.2-8 FIGURE 1.2-8 General Arrangement Auxiliary Building Sections G-G and H-H 25203-27016 (a) 1.2-9 FIGURE 1.2-9 General Arrangement Auxiliary Building Ground Floor Elevation 14 feet 6 inches and Cable Vault Elevation 25 feet 6 inches 25203-27017 (a) 1.2-10 FIGURE 1.2-10 General Arrangement Containment and Auxiliary Building Plan at Elevation (-)5 feet 0 inches and Elevation (-)3 feet 6 inches 25203-27018 (a) 1.2-11 FIGURE 1.2-11 General Arrangement Containment and Auxiliary Building Plan at Elevation (-)25 feet 6 inches and Elevation (-)22 feet 6 inches 25203-27019 (a) 1.2-12 FIGURE 1.2-12 General Arrangement Containment and Auxiliary Building Plan at Elevation (-)45 feet 6 inches 25203-27020 (a) 1.2-13 FIGURE 1.2-13 General Arrangement Containment and Auxiliary Building Section A-A 25203-27021 (a)
Figure Number Figure Label Title Drawing Number She 1.2-14 FIGURE 1.2-14 General Arrangement Containment and Auxiliary Building Section B-B 25203-27022 (a) 1.2-15 FIGURE 1.2-15 General Arrangement Turbine Building Sections C-C and E-E 25203-27023 (a) 1.2-16 FIGURE 1.2-16 General Arrangement Turbine Building Sections D-D and F-F 25203-27024 (a) 1.2-17 FIGURE 1.2-17 General Arrangement Intake Structure Auxiliary Steam Boiler Room Plan and Section 25203-27025 (a) 2.4-1 FIGURE 2.4-1 Geological Features N/A 2.4-2a FIGURE 2.4-2a Boring Plan N/A 2.4-2b FIGURE 2.4-2b Test Borings N/A 2.4-2c FIGURE 2.4-2c Boring Logs N/A 2.4-2d FIGURE 2.4-2d Boring Logs N/A 2.4-3 FIGURE 2.4-3 Seismic Line Location Map N/A 2.4-4 FIGURE 2.4-4 Seismic Profiles N/A 2.5-1 FIGURE 2.5-1 Topography in the Vicinity of Millstone Point N/A 2.5-2 FIGURE 2.5-2 Bore Hole and Test Pit Locations N/A 2.5-3 FIGURE 2.5-3 Test Pit Number 1 N/A 2.5-4 FIGURE 2.5-4 Test Pit Number 2 N/A 2.5-5 FIGURE 2.5-5 Relationship Between Hurricane Wind Direction and Plant N/A Layout 2.5-6 FIGURE 2.5-6 Section Through Plant N/A 2.5-7 FIGURE 2.5-7 Profiles of Plant N/A
Figure Number Figure Label Title Drawing Number She 2.5-8 FIGURE 2.5-8 Surge Hydrograph for PMH N/A 2.5-9 FIGURE 2.5-9 Bottom Profile for Surge Traverse Line N/A 2.5-10 FIGURE 2.5-10 Storm Tracker for Probable Maximum Hurricane N/A 2.5-11 FIGURE 2.5-11 Location of the Center of the Storm Within the Critical Area N/A 2.5-12 FIGURE 2.5-12 Shore Protection N/A 2.5-13 FIGURE 2.5-13 Shore Protection N/A 2.5-14 FIGURE 2.5-14 Wave Force Diagrams For The Three Zones And Their N/A Corresponding Bottom Profiles Near The Walls 2.5-15 FIGURE 2.5-15 Typical Anchorage Detail N/A 2.5-16 FIGURE 2.5-16 Filter System and the Gradation of the Filter Materials N/A 2.5-17 FIGURE 2.5-17 Scour Protection N/A 2.5-18 FIGURE 2.5-18 Flood Protection N/A 2.5-19 FIGURE 2.5-19 General Roof Plan N/A 2.5-20 FIGURE 2.5-20 Drainage Plan N/A 2.5-21 FIGURE 2.5-21 Turbine and Auxiliary Building Plans at Elevation 14 Feet N/A 6 Inches 2.5-22 FIGURE 2.5-22 Auxiliary Building Basement Plans N/A 2.5-23 FIGURE 2.5-23 Intake Structure N/A 2.5-24 FIGURE 2.5-24 Louver Protection - Intake Structure N/A 2.7-1 FIGURE 2.7-1 Excavation Plan N/A 2.7-2 FIGURE 2.7-2 Backfill and Compaction Requirements N/A 3.1-1 FIGURE 3.1-1 Reactor Vertical Arrangement N/A
Figure Number Figure Label Title Drawing Number She 3.1-2 FIGURE 3.1-2 Reactor Core Cross Section N/A 3.3-1A FIGURE 3.3-1A Fuel Rod Assembly (Batch DD and Prior) N/A 3.3-2A FIGURE 3.3-2A AREVA - Reload Fuel Assembly Batch S and Prior N/A 3.3-2B FIGURE 3.3-2B AREVA - Reload Fuel Assembly Batch T and Later N/A 3.3-3A FIGURE 3.3-3A AREVA - Reload Fuel Assembly Components Batch S and N/A Prior 3.3-3B FIGURE 3.3-3B AREVA - Reload Fuel Assembly Components Batch T and N/A Later 3.3-4A FIGURE 3.3-4A Bi-Metallic Fuel Spacer Assembly N/A 3.3-4B FIGURE 3.3-4B HTP Fuel Space Assembly N/A 3.3-5 FIGURE 3.3-5 Fuel Assembly Hold Down Device N/A 3.3-6 FIGURE 3.3-6 Control Element Assembly N/A 3.3-7 FIGURE 3.3-7 Control Element Assembly Materials N/A 3.3-8 FIGURE 3.3-8 Control Element Assemblies Group and Number Designation N/A 3.3-9 FIGURE 3.3-9 Core Orientation N/A 3.3-11 FIGURE 3.3-11 Reactor Internals Assembly N/A 3.3-12 FIGURE 3.3-12 Pressure Vessel-Core Support Barrel Snubber Assembly N/A 3.3-13 FIGURE 3.3-13 Core Shroud Assembly N/A 3.3-14 FIGURE 3.3-14 Upper Guide Structure Assembly N/A 3.3-15 FIGURE 3.3-15 Control Element Drive Mechanism (Magnetic Jack) N/A 3.3-16 FIGURE 3.3-16 (Left Blank Intentionally) N/A 3.3-17 FIGURE 3.3-17 Heated Junction Thermocouple Probe Pressure Boundary N/A Installation
Figure Number Figure Label Title Drawing Number She 3.3-18 FIGURE 3.3-18 Typical Heated Junction Thermocouple Probe Assembly N/A Installation 3.3-19 FIGURE 3.3-19 Placement of Natural Uranium Replacement Fuel Rods and Fuel N/A Assembly Orientation Relative to the Core Baffle for Cycle 19 3.4-1 FIGURE 3.4-1 Representative Full Core Loading Pattern N/A 3.4-2 FIGURE 3.4-2 Representative Quarter Core Loading Pattern N/A 3.4-3 FIGURE 3.4-3 Representative BOC and EOC Exposure Distribution N/A 3.4-4 FIGURE 3.4-4 Representative Boron Letdown, HFP, ARO N/A 3.4-5 FIGURE 3.4-5 Representative Normalized Power Distributions, Hot Full Power, N/A Equilibrium Xenon, 150 MWD/MTU 3.4-6 FIGURE 3.4-6 Representative Normalized Power Distribution, Hot Full Power, N/A Equilibrium Xenon, 18,020 MWD/MTU 3.A-1 FIGURE 3.A-1 Representative Node Locations - Horizontal Mathematical Model N/A 3.A-2 FIGURE 3.A-2 Mathematical Model - Horizontal Seismic Analysis N/A 3.A-3 FIGURE 3.A-3 Mathematical Model - Vertical Seismic Analysis N/A 3.A-4 FIGURE 3.A-4 Core Support Barrel Upper Flange - Finite Element Model N/A 3.A-5 FIGURE 3.A-5 Core Support Barrel Lower Flange - Finite Element Model N/A 3.A-6 FIGURE 3.A-6 Lateral Seismic Model - Mode 1, 3.065 CPS N/A 3.A-7 FIGURE 3.A-7 Lateral Seismic Model - Mode 2, 5.118 CPS N/A 3.A-8 FIGURE 3.A-8 Lateral Seismic Model - Mode 2, 5.118 CPS N/A 3.A-9 FIGURE 3.A-9 Reactor Vessel Flange Vertical Response Spectrum (1%
N/A Damping) 3.A-10 FIGURE 3.A-10 ASHSD Finite Element Model of the Core Support Barrel/
N/A Thermal Shield System
Figure Number Figure Label Title Drawing Number She 3.A-11 FIGURE 3.A-11 Vertical Shock Model N/A 3.A-12 FIGURE 3.A-12 Lateral Shock Mode N/A 3.A-13 FIGURE 3.A-13 SAMMSOR DYNASOR Finite Element Model of Core Support N/A Barrel 4.1-1 FIGURE 4.1-1 P&ID for Reactor Coolant System & Pump (Sheet 1) 25203-26014 (a) Sheet 1 4.1-1 FIGURE 4.1-1 P&ID for Reactor Coolant System & Pump (Sheet 2) 25203-26014 (a) Sheet 2 4.1-1 FIGURE 4.1-1 P&ID for Reactor Coolant System & Pump (Sheets 3) 25203-26014 (a) Sheet 3 4.1-2 FIGURE 4.1-2 Reactor Coolant System Arrangement-Elevation N/A 4.1-3 FIGURE 4.1-3 Reactor Coolant System Arrangement-Plan N/A 4.3-1 FIGURE 4.3-1 Reactor Vessel N/A 4.3-2 FIGURE 4.3-2 Steam Generator N/A 4.3-3 FIGURE 4.3-3 Reactor Coolant Pump N/A 4.3-4 FIGURE 4.3-4 P&ID Reactor Coolant Pump 25203-26014 (a) Sheet 3 4.3-5 FIGURE 4.3-5 Reactor Coolant Pump Seal Area N/A 4.3-6 FIGURE 4.3-6 Reactor Coolant Pump Predicted Performance N/A 4.3-7 FIGURE 4.3-7 Pressurizer N/A 4.3-8 FIGURE 4.3-8 Temperature Control Program N/A 4.3-9 FIGURE 4.3-9 Pressurizer Level Setpoint Program N/A 4.3-10 FIGURE 4.3-10 Pressurizer Level Control Program N/A 4.3-11 FIGURE 4.3-11 Quench Tank N/A 4.3-12 FIGURE 4.3-12 Permanent Reactor Cavity Seal Plate N/A
Figure Number Figure Label Title Drawing Number She 4.5-1 FIGURE 4.5-1 Reactor Coolant System Pressure Temperature Limitations for 7 N/A Full Power Years 4.5-2 FIGURE 4.5-2 Reactor Coolant System Pressure - Temp Limitations During N/A Plant Heatup/Cooldown After 7 Years Integrated Neutron Flux 4.5-3 FIGURE 4.5-3 Reactor Coolant System Pressure Temperature Limitations For 0 N/A to 2 Years of Full Power 4.5-4 FIGURE 4.5-4 Reactor Coolant System Heatup Limitations for 54 EFPY N/A 4.5-5 FIGURE 4.5-5 Reactor Coolant System Cooldown Limitations for 54 EFPY N/A 4.6-1 FIGURE 4.6-1 Location of Surveillance Capsule Assemblies N/A 4.6-2 FIGURE 4.6-2 Typical Surveillance Capsule Assembly N/A 4.6-3 FIGURE 4.6-3 Typical Charpy Impact Compartment Assembly N/A 4.6-4 FIGURE 4.6-4 Typical Tensile-Monitor Compartment Assembly N/A 4.6-5 FIGURE 4.6-5 Base Metal - WR (Transverse) Plate C-506-1 Impact Energy vs N/A Temperature 4.6-6 FIGURE 4.6-6 Base Metal - WR (Transverse) Plate C-506-1 Lateral Expansion N/A versus Temperature 4.6-7 FIGURE 4.6-7 Base Metal - RW (Longitudinal) Plate C-506-1 Impact Energy N/A versus Temperature 4.6-8 FIGURE 4.6-8 Base Metal - RW (Longitudinal) Plate C-506-1 Lateral Expansion N/A vs Temperature 4.6-9 FIGURE 4.6-9 Weld Metal Plate C-506-2/C-506-3 Impact Energy vs N/A Temperature 4.6-10 FIGURE 4.6-10 Weld Metal, Plate C-506-2/C-506-3 Lateral Expansion vs N/A Temperature 4.6-11 FIGURE 4.6-11 HAZ Metal, Plate C-506-1 Impact Energy versus Temperature N/A
Figure Number Figure Label Title Drawing Number She 4.6-12 FIGURE 4.6-12 HAZ Metal, Plate C-506-1 Lateral Expansion versus Temperature N/A 4.6-13 FIGURE 4.6-13 SRM (HSST Plate 01MY - Longitudinal) Impact Energy versus N/A Temperature 4.6-14 FIGURE 4.6-14 SRM (HSST Plate 01MY - Longitudinal) Lateral Expansion N/A versus Temperature 4.A-1 FIGURE 4.A-1 Reactor Coolant System Seismic Analysis Model MS2 N/A 4.A-1A FIGURE 4.A-1A Reactor Coolant System - Seismic Analysis Model MS2 and N/A RV14 4.A-2 FIGURE 4.A-2 RV14 Reactor and Internals Seismic Analysis Model N/A 4.A-3 FIGURE 4.A-3 Pressurizer Seismic Analysis Model N/A 4.A-4 FIGURE 4.A-4 Surge Line Seismic Analysis Model N/A 5.2-1 FIGURE 5.2-1 Containment Structure Details N/A 5.2-2 FIGURE 5.2-2 Containment Structure Details N/A 5.2-3 FIGURE 5.2-3 Design Thermal Gradient N/A 5.2-4 FIGURE 5.2-4 Equipment Hatch Details N/A 5.2-5 FIGURE 5.2-5 Personnel Lock Details N/A 5.2-6 FIGURE 5.2-6 Liner Plate N/A 5.2-7 FIGURE 5.2-7 Leak Chase Channels N/A 5.2-8 FIGURE 5.2-8 Typical Penetrations N/A 5.2-9 FIGURE 5.2-9 Bracket Details N/A 5.2-10 FIGURE 5.2-10 Liner Plate Details N/A 5.2-11 FIGURE 5.2-11 Reactor Vessel Support Details N/A 5.2-12 FIGURE 5.2-12 Lower Steam Generator Support Details N/A
Figure Number Figure Label Title Drawing Number She 5.2-13 FIGURE 5.2-13 Upper Steam Generator Support Details N/A 5.2-14 FIGURE 5.2-14 Primary and Secondary Shield Wall N/A 5.2-15 FIGURE 5.2-15 Detail - Seismic Restraint N/A 5.2-16 FIGURE 5.2-16 Finite Element Mesh of Bottom of Containment Shell N/A 5.2-17 FIGURE 5.2-17 Finite Element Mesh of Top of Containment Shell N/A 5.2-18 FIGURE 5.2-18 Finite Element Mesh of Containment Shell for Stressing N/A Sequence 5.2-19 FIGURE 5.2-19 Containment Structure Stress Analysis Summary, Dead Load and N/A Initial Prestress, Live Load 5.2-20 FIGURE 5.2-20 Containment Structure Stress Analysis Summary, Dead Load, N/A Live Load, Prestress and Test Pressure 5.2-21 FIGURE 5.2-21 Containment Structure Stress Analysis Summary, Dead Load, N/A Live Load, Prestress, Operating Temperature and DBE 5.2-22 FIGURE 5.2-22 Containment Structure Stress Analysis Summary, Dead Load, Live Load, Prestress, 100% Accident Pressure and Accident N/A Temperature 5.2-23 FIGURE 5.2-23 Containment Structure Stress Analysis Summary, Dead Load, Prestress, Operating Temperature, Thermal Expansion Forces of N/A Pipes, Pipe Rupture Forces and DBE 5.2-24 FIGURE 5.2-24 Containment Structure Stress Analysis Summary, Dead Load, Prestress, 100% Accident Pressure, Thermal Expansion Forces of N/A Pipes, Accident Temperature and DBE 5.2-25 FIGURE 5.2-25 Containment Structure Stress Analysis Summary, Dead Load, Prestress, 125% Accident Pressure, 125% Thermal Expansion N/A Forces of Pipes, Accident Temperature and 125% OBE
Figure Number Figure Label Title Drawing Number She 5.2-26 FIGURE 5.2-26 Containment and Structure Stress Analysis Summary, Dead Load, N/A Prestress, 150% Accident Pressure and Accident Temperature 5.2-27 FIGURE 5.2-27 Isolation Valve Arrangements N/A 5.2-28 FIGURE 5.2-28 Isolation Valve Arrangements N/A 5.2-29 FIGURE 5.2-29 Isolation Valve Arrangements N/A 5.2-30 FIGURE 5.2-30 Isolation Valve Arrangements N/A 5.2-31 FIGURE 5.2-31 Isolation Valve Arrangements N/A 5.2-32 FIGURE 5.2-32 Isolation Valve Arrangements N/A 5.2-33 FIGURE 5.2-33 Isolation Valve Arrangements N/A 5.2-34 FIGURE 5.2-34 Isolation Valve Arrangements N/A 5.2-35 FIGURE 5.2-35 Reactor Coolant System Plan N/A 5.2-36 FIGURE 5.2-36 Reactor Coolant System Elevation N/A 5.2-37 FIGURE 5.2-37 Deleted by FSARCR 04-MP2-016 N/A 5.3-1 FIGURE 5.3-1 Enclosure Building N/A 5.3-2 FIGURE 5.3-2 Enclosure Building Layout N/A 5.3-3 FIGURE 5.3-3 Waterproof Membrane Details N/A 5.3-4 FIGURE 5.3-4 Waterproof Membrane Details N/A 5.3-5 FIGURE 5.3-5 Spent Fuel Cask Travel Limits N/A 5.4-1 FIGURE 5.4-1 Probable Missile Trajectories Inside Auxiliary Building N/A 5.4-2 FIGURE 5.4-2 Missile Resistant Siding Detail N/A 5.4-3 FIGURE 5.4-3 Location of Missile Resistant Siding N/A 5.5-1 FIGURE 5.5-1 Joint Detail at Turbine Pedestal N/A
Figure Number Figure Label Title Drawing Number She 5.5-2 FIGURE 5.5-2 Joint Detail at Col. Line E N/A 5.6-1 FIGURE 5.6-1 Intake Structure Layout N/A 5.6-2 FIGURE 5.6-2 C. W. System - Plan N/A 5.8-1 FIGURE 5.8-1 Recommended Damped Response Spectra 9%g Acceleration, N/A Operating Basis Earthquake 5.8-2 FIGURE 5.8-2 Recommended Damped Response Spectra 17%g Acceleration, N/A Design Basis Earthquake 5.8-3 FIGURE 5.8-3 Recommended Damped Response Spectra 9%g Acceleration, N/A Operating Basis Earthquake (Soil Surface) 5.8-4 FIGURE 5.8-4 Recommended Damped Response Spectra, 17%g Acceleration, N/A Design Basis Earthquake (Soil Surface) 5.8-5 FIGURE 5.8-5 Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Critical N/A Damping = 0.5%)
5.8-6 FIGURE 5.8-6 Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Critical N/A Damping = 1%)
5.8-7 FIGURE 5.8-7 Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Critical N/A Damping = 2%)
5.8-8 FIGURE 5.8-8 Comparison of Smooth Response Spectra vs. Response Spectra from the Anamet Time History Design Earthquake (Critical N/A Damping = 5%)
5.8-9 FIGURE 5.8-9 Response Spectra from the Time History Design Earthquake with N/A Various Frequency Intervals
Figure Number Figure Label Title Drawing Number She 5.8-10 FIGURE 5.8-10 Comparison of Response Spectra with 1952 Taft and 1940 El N/A Centro Earthquake 5.8-11 FIGURE 5.8-11 Foundation Outline N/A 5.8-12 FIGURE 5.8-12 Sections A-A & B-B N/A 5.8-13 FIGURE 5.8-13 Auxiliary Bay of Turbine Building N/A 5.8-14 FIGURE 5.8-14 Containment Mass Model N/A 5.8-15 FIGURE 5.8-15 Mode Shapes for the Containment Building N/A 5.8-16 FIGURE 5.8-16 Containment Building Design Earthquake 9% Ground N/A Acceleration 5.8-17 FIGURE 5.8-17 Containment Building Design Earthquake 17% Ground N/A Acceleration 5.8-18 FIGURE 5.8-18 Containment Structure Elevation 53 feet 0 inches N/A 5.8-19 FIGURE 5.8-19 Containment Structure Elevation 97 feet 0 inches N/A 5.8-20 FIGURE 5.8-20 Containment Structure Elevation 152 feet 6 inches N/A 5.8-21 FIGURE 5.8-21 Containment Internals Model N/A 5.8-22 FIGURE 5.8-22 Mode Shapes & Frequencies Containment Internals - North-South N/A 5.8-23 FIGURE 5.8-23 Mode Shapes & Frequencies Containment Internals - North-South N/A OBE (DBE) 5.8-24 FIGURE 5.8-24 Mode Shapes & Frequencies Containment Internals - East-West N/A 5.8-25 FIGURE 5.8-25 Containment Internals - East-West OBE (DBE) N/A 5.8-26 FIGURE 5.8-26 Containment Internals Elevation 0 feet 0 inches - OBE (North-N/A South) Reactor Vessel Support 5.8-27 FIGURE 5.8-27 Containment Internals Elevation 0 feet 0 inches - OBE (East-N/A West) Reactor Vessel Support
Figure Number Figure Label Title Drawing Number She 5.8-28 FIGURE 5.8-28 Containment Internals Elevation 14 feet 6 inches - OBE (North-N/A South) Pressurizer Support 5.8-29 FIGURE 5.8-29 Containment Internals Elevation 14 feet 6 inches - OBE (East-N/A West) Pressurizer Support 5.8-30 FIGURE 5.8-30 Containment Internals Elevation 38 feet 6 inches - OBE (North-N/A South) Safety Injection Tank Support 5.8-31 FIGURE 5.8-31 Containment Internals Elevation 38 feet 6 inches - OBE (East-N/A West) Safety Injection Tank Support 5.8-32 FIGURE 5.8-32 Containment Internals Elevation 43 feet 0 inches - OBE (North-N/A South) Steam Generator Upper Support (Snubbers) 5.8-33 FIGURE 5.8-33 Containment Internals Elevation 43 feet 0 inches - OBE (East-N/A West) Steam Generator Upper Support (Snubbers) 5.8-34 FIGURE 5.8-34 Containment Internals Elevation 50 feet 0 inches - OBE (North-N/A South) Steam Generator Upper Support (Shear Keys) 5.8-35 FIGURE 5.8-35 Containment Internals Elevation 50 feet 0 inches - OBE (East-N/A West) Steam Generator Upper Support (Shear Keys) 5.8-36 FIGURE 5.8-36 Containment Internals Elevation0 feet 0 inches - OBE (North-N/A South) Steam Generator Lower Support 5.8-37 FIGURE 5.8-37 Containment Internals Elevation 0 feet 0 inches - OBE (East-N/A West) Steam Generator Lower Support 5.8-38 FIGURE 5.8-38 Auxiliary Building Model N/A 5.8-39 FIGURE 5.8-39 Mode Shapes & Frequencies Auxiliary Building - North-South N/A 5.8-40 FIGURE 5.8-40 Auxiliary Building - North-South OBE (DBE) N/A 5.8-41 FIGURE 5.8-41 Mode Shapes & Frequencies Auxiliary Building - East-West N/A 5.8-42 FIGURE 5.8-42 Auxiliary Building - East-West OBE (DBE) N/A
Figure Number Figure Label Title Drawing Number She 5.8-43 FIGURE 5.8-43 Auxiliary Building Elevation 14 feet 6 inches N/A 5.8-44 FIGURE 5.8-44 Auxiliary Building Elevation 38 feet 6 inches N/A 5.8-45 FIGURE 5.8-45 Auxiliary Building Elevation 71 feet 6 inches N/A 5.8-46 FIGURE 5.8-46 Warehouse Model N/A 5.8-47 FIGURE 5.8-47 Mode Shapes & Frequencies Warehouse Bldg. - East-West N/A 5.8-48 FIGURE 5.8-48 Mode Shapes & Frequencies Warehouse Bldg. - North-South N/A 5.8-49 FIGURE 5.8-49 Warehouse Bldg. - OBE (DBE) N/A 5.8-50 FIGURE 5.8-50 Warehouse Elevation 38 feet 6 inches N/A 5.8-51 FIGURE 5.8-51 Turbine Building Model N/A 5.8-52 FIGURE 5.8-52 Mode Shapes & Frequencies Turbine Bldg. - North-South N/A 5.8-53 FIGURE 5.8-53 Turbine Bldg. OBE (DBE) East-West N/A 5.8-54 FIGURE 5.8-54 Mode Shapes & Frequencies Turbine Bldg. - East-West N/A 5.8-55 FIGURE 5.8-55 Turbine Bldg. OBE (DBE) North-South N/A 5.8-56 FIGURE 5.8-56 Turbine Building Elevation 31 feet 6 inches N/A 5.8-57 FIGURE 5.8-57 Turbine Building Crane - OBE N/A 5.8-58 FIGURE 5.8-58 Intake Structure Model N/A 5.8-59 FIGURE 5.8-59 Intake Structure OBE (DBE) N/A 5.8-60 FIGURE 5.8-60 Mode Shapes & Frequencies Intake Structure N/A 5.8-61 FIGURE 5.8-61 Intake Structure Elevation 14 feet 0 inches OBE N/A 5.A-1 FIGURE 5.A-1 Thick Walled Cylinder With Internal Pressure N/A 5.D-1 FIGURE 5.D-1 Tangential Velocities as Derived from Hoecker's Pressure - Time N/A Profile
Figure Number Figure Label Title Drawing Number She 5.D-2 FIGURE 5.D-2 Monthly Weather Review - Hoecker N/A 5.D-3 FIGURE 5.D-3 Test Data Summary N/A 5.D.A-1 FIGURE 5.D.A-1 Plan of Spent Fuel Area N/A 5.D.A-2 FIGURE 5.D.A-2 Spent Fuel Pool Section View N/A 5.D.A-3 FIGURE 5.D.A-3 Missile Strike Angle to Missile Proof Siding N/A 6.1-1 FIGURE 6.1-1 Safety Injection P&ID (Sheet 1) 25203-26015 (a) Sheet 1 6.1-1 FIGURE 6.1-1 Safety Injection P&ID (Sheet 2) 25203-26015 (a) Sheet 2 6.1-1 FIGURE 6.1-1 Safety Injection P&ID (Sheet 3) 25203-26015 (a) Sheet 3 6.1-2 FIGURE 6.1-2 Main Steam Pipe Whip Restraint N/A 6.1-3 FIGURE 6.1-3 Pipe Restraint Design N/A 6.1-4 FIGURE 6.1-4 Fluid Jet Expansion Model N/A 6.3-1 FIGURE 6.3-1 Safety Injection and Containment Spray Pumps Suction Piping N/A 6.3-2 FIGURE 6.3-2 High Pressure Safety Injection Pump Performance N/A 6.3-3 FIGURE 6.3-3 Low Pressure Safety Injection Pump Performance N/A 6.4-1 FIGURE 6.4-1 Area 5 Piping Containment Spray and Hydrogen Purge N/A 6.4-2 FIGURE 6.4-2 Containment Spray Nozzles Spray Patterns (1713A Nozzle N/A Spraying Horizontally) 6.4-3 FIGURE 6.4-3 Containment Spray Nozzles Spray Patterns (1713A Nozzle N/A Spraying Downward on 45°)
6.4-4 FIGURE 6.4-4 Containment Spray Nozzles Spray Patterns (1713A Nozzle N/A Spraying Vertically Downward) 6.4-4A FIGURE 6.4-4A Typical Spray Coverage Patterns N/A
Figure Number Figure Label Title Drawing Number She 6.4-5 FIGURE 6.4-5 Not Used N/A 6.4-6 FIGURE 6.4-6 Not Used N/A 6.4-7 FIGURE 6.4-7 Containment Spray Nozzle Performance Characteristics N/A 6.4-8 FIGURE 6.4-8 Containment Spray Pump Performance Characteristics. N/A 6.4-9 FIGURE 6.4-9 Containment Heat Removal Systems Sink Schematic N/A 6.5-1 FIGURE 6.5-1 Containment Air Recirculation and Cooling Unit Fan N/A Performance Curve 6.5-2 FIGURE 6.5-2 Containment Air Recirculation and Cooling Unit Coil N/A Performance Characteristics 6.6-1 FIGURE 6.6-1 Post-Incident Recirculation Fan Performance Characteristics N/A 6.7-1 FIGURE 6.7-1 Enclosure Building Filtration System Fan Performance Curve N/A 7.2-1 FIGURE 7.2-1 Reactor Protective System Block Diagram 7.2-2 FIGURE 7.2-2 Reactor Protective System Functional Diagram 25203-29193 (a) Shee 7.2-3 FIGURE 7.2-3 Nuclear Instrumentation System Functional Diagram 7.2-4 FIGURE 7.2-4 Low Flow Protective System Functional Diagram 7.2-5 FIGURE 7.2-5 Low Steam Generator Pressure Reactor Trip Bypass Functional Diagram 7.2-6 FIGURE 7.2-6 Block Diagram Core Protection Trips 7.2-7 FIGURE 7.2-7 Neutron Flux Monitoring System Logarithmic Range Channels 7.2-8 FIGURE 7.2-8 Neutron Flux Monitoring System Power Range Channels 7.2-9 FIGURE 7.2-9 Not Used 7.2-10 FIGURE 7.2-10 Reactor Coolant Pump Underspeed Block Diagram 7.2-11 FIGURE 7.2-11 Variable High Power Trip Operation
Figure Number Figure Label Title Drawing Number She 7.2-12 FIGURE 7.2-12 Thermal Margin Trip 7.2-13 FIGURE 7.2-13 DT Power Calculation 7.2-14 FIGURE 7.2-14 Local Power Density Trip 7.3-1 FIGURE 7.3-1 Engineered Safety Logic 25203-28150 (a) Shee 7.3-2A FIGURE 7.3-2A Engineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a) Sheet 7.3-2B FIGURE 7.3-2B Engineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a) Sheet 7.3-2C FIGURE 7.3-2C Engineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a) Sheet 7.3-2D FIGURE 7.3-2D Engineered Safety Logic Actuated Equipment Tabulation 25203-28150 (a) Sheet 7.3-3 FIGURE 7.3-3 Engineered Safety Logic Sequencer & Channel 5 Output 25203-28150 (a) Shee 7.3-4 FIGURE 7.3-4 Engineered Safety Logic 25203-28150 (a) Shee 7.4-1 FIGURE 7.4-1 Deleted by FSARCR 05-MP2-026 N/A 7.4-2 FIGURE 7.4-2 CEA Position Setpoints N/A 7.4-3 FIGURE 7.4-3 CEDS Functional Block Diagram 25203-29155 (a) Shee 7.4-4 FIGURE 7.4-4 Pressure Control Program N/A 7.4-5 FIGURE 7.4-5 Steam Dump to Condensers and Turbine Bypass System N/A 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 1) 25203-39220 (a) Sheet 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 2) 25203-39220 (a) Sheet 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 3) 25203-39220 (a) Sheet 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 4) 25203-39220 (a) Sheet 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 5) 25203-39220 (a) Sheet
Figure Number Figure Label Title Drawing Number She 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 6) 25203-39220 (a) Sheet 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 7) 25203-39220 (a) Sheet 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 8) 25203-39220 (a) Sheet 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 9) 25203-39220 (a) Sheet 7.4-6 FIGURE 7.4-6 Feedwater Control System (Sheet 10) 25203-39220 (a) Sheet 7.4-7 FIGURE 7.4-7 Feedwater Regulating System Block Power Distribution N/A 7.4-8 FIGURE 7.4-8 Reactivity Control System N/A 7.4-9 FIGURE 7.4-9 Motion Inhibit Circuit Interconnection Simplified Diagram N/A 7.5-1 FIGURE 7.5-1 Pressurizer Pressure Measurement Channel Functional Diagram N/A 7.5-2 FIGURE 7.5-2 Out-Of-Core Nuclear Detector Location N/A 7.5-3 FIGURE 7.5-3 In-Core Nuclear Detector Assembly N/A 7.5-4 FIGURE 7.5-4 In-Core Detector/Core Exit Thermocouple and RVLM Sensor N/A Locations 7.5-5 FIGURE 7.5-5 Process Radiation Monitor Schematic N/A 7.5-6 FIGURE 7.5-6 Heated Junction Thermocouple Probe Assembly N/A 7.5-7 FIGURE 7.5-7 ICCMS Functional Block Diagram N/A 7.5-8 FIGURE 7.5-8 ICCMS Data Processing N/A 7.5-9 FIGURE 7.5-9 ICCMS Display Hierarchy N/A 7.6-1 FIGURE 7.6-1 General Arrangement Control Room Plan Elevation 35 feet 6 inches 25203-27027 (a) 7.6-2 FIGURE 7.6-2 C01, CRP, Front View Arrangement Safeguards Section (Sheet 1) 25203-30208 (a) Sheet 1
Figure Number Figure Label Title Drawing Number She 7.6-2 FIGURE 7.6-2 C01, CRP, Front View Arrangement Safeguards Section (Sheet 2) 25203-30208 (a) Sheet 2 7.6-2 FIGURE 7.6-2 C01, CRP, Front View Arrangement Safeguards Section (Sheet 3) 25203-30208 (a) Sheet 3 7.6-2 FIGURE 7.6-2 C01, CRP, Front View Arrangement Safeguards Section (Sheet 4) 25203-30208 (a) Sheet 4 7.6-3 FIGURE 7.6-3 CRP Front View Arrangements (Sheet 1) 25203-30209 (a) Sheet 1 7.6-3 FIGURE 7.6-3 CRP Front View Arrangements (Sheet 2) 25203-30209 (a) Sheet 2 7.6-3 FIGURE 7.6-3 CRP Front View Arrangements (Sheet 3) 25203-30210 (a) Sheet 1 7.6-3 FIGURE 7.6-3 CRP Front View Arrangements (Sheet 4) 25203-30210 (a) Sheet 2 7.6-4 FIGURE 7.6-4 C04 CRP, Front View Arrangement Reactivity Control System 25203-30211 (a) Shee (Sheet 1) 7.6-4 FIGURE 7.6-4 C04 CRP, Front View Arrangement Reactivity Control System 25203-30211 (a) Shee (Sheet 2) 7.6-4 FIGURE 7.6-4 C04 CRP, Front View Arrangement Reactivity Control System 25203-30211 (a) Shee (Sheet 3) 7.6-4 FIGURE 7.6-4 C04 CRP, Front View Arrangement Reactivity Control System 25203-30211 (a) Shee (Sheet 4) 7.6-5 FIGURE 7.6-5 C05, CRP, Front View Arrangement Steam Generator &
25203-30212 (a) Shee Feedwater Control (Sheet 1) 7.6-5 FIGURE 7.6-5 C05, CRP, Front View Arrangement Steam Generator &
25203-30212 (a) Shee Feedwater Control (Sheet 2) 7.6-5 FIGURE 7.6-5 C05, CRP, Front View Arrangement Steam Generator &
25203-30212 (a) Shee Feedwater Control (Sheet 3) 7.6-5 FIGURE 7.6-5 C05, CRP, Front View Arrangement Steam Generator &
25203-30212 (a) Shee Feedwater Control (Sheet 4)
Figure Number Figure Label Title Drawing Number She 7.6-6 FIGURE 7.6-6 C06, CRP. Front View Arrangement Plant Auxiliary (Sheet 1) 25203-30213 (a) Sheet 1 7.6-6 FIGURE 7.6-6 C06, CRP. Front View Arrangement Plant Auxiliary (Sheet 2) 25203-30213 (a) Sheet 2 7.6-7 FIGURE 7.6-7 C07, Control Room Panel, Front View Arrangement Turbine-25203-30214 (a) Sheet 1 Generator (Sheet 1) 7.6-7 FIGURE 7.6-7 C07, Control Room Panel, Front View Arrangement Turbine-25203-30214 (a) Sheet 2 Generator (Sheet 2) 7.6-7 FIGURE 7.6-7 C07, Control Room Panel, Front View Arrangement Turbine-25203-30214 (a) Sheet 3 Generator (Sheet 3) 7.6-7 FIGURE 7.6-7 C07, Control Room Panel, Front View Arrangement Turbine-25203-30214 (a) Sheet 4 Generator (Sheet 4) 7.6-8 FIGURE 7.6-8 C08, CRP Front View Arrangement Station Service Electric 25203-30215 (a) Sheet 1 (Sheet 1) 7.6-8 FIGURE 7.6-8 C08, CRP Front View Arrangement Station Service Electric 25203-30215 (a) Sheet 2 (Sheet 2) 7.6-8 FIGURE 7.6-8 C08, CRP Front View Arrangement Station Service Electric 25203-30215 (a) Sheet 3 (Sheet 3) 7.6-8 FIGURE 7.6-8 C08, CRP Front View Arrangement Station Service Electric 25203-30215 (a) Sheet 4 (Sheet 4) 7.6-9 FIGURE 7.6-9 Local Control Panels (C60) & (C61) 25203-28006 (a) Sheet 1 7.6-10 FIGURE 7.6-10 Local Control Panels (C63) & (C21) 25203-28006 (a) Sheet 2 7.6-11 FIGURE 7.6-11 Engineered Safety Equipment Status Panel Layout (C01X) 25203-30071 (a) 7.6-12 FIGURE 7.6-12 Condensate Demineralizer Waste Treating Panel CDX N/A 7.6-13 FIGURE 7.6-13 Condensate Demineralizer Waste Treating Panel CDX N/A 7.6-14 FIGURE 7.6-14 Condensate Demineralizer Waste Treating Panel CDX N/A
Figure Number Figure Label Title Drawing Number She 7.6-15 FIGURE 7.6-15 Condensate Demineralizer Waste Treating Panel CDX N/A 7.9-1 FIGURE 7.9-1 Logic Diagram - Anticipated Transient Without Scram 25203-28105 (a) Sheet 7.9-2 FIGURE 7.9-2 Block Diagram Diverse SCRAM System (ATWS) 25203-37005 (a) Sheet 7.9-3 FIGURE 7.9-3 Schematic Diagram Diverse SCRAM System ATWS 25203-32012 (a) Sheet 7.10-1 FIGURE 7.10-1 Piping and Instrumentation Diagram Auxiliary Steam and 25203-26026 (a) Sheet 2 Condensate 8.1-1A FIGURE 8.1-1A Deleted by FSARCR MP2-UCR-2016-007 N/A 8.1-1B FIGURE 8.1-1B Hunts Brook Junction N/A 8.1-1C FIGURE 8.1-1C 345 kV Transmission Map of Connecticut and Western N/A Massachusetts 8.1-1D FIGURE 8.1-1D 345 kV Switchyard N/A 8.2-1 FIGURE 8.2-1 Main Single Line Diagram 25203-30001 (a) 8.3-1 FIGURE 8.3-1 Logic Diagrams Diesel Generators (Sheet A) 25203-30034 (a) Shee 8.3-1 FIGURE 8.3-1 Logic Diagrams Diesel Generators (Sheet B) 25203-30034 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 0A) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 1) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 1A) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 2) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 2A) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 3) 25203-32041 (a) Shee
Figure Number Figure Label Title Drawing Number She 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 4) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 5) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 6) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 7) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 8) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 9) 25203-32041 (a) Shee 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 10) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 11) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 12) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 13) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 14) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 15) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 16) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 17) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 18) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 19) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 20) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 21) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 22) 25203-32041 (a) Sheet
Figure Number Figure Label Title Drawing Number She 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 23) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 24) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 25) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 26) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 27) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 28) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 29) 25203-32041 (a) Sheet 8.3-2 FIGURE 8.3-2 Diesel Generator Related (Sheet 30) 25203-32041 (a) Sheet 8.3-3 FIGURE 8.3-3 Not Used 8.3-4 FIGURE 8.3-4 Diesel Generator Fuel Oil System/Auxiliary Steam Condensate 25203-26010 (a) Sheet 1 and Heater Index (Sheets 1) 8.3-4 FIGURE 8.3-4 Diesel Generator Fuel Oil System/Auxiliary Steam Condensate 25203-26026 (a) Sheet 3 and Heater Index (Sheet 2) 8.3-4 FIGURE 8.3-4 Diesel Generator Fuel Oil System/Auxiliary Steam Condensate 25203-26026 (a) Sheet 4 and Heater Index (Sheet 3) 8.3-5 FIGURE 8.3-5 Diesel Generators' Ancillary Systems (Sheet 1A) 25203-26018 (a) Sheet 4 8.3-5 FIGURE 8.3-5 Diesel Generators' Ancillary Systems (Sheet 1B) 25203-26018 (a) Sheet 5 8.3-5 FIGURE 8.3-5 Diesel Generators' Ancillary Systems (Sheet 2) 25203-26018 (a) Sheet 2 8.3-5 FIGURE 8.3-5 Diesel Generators' Ancillary Systems (Sheet 3) 25203-26018 (a) Sheet 3 8.4-1 FIGURE 8.4-1 Charging Pump - Power Supply Crossover P18B 25203-32009 (a) Sheet 8.4-2 FIGURE 8.4-2 Service Water Strainer ML1B Power Supply Crossover Scheme 25203-32013 (a) Sheet
Figure Number Figure Label Title Drawing Number She 8.5-1 FIGURE 8.5-1 Single Line Diagram 125 VDC / VAC Systems (Sheet 1) 25203-30024 (a) 8.5-1 FIGURE 8.5-1 Single Line Diagram 125 VDC / VAC Systems (Sheet 2) 25203-30023 (a) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 1) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 2) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 3) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 4) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 5) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 6) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 7) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 8) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Shee 9) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Sheet 10A) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Sheet 10B)
Figure Number Figure Label Title Drawing Number She 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Sheet 10C) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Sheet 10D) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Sheet 11) 8.5-2 FIGURE 8.5-2 Reactor Trip Switchgear Circuit Breaker Control Circuitry (Sheet 25203-32045 (a) Sheet 12) 8.7-1 FIGURE 8.7-1 Raceway Plans (Sheet 1) 25203-34060 (a) 8.7-1 FIGURE 8.7-1 Raceway Plan Cable Vault Area -6, Elevation 25 Feet 6 Inches (Sheet 2) 25203-34031 (a) 8.7-1 FIGURE 8.7-1 Raceway Plan Cable Vault Area -7, Elevation 25 Feet 6 Inches (Sheet 3) 25203-34032 (a) 8.7-1 FIGURE 8.7-1 Raceway Plan Containment Area Elevation 14 Feet 6 Inches (Sheets 4) 25203-34042 (a) 9.0-1 FIGURE 9.0-1 P&ID Legend 25203-26001 (a) Sheet 1 9.0-2 FIGURE 9.0-2 P&ID Legend 25203-26001 (a) Sheet 2 9.0-3 FIGURE 9.0-3 General Legend Notes N/A 9.2-1 FIGURE 9.2-1 Chemical and Volume Control System Flow Schematic (Normal N/A Operation) 9.2-2 FIGURE 9.2-2 P&IDs: Charging; Deborating; Purification; Boric Acid Systems 25203-26017 (a) Sheet 1 (Sheet 1) 9.2-2 FIGURE 9.2-2 P&IDs: Charging; Deborating; Purification; Boric Acid Systems 25203-26017 (a) Sheet 2 (Sheet 2)
Figure Number Figure Label Title Drawing Number She 9.2-2 FIGURE 9.2-2 P&IDs: Charging; Deborating; Purification; Boric Acid Systems 25203-26017 (a) Sheet 3 (Sheet 3) 9.3-1 FIGURE 9.3-1 Shutdown Cooling Flow Diagram N/A 9.4-1 FIGURE 9.4-1 P&ID RBCCW System RBCCW Pumps and Heat Exchangers 25203-26022 (a) Sheet 1 9.4-2 FIGURE 9.4-2 RBCCW System Spent Fuel Pool and Shutdown Heat Exchangers 25203-26022 (a) Sheet 2 9.4-3 FIGURE 9.4-3 P&ID RBCCW. System Containment Spray Pump and Safety 25203-26022 (a) Sheet 3 Injection Pump Seal Coolers 9.4-4 FIGURE 9.4-4 P&ID RBCCW. System Reactor Coolant Pump, Thermal Barriers 25203-26022 (a) Sheet 4 and Lube Oil Coolers 9.4-5 FIGURE 9.4-5 P&ID RBCCW. System Containment Air Recirculation and 25203-26022 (a) Sheet 5 Coolant Unit 9.4-6 FIGURE 9.4-6 P&ID Diagram RBCCW. System Reactor Vessel Support 25203-26022 (a) Sheet 6 Concrete Cooling Coils 9.4-7 FIGURE 9.4-7 Reactor Building Closed Cooling Water Pump Performance N/A Curve 9.5-1 FIGURE 9.5-1 P&ID Spent Fuel Pool Cleaning and Cleanup System (Sheet 1) 25203-26023 (a) Sheet 1 9.5-1 FIGURE 9.5-1 P&ID Spent Fuel Pool Cleaning and Cleanup System (Sheet 2) 25203-26023 (a) Sheet 2 9.5-2 FIGURE 9.5-2 Spent Fuel Pool Pump Performance Curve N/A 9.6-1 FIGURE 9.6-1 P&ID Diagram Sampling System 25203-26025 (a) Sheet 1 9.6-2 FIGURE 9.6-2 P&ID Diagram Sampling System 25203-26025 (a) Sheet 2 9.6-3 FIGURE 9.6-3 P&ID Diagram Sampling System 25203-26025 (a) Sheet 3 9.6-4 FIGURE 9.6-4 P&ID Post Accident Sampling System Reactor Coolant Sample 25203-26074 (a) Sheet 1
Figure Number Figure Label Title Drawing Number She 9.6-5 FIGURE 9.6-5 P&ID Post Accident Sampling System Containment Air Sample 25203-26074 (a) Sheet 2 9.7-1 FIGURE 9.7-1 P&IDs - Circulating Water, Service Water, Screen Wash, Sodium 25203-26008 (a) Sheet 1 Hypochlorite (Sheet 1) 9.7-1 FIGURE 9.7-1 P&IDs - Circulating Water, Service Water, Screen Wash, Sodium 25203-26008 (a) Sheet 2 Hypochlorite (Sheet 2) 9.7-1 FIGURE 9.7-1 P&IDs - Circulating Water, Service Water, Screen Wash, Sodium 25203-26008 (a) Sheet 3 Hypochlorite (Sheet 3) 9.7-1 FIGURE 9.7-1 P&IDs - Circulating Water, Service Water, Screen Wash, Sodium 25203-26008 (a) Sheet 4 Hypochlorite (Sheet 4) 9.7-2 FIGURE 9.7-2 P&ID TBCCW System (Sheet 1) 25203-26007 (a) Sheet 1 9.7-2 FIGURE 9.7-2 P&ID TBCCW System (Sheet 2) 25203-26007 (a) Sheet 2 9.7-2 FIGURE 9.7-2 P&ID TBCCW System (Sheet 3) 25203-26007 (a) Sheet 3 9.7-3 FIGURE 9.7-3 Typical Service Water Pump Certified Test Curve N/A 9.7-4 FIGURE 9.7-4 Deleted by FSARCR 03-MP2-011 N/A 9.8-1 FIGURE 9.8-1 Plan of New Fuel Storage Racks N/A 9.8-2 FIGURE 9.8-2 New Fuel Storage Racks - Section A-A N/A 9.8-3 FIGURE 9.8-3 New Fuel Storage Rack Assembly (8 Rack Module) 25203-13013 (a) Sheet 9.8-4 FIGURE 9.8-4 New Fuel Storage Rack Assembly (4 Rack Module) 25203-13013 (a) Sheet 9.8-5 FIGURE 9.8-5 Storage Rack N/A 9.8-6 FIGURE 9.8-6 Closure Bar New Fuel Storage Racks 25203-13013 (a) Sheet 9.8-7 FIGURE 9.8-7 Fuel Pool Arrangement - Four Region N/A 9.8-8A FIGURE 9.8-8A Typical Spent Fuel Rack Module/Poison Box - Regions 1 and 2 N/A
Figure Number Figure Label Title Drawing Number She 9.8-8B FIGURE 9.8-8B Typical Spent Fuel Rack Module/Regions 3 and 4 N/A 9.8-8C FIGURE 9.8-8C Poison Box (Boraflex poison no longer credited) N/A 9.8-8D FIGURE 9.8-8D Adjustable Foot N/A 9.8-9 FIGURE 9.8-9 Collector Leak Channel Plan at Base of Walls N/A 9.8-10 FIGURE 9.8-10 Refueling Equipment Arrangement N/A 9.8-11 FIGURE 9.8-11 Refueling Machine N/A 9.8-12 FIGURE 9.8-12 Deleted by PKG FSC MP2-UCR-2009-006 N/A 9.8-13 FIGURE 9.8-13 Reactor Vessel Head Lifting Rig N/A 9.8-14 FIGURE 9.8-14 Core Support Barrel Lifting Rig N/A 9.8-15 FIGURE 9.8-15 Upper Guide Structure Lifting Rig N/A 9.8-16 FIGURE 9.8-16 Surveillance Capsule Retrieval Tool N/A 9.8-17 FIGURE 9.8-17 Spent Fuel Pool Platform Crane N/A 9.8-18 FIGURE 9.8-18 Spent Fuel Pool Platform Crane Travel Limits N/A 9.8-19 FIGURE 9.8-19 Spent Fuel Cask Crane 25203-29022 (a) 16 9.8-20 FIGURE 9.8-20 Heated Junction Thermocouple Handling Canister N/A 9.9-1 FIGURE 9.9-1 P&ID Containment and Enclosure Building Ventilation 25203-26028 (a) Sheet 1 9.9-2 FIGURE 9.9-2 Ventilation P&IDs (Sheet 1) 25203-26028 (a) Sheet 2 9.9-2 FIGURE 9.9-2 Ventilation P&IDs (Sheet 2) 25203-26028 (a) Sheet 3 9.9-2 FIGURE 9.9-2 Ventilation P&IDs (Sheet 3) 25203-26028 (a) Sheet 4 9.9-2 FIGURE 9.9-2 Ventilation P&IDs (Sheet 4) 25203-26028 (a) Sheet 5 9.9-3 FIGURE 9.9-3 P&ID Auxiliary Building Ventilation System (Sheet 1) 25203-26029 (a) Sheet 1
Figure Number Figure Label Title Drawing Number She 9.9-3 FIGURE 9.9-3 P&ID Auxiliary Building Ventilation System (Sheet 2) 25203-26029 (a) Sheet 2 9.9-3 FIGURE 9.9-3 P&ID Auxiliary Building Ventilation System (Sheet 3) 25203-26029 (a) Sheet 3 9.9-4 FIGURE 9.9-4 P&ID HVAC System Turbine Building, Intake Structure, 25203-26027 (a) Shee Warehouse and Diesel Generator Rooms 9.9-4A FIGURE 9.9-4A P&ID Control Room Air Conditioning System 25203-26027 (a) Shee 9.9-5 FIGURE 9.9-5 Control Element Drive Mechanism (CEDM) Fan Performance N/A Curve 9.9-6 FIGURE 9.9-6 Containment Purge Fan Performance Curve N/A 9.9-7 FIGURE 9.9-7 Containment Auxiliary Circulation Fan Performance Curve N/A 9.9-8 FIGURE 9.9-8 Containment Penetration Cooling Fan Performance Curve N/A 9.9-9 FIGURE 9.9-9 Radwaste Ventilation Fan Performance Curve N/A 9.9-10 FIGURE 9.9-10 Logic Diagram Radwaste Area Supply Fan 25203-28129 (a) Sheet 9.9-11 FIGURE 9.9-11 Non-Radioactive Supply Fan Performance Curve N/A 9.9-12 FIGURE 9.9-12 Non-Radioactive Exhaust Fan Performance Curve N/A 9.9-13 FIGURE 9.9-13 Battery Room Exhaust Fan Performance Curve N/A 9.9-14 FIGURE 9.9-14 Cable Vault Transfer Fan Performance Curve N/A 9.9-15 FIGURE 9.9-15 Engineered Safety Features Room Fan Performance Curve N/A 9.9-16 FIGURE 9.9-16 Fuel Handling Supply Fan Performance Curve N/A 9.9-17 FIGURE 9.9-17 Deleted N/A 9.9-18 FIGURE 9.9-18 Main Exhaust Fan Performance Curve N/A 9.9-19 FIGURE 9.9-19 Control Room Air Conditioning Fan Performance Curve N/A 9.9-20 FIGURE 9.9-20 Air Cooled Condenser Fan Performance Curve N/A
Figure Number Figure Label Title Drawing Number She 9.9-21 FIGURE 9.9-21 Control Room Exhaust Fan Performance Curve N/A 9.9-22 FIGURE 9.9-22 Control Room Filtration System Fan Performance Curve N/A 9.9-23 FIGURE 9.9-23 Diesel Generator Room Supply Fan Performance Curve N/A 9.9-24 FIGURE 9.9-24 Diesel Generator Fan Performance Curve N/A 9.9-25 FIGURE 9.9-25 Turbine Building Supply Fan Performance Curve N/A 9.9-26 FIGURE 9.9-26 Turbine Building Exhaust Fan Performance Curve N/A 9.9-27 FIGURE 9.9-27 Electrical Room Supply Fan Performance Curve N/A 9.9-28 FIGURE 9.9-28 Access Control Area Air Conditioning Fan Performance Curve N/A 9.9-29 FIGURE 9.9-29 Deleted N/A 9.9-30 FIGURE 9.9-30 Deleted N/A 9.9-31 FIGURE 9.9-31 P&ID Turbine Building, Intake Structure, Warehouse and Diesel 25203-26027 (a) Shee Generator Room Chilled Water System 9.10-1 FIGURE 9.10-1 Deleted N/A 9.10-2 FIGURE 9.10-2 P&ID Domestic Water (Sheet 1) 25203-26011 (a) Sheet 1 9.10-2 FIGURE 9.10-2 P&ID Domestic Water (Sheet 2) 25203-26011 (a) Sheet 2 9.11-1 FIGURE 9.11-1 P&ID Instrument Air System Compressors F-3E and F-3F 25203-26009 (a) Shee 9.11-2 FIGURE 9.11-2 P&ID Instrument Air System Compressors F-3D 25203-26009 (a) Sheet 9 9.12-1 FIGURE 9.12-1 P&ID Diagram Water Treatment System 25203-26030 (a) Sheet 1 9.13-1 FIGURE 9.13-1 P&ID Auxiliary Steam and Condensate (Sheet 1) 25203-26026 (a) Sheet 1 9.13-1 FIGURE 9.13-1 P&ID Auxiliary Steam and Condensate (Sheet 2) 25203-26026 (a) Sheet 2 9.13-1 FIGURE 9.13-1 P&ID Auxiliary Steam and Condensate (Sheet 3) 25203-26026 (a) Sheet 3
Figure Number Figure Label Title Drawing Number She 9.13-1 FIGURE 9.13-1 P&ID Auxiliary Steam and Condensate (Sheet 4) 25203-26026 (a) Sheet 4 10.1-1 FIGURE 10.1-1 Deleted by FSARCR 03-MP2-007] N/A 10.1-2 FIGURE 10.1-2 Deleted by FSARCR 03-MP2-007 N/A 10.3-1 FIGURE 10.3-1 P&ID Main Steam from Generators (25203-26002 Sheet 1) 25203-26002 (a) Sheet 1 10.3-1 FIGURE 10.3-1 P&ID Main Steam Generator Blowdown System (25203-26002 25203-26002 (a) Sheet 2 Sheet 2) 10.3-1 FIGURE 10.3-1 P&ID Main Steam Turbine and Reheater 1A (25203-26002 Sheet 25203-26002 (a) Sheet 3 3) 10.3-1 FIGURE 10.3-1 P&ID Main Steam Turbine (25203-26002 Sheet 4) 25203-26002 (a) Sheet 4 10.4-1 FIGURE 10.4-1 P&ID Condenser Air Removal Water Box Priming and Turbine Building Sump (25203-26012) 25203-26012 (a) 10.4-2 FIGURE 10.4-2 P&ID Condensate System (25203-26005 Sheet 2) 25203-26005 (a) Sheet 1 10.4-2 FIGURE 10.4-2 P&ID Condensate Storage and Auxiliary Feed (25203-26005 25203-26005 (a) Sheet 2 Sheet 3) 10.4-2 FIGURE 10.4-2 P&ID Condensate Storage and Auxiliary Feed (25203-26005 25203-26005 (a) Sheet 3 Sheet 4) 10.4-2 FIGURE 10.4-2 P&ID Condensate System (25203-26005 Sheet 1) 25203-26005 (a) Sheet 4 11.1-1 FIGURE 11.1-1 P&ID Clean Liquid Radwaste System 25203-26020 (a) Sheet 1 11.1-2 FIGURE 11.1-2 P&ID Clean Liquid Radwaste System 25203-26020 (a) Sheet 2 11.1-3 FIGURE 11.1-3 P&ID Drains (Containment & Auxiliary Building and Auxiliary 25203-26024 (a) Shee Yard Sump) (Sheet 1) 11.1-3 FIGURE 11.1-3 P&ID Drains (Containment & Auxiliary Building and Auxiliary 25203-26024 (a) Shee Yard Sump) (Sheet 2)
Figure Number Figure Label Title Drawing Number She 11.1-3 FIGURE 11.1-3 P&ID Drains (Containment & Auxiliary Building and Auxiliary 25203-26024 (a) Shee Yard Sump) (Sheet 3) 11.1-4 FIGURE 11.1-4 P&ID Aerated Liquid Radwaste System 25203-26021 (a) Sheet 1 11.1-5 FIGURE 11.1-5 P&ID Diagram Gaseous Radwaste System 25203-26021 (a) Sheet 2 11.1-6 FIGURE 11.1-6 Degasifier Performance Curve N/A 11.1-7 FIGURE 11.1-7 P&ID Spent Resin Radwaste System 25203-26021 (a) Sheet 3 11.2-1 FIGURE 11.2-1 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building - 25203-17001 (a)
Elevation (-) 45 Feet 6 Inches 11.2-2 FIGURE 11.2-2 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building - 25203-17002 (a)
Elevation (-) 29 Feet 6 Inches 11.2-3 FIGURE 11.2-3 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building - 25203-17003 (a)
Elevation (-) 5 Feet 0 Inches 11.2-4 FIGURE 11.2-4 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment Building - Elevation 14 Feet 25203-17004 (a) 6 Inches and 38 Feet 6 Inches 11.2-5 FIGURE 11.2-5 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Auxiliary Building - Elevation 14 Feet 6 25203-17005 (a)
Inches and 25 Feet 6 Inches 11.2-6 FIGURE 11.2-6 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Turbine Building - Elevation 14 Feet 6 25203-17006 (a)
Inches
Figure Number Figure Label Title Drawing Number She 11.2-7 FIGURE 11.2-7 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Auxiliary Building - Elevation 36 Feet 6 25203-17007 (a)
Inches 11.2-8 FIGURE 11.2-8 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building - 25203-17008 (a)
Section A-A 11.2-9 FIGURE 11.2-9 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary Building - 25203-17009 (a)
Section B-B 11.2-10 FIGURE 11.2-10 P&ID, Radiation Zones and Access Control Normal Operation With 1.0% Failed Fuel Containment and Auxiliary 25203-17010 (a) 11.2-11 FIGURE 11.2-11 Neutron Shield Segment N/A 11.2-12 FIGURE 11.2-12 Neutron Shielding - Sectional View N/A 11.2-13 FIGURE 11.2-13 Not Used N/A 11.2-14 FIGURE 11.2-14 Not Used N/A 11.2-15 FIGURE 11.2-15 Neutron Shield - Thermal Loadings (Typical Annular Section) N/A 11.2-16 FIGURE 11.2-16 Neutron Shield - Thermal Loadings (Plug Shield Section) N/A 11.B-1 FIGURE 11.B-1 NUREG-0017 Gale Code Input Diagram - Liquid Waste System N/A 11.B-2 FIGURE 11.B-2 NUREG-0017 Gale Code Input Diagram - Airborne N/A 13.2-1 FIGURE 13.2-1 Millstone Nuclear Power Station Organization Diagram During N/A Initial Startup 13.2-2 FIGURE 13.2-2 Startup Group Organization N/A 14.0.4-1 FIGURE 14.0.4-1 RCS Cold Leg Temperature as a Function of Power N/A 14.0.4-2 FIGURE 14.0.4-2 Not Used N/A
Figure Number Figure Label Title Drawing Number She 14.0.4-3 FIGURE 14.0.4-3 Not Used N/A 14.0.4-4 FIGURE 14.0.4-4 Not Used N/A 14.0.4-5 FIGURE 14.0.4-5 Not Used N/A 14.0.4-6 FIGURE 14.0.4-6 Not Used N/A 14.0.4-7 FIGURE 14.0.4-7 Linear Heat Rate Limiting Condition for Operation used in Local N/A Power Density Limiting Condition for Operation Verification 14.0.7-1 FIGURE 14.0.7-1 Verification of Local Power Density Limiting Safety System N/A Setting 14.0.7-2 FIGURE 14.0.7-2 Thermal Margin/Low Pressure Trip Function A1 N/A 14.0.7-3 FIGURE 14.0.7-3 Thermal Margin/Low Pressure Trip Function QR1 N/A 14.0.7-4 FIGURE 14.0.7-4 Not Used N/A 14.0.7-5 FIGURE 14.0.7-5 Verification of the Departure from Nucleate Boiling Limiting N/A Condition for Operation 14.0.7-6 FIGURE 14.0.7-6 Verification of Local Power Density Limiting Condition for N/A Operation 14.0.7-7 FIGURE 14.0.7-7 Linear Heat Rate Limiting Condition of Operation Used in Local N/A Power Density Limiting Condition of Operation Verification 14.1.3-1 FIGURE 14.1.3-1 Normalized Power and Heat Flux for the Increase in Steam Flow N/A Event 14.1.3-2 FIGURE 14.1.3-2 Reactivity Feedback for the Increase in Steam Flow Event N/A 14.1.3-3 FIGURE 14.1.3-3 Reactor Coolant Temperatures for Increase in Steam Flow Event N/A 14.1.3-4 FIGURE 14.1.3-4 Core Inlet Mass Flow Rate for the Increase in Steam Flow Event N/A 14.1.3-5 FIGURE 14.1.3-5 Pressurizer Pressure for the Increase in Steam Flow Event N/A 14.1.3-6 FIGURE 14.1.3-6 Steam Generator Pressures for the Increase in Steam Flow Event N/A
Figure Number Figure Label Title Drawing Number She 14.1.3-7 FIGURE 14.1.3-7 Steam Mass Flow Rates for the Increase in Steam Flow Event N/A 14.1.3-8 FIGURE 14.1.3-8 Main Feedwater Flow for the Increase in Steam Flow Event N/A 14.1.3-9 FIGURE 14.1.3-9 Main Feedwater Temperature for the Increase in Steam Flow N/A Event 14.1.5.1-1 FIGURE 14.1.5.1-1 Normalized Core Power (0.20 ft2 Asymmetric Break Inside N/A Containment) 14.1.5.1-2 FIGURE 14.1.5.1-2 Core Inlet Temperatures (0.20 ft2 Asymmetric Break Inside N/A Containment) 14.1.5.1-3 FIGURE 14.1.5.1-3 Reactivity Feedback (0.20 ft2 Asymmetric Break Inside N/A Containment) 14.1.5.1-4 FIGURE 14.1.5.1-4 Pressurizer Pressure (0.20 ft2 Asymmetric Break Inside N/A Containment) 14.1.5.1-5 FIGURE 14.1.5.1-5 Steam Generator Pressures (0.20 ft2 Asymmetric Break Inside N/A Containment) 14.1.5.1-6 FIGURE 14.1.5.1-6 Steam Mass Flow Rates (0.20 ft2 Asymmetric Break Inside N/A Containment) 14.1.5.1-7 FIGURE 14.1.5.1-7 Normalized Power and Heat Flux (Asymmetric 3.51 ft2 Break N/A Inside Containment with Loss of Offsite Power) 14.1.5.1-8 FIGURE 14.1.5.1-8 Reactor Coolant Temperatures (Asymmetric 3.51 ft2 Break Inside N/A Containment with Loss of Offsite Power) 14.1.5.1-9 FIGURE 14.1.5.1-9 Normalized Reactor Coolant System Flow Rate (Asymmetric N/A 3.51 ft2 Break Inside Containment with Loss of Offsite Power) 14.1.5.1-10 FIGURE 14.1.5.1-10 Pressurizer Pressure (Asymmetric 3.51 ft2 Break Inside N/A Containment with Loss of Offsite Power)
Figure Number Figure Label Title Drawing Number She 14.1.5.1-11 FIGURE 14.1.5.1-11 Steam Generator Pressures (Asymmetric 3.51 ft2 Break Inside N/A Containment with Loss of Offsite Power) 14.1.5.2-1 FIGURE 14.1.5.2-1 One Pump High Pressure Safety Injection System Delivery vs.
N/A Primary Pressure (Post-Scram Steam Line Break) 14.1.5.2-2 FIGURE 14.1.5.2-2 Steam Generator Break Flow (HZP Post-Scram Steam Line N/A Outside Containment Break with Offsite Power Available) 14.1.5.2-3 FIGURE 14.1.5.2-3 Steam Generators' Secondary Pressures (HZP Post-Scram Steam N/A Line Outside Containment Break with Offsite Power Available) 14.1.5.2-4 FIGURE 14.1.5.2-4 Core Inlet Temperatures (HZP Post-Scram Steam Line Outside N/A Containment Break with Offsite Power Available) 14.1.5.2-5 FIGURE 14.1.5.2-5 Pressurizer Pressure (HZP Post-Scram Steam Line Outside N/A Containment Break with Offsite Power Available) 14.1.5.2-6 FIGURE 14.1.5.2-6 Pressurizer Level (HZP Post-Scram Steam Line Outside N/A Containment Break with Offsite Power Available) 14.1.5.2-7 FIGURE 14.1.5.2-7 Steam Generators' Secondary Mass (HZP Post-Scram Steam Line N/A Outside Containment Break with Offsite Power Available) 14.1.5.2-8 FIGURE 14.1.5.2-8 Reactivity Components (HZP Post-Scram Steam Line Outside N/A Containment Break with Offsite Power Available) 14.1.5.2-9 FIGURE 14.1.5.2-9 Reactor Power (HZP Post-Scram Steam Line Outside N/A Containment Break with Offsite Power Available) 14.1.5.2-10 FIGURE 14.1.5.2-10 Steam Generator Break Flow (HZP Post-Scram Steam Line N/A Outside Containment Break with Loss of Offsite Power) 14.1.5.2-11 FIGURE 14.1.5.2-11 Steam Generators' Secondary Pressures (HZP Post-Scram Steam N/A Line Outside Containment Break with Loss of Offsite Power) 14.1.5.2-12 FIGURE 14.1.5.2-12 Core Inlet Temperatures (HZP Post-Scram Steam Line Outside N/A Containment Break with Loss of Offsite Power)
Figure Number Figure Label Title Drawing Number She 14.1.5.2-13 FIGURE 14.1.5.2-13 Pressurizer Pressure (HZP Post-Scram Steam Line Outside N/A Containment Break with Loss of Offsite Power) 14.1.5.2-14 FIGURE 14.1.5.2-14 Pressurizer Level (HZP Post-Scram Steam Line Outside N/A Containment Break with Loss of Offsite Power) 14.1.5.2-15 FIGURE 14.1.5.2-15 Reactivity Components (HZP Post-Scram Steam Line Outside N/A Containment Break with Loss of Offsite Power) 14.1.5.2-16 FIGURE 14.1.5.2-16 Reactor Power (HZP Post-Scram Steam Line Outside N/A Containment Break with Loss of Offsite Power) 14.2.1-1 FIGURE 14.2.1-1 Reactor Power Level for Loss of External Load (Primary N/A Overpressurization Case) 14.2.1-2 FIGURE 14.2.1-2 Core Average Heat Flux for Loss of External Load (Primary N/A Overpressurization Case) 14.2.1-3 FIGURE 14.2.1-3 Reactor Coolant System Temperatures for Loss of External Load N/A (Primary Overpressurization Case) 14.2.1-4 FIGURE 14.2.1-4 Primary System Pressures for Loss of External Load (Primary N/A Overpressurization Case) 14.2.1-5 FIGURE 14.2.1-5 Total Reactivity for Loss of External Load (Primary N/A Overpressurization Case) 14.2.1-6 FIGURE 14.2.1-6 Reactor Power Level for Loss of External Load (Secondary N/A Overpressurization Case) 14.2.1-7 FIGURE 14.2.1-7 Core Average Hot Flux for Loss of External Load (Secondary N/A Overpressurization Case) 14.2.1-8 FIGURE 14.2.1-8 Reactor Coolant System Temperatures for Loss of External Load N/A (Secondary Overpressurization Case) 14.2.1-9 FIGURE 14.2.1-9 Pressurizer Pressure for Loss of External Load (Secondary N/A Overpressurization Case)
Figure Number Figure Label Title Drawing Number She 14.2.1-10 FIGURE 14.2.1-10 Total Reactivity for Loss of External Load (Secondary N/A Overpressurization Case) 14.2.1-11 FIGURE 14.2.1-11 Maximum Secondary System Pressures for Loss of External Load N/A (Secondary Overpressurization Case) 14.2.1-12 FIGURE 14.2.1-12 Reactor Power Level for Loss of External Load (MDNBR Case) N/A 14.2.1-13 FIGURE 14.2.1-13 Normalized Heat Flux for Loss of External Load (MDNBR Case) N/A 14.2.1-14 FIGURE 14.2.1-14 Reactor Coolant System Temperature for Loss of External Load N/A (MDNBR Case) 14.2.1-15 FIGURE 14.2.1-15 Pressurizer Pressure for Loss of External Load (MDNBR Case) N/A 14.2.1-16 FIGURE 14.2.1-16 Total Reactivity for Loss of External Load (MDNBR Case) N/A 14.2.1-17 FIGURE 14.2.1-17 Maximum Secondary System Pressure for Loss of External Load N/A (MDNBR Case) 14.2.4-1 FIGURE 14.2.4-1 Reactor Power Level for MSIV Closure (Lower Steam Flow N/A Case) 14.2.4-2 FIGURE 14.2.4-2 Reactor Coolant System Temperatures for MSIV Closure (Lower N/A Steam Flow Case) 14.2.4-3 FIGURE 14.2.4-3 Pressurizer Pressure for MSIV Closure (Lower Steam Flow Case) N/A 14.2.4-4 FIGURE 14.2.4-4 Isolated Steam Generator Pressure at Bottom of Boiler Region for N/A MSIV Closure (Lower Steam Flow Case))
14.2.4-5 FIGURE 14.2.4-5 Open MSIV Steam Generator Steam Dome Pressure for MSIV N/A Closure (Lower Steam Flow Case))
14.2.7-1 FIGURE 14.2.7-1 Reactor Coolant System Loop Temperatures for Minimum Steam Generator Inventory Case: Offsite Power Available, B Motor- N/A Driven AFW Pump Fails to Start
Figure Number Figure Label Title Drawing Number She 14.2.7-2 FIGURE 14.2.7-2 Steam Generator Dome Pressure for Minimum Steam Generator Inventory Case: Offsite Power Available, B Motor-Driven N/A AFW Pump Fails to Start 14.2.7-3 FIGURE 14.2.7-3 Pressurizer Level for Minimum Steam Generator Inventory Case:
Offsite Power Available, B Motor-Driven AFW Pump Fails to N/A Start 14.2.7-4 FIGURE 14.2.7-4 Steam Generator for Liquid Mass Inventory for Minimum Steam Generator Inventory Case: Offsite to Power Available, B N/A Motor-Driven AFW Pump Fails to Start 14.2.7-5 FIGURE 14.2.7-5 Steam Generator Collapsed Liquid Level for Minimum Steam Generator Inventory Case: Offsite to Power Available, B N/A Motor-Driven AFW Pump Fails to Start 14.2.7-6 FIGURE 14.2.7-6 Reactor Coolant System Loop Temperatures for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven N/A AFW Pump Fails to Start 14.2.7-7 FIGURE 14.2.7-7 Steam Generator Dome Pressure for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven AFW Pump Fails N/A to Start 14.2.7-8 FIGURE 14.2.7-8 Pressurizer Level for Maximum Pressurizer Level Case: Loss of N/A Offsite Power, One Motor-Driven AFW Pump Fails to Start 14.2.7-9 FIGURE 14.2.7-9 Steam Generator Liquid Mass Inventory for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven N/A AFW Pump Fails to Start 14.2.7-10 FIGURE 14.2.7-10 Steam Generator Collapsed Liquid Level for Maximum Pressurizer Level Case: Loss of Offsite Power, One Motor-Driven N/A AFW Pump Fails to Start 14.3.1-1 FIGURE 14.3.1-1 Reactor Power Level for Loss of Forced Reactor Coolant Flow N/A
Figure Number Figure Label Title Drawing Number She 14.3.1-2 FIGURE 14.3.1-2 Core Average Heat Flux for Loss of Forced Reactor Coolant Flow N/A 14.3.1-3 FIGURE 14.3.1-3 Reactor Coolant System Temperature for Loss of Forced Reactor N/A Coolant Flow 14.3.1-4 FIGURE 14.3.1-4 Pressurizer Pressure for Loss of Forced Reactor Coolant Flow N/A 14.3.1-5 FIGURE 14.3.1-5 Reactivities for Loss of Forced Reactor Coolant Flow N/A 14.3.1-6 FIGURE 14.3.1-6 Primary Coolant Flow Rate for Loss of Forced Reactor Coolant N/A Flow 14.3.1-7 FIGURE 14.3.1-7 Secondary Pressure for Loss of Forced Reactor Coolant Flow N/A 14.3-3-1 FIGURE 14.3-3-1 Reactor Power Level for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-2 FIGURE 14.3-3-2 Core Average Heat Flux for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-3 FIGURE 14.3-3-3 Reactor Coolant System Temperatures for Reactor Coolant Pump N/A Rotor Seizure 14.3-3-4 FIGURE 14.3-3-4 Pressurizer Pressure for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-5 FIGURE 14.3-3-5 Reactivities for Reactor Coolant Pump Rotor Seizure N/A 14.3-3-6 FIGURE 14.3-3-6 Primary Coolant Flow Rate for Reactor Coolant Pump Rotor N/A Seizure 14.3-3-7 FIGURE 14.3-3-7 Secondary Pressure for Reactor Coolant Pump Rotor Seizure N/A 14.4.1-1 FIGURE 14.4.1-1 Reactor Power Level for Low Power Bank Withdrawal N/A 14.4.1-2 FIGURE 14.4.1-2 Core Average Heat Flux for Low Power Bank Withdrawal N/A 14.4.1-3 FIGURE 14.4.1-3 Reactor Coolant Temperatures for Low Power Bank Withdrawal N/A 14.4.1-4 FIGURE 14.4.1-4 Pressurizer Pressure for Low Power Bank Withdrawal N/A 14.4.1-5 FIGURE 14.4.1-5 Reactivities for Low Power Bank Withdrawal N/A
Figure Number Figure Label Title Drawing Number She 14.4.2-1 FIGURE 14.4.2-1 Reactor Core Power for an Uncontrolled Bank Withdrawal at N/A Power 14.4.2-2 FIGURE 14.4.2-2 Core Average Heat Flux for an Uncontrolled Bank Withdrawal at N/A Power 14.4.2-3 FIGURE 14.4.2-3 Reactor Coolant System Temperatures for an Uncontrolled Bank N/A Withdrawal at Power 14.4.2-4 FIGURE 14.4.2-4 Pressurizer Pressure for an Uncontrolled Bank Withdrawal at N/A Power 14.4.2-5 FIGURE 14.4.2-5 Reactivities for an Uncontrolled Bank Withdrawal at Power N/A 14.4.2-6 FIGURE 14.4.2-6 Secondary Pressure for an Uncontrolled Bank Withdrawal at N/A Power 14.4.3.1-1 FIGURE 14.4.3.1-1 Reactor Power Level for the Limiting Dropped Control Rod/Bank N/A Case 14.4.3.1-2 FIGURE 14.4.3.1-2 Reactor Coolant System Temperatures for the Limiting Dropped N/A Control Rod/Bank Case 14.4.3.1-3 FIGURE 14.4.3.1-3 Pressurizer Pressure for the Limiting Dropped Control Rod/Bank N/A Case 14.4.3.1-4 FIGURE 14.4.3.1-4 Secondary Pressure for the Limiting Dropped Control Rod/Bank N/A Case 14.4.8-1 FIGURE 14.4.8-1 Core Power for a CEA Ejection (Minimum Departure for N/A Nucleate Boiling Ratio Case) 14.4.8-2 FIGURE 14.4.8-2 Core Average Heat Flux for a CEA Ejection (Minimum Departure N/A for Nucleate Boiling Ratio Case) 14.4.8-3 FIGURE 14.4.8-3 Reactor Coolant System Temperatures for a CEA Ejection N/A (Minimum Departure for Nucleate Boiling Ratio Case)
Figure Number Figure Label Title Drawing Number She 14.4.8-4 FIGURE 14.4.8-4 Pressurizer Pressure for a CEA Ejection (Minimum Departure for N/A Nucleate Boiling Ratio Case) 14.4.8-5 FIGURE 14.4.8-5 Reactivities for a CEA Ejection (Minimum Departure for N/A Nucleate Boiling Ratio Case) 14.4.8-6 FIGURE 14.4.8-6 Secondary Pressure for a CEA Ejection (Minimum Departure for N/A Nucleate Boiling Ratio Case) 14.4.8-7 FIGURE 14.4.8-7 Core Power for a CEA Ejection (Overpressure) N/A 14.4.8-8 FIGURE 14.4.8-8 Core Average Heat Flux for a CEA Ejection (Overpressure) N/A 14.4.8-9 FIGURE 14.4.8-9 Primary System Temperatures for a CEA Ejection (Overpressure) N/A 14.4.8-10 FIGURE 14.4.8-10 Pressurizer Pressure for a CEA Ejection (Overpressure) N/A 14.4.8-11 FIGURE 14.4.8-11 Reactivities for a CEA Ejection (Overpressure) N/A 14.4.8-12 FIGURE 14.4.8-12 Secondary Pressure for a CEA Ejection (Overpressure) N/A 14.6.1-1 FIGURE 14.6.1-1 Reactor Power Level for an Inadvertent Opening of a Pressurized N/A Water Reactor Pressurizer Pressure Relief Valve (Rated Power) 14.6.1-2 FIGURE 14.6.1-2 Core Average Heat Flux for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve N/A (Rated Power) 14.6.1-3 FIGURE 14.6.1-3 Reactor Coolant System Temperatures for an Inadvertent Opening of a Pressurized Water Reactor Pressurizer Pressure Relief Valve N/A (Rated Power) 14.6.1-4 FIGURE 14.6.1-4 Pressurizer Pressure for an Inadvertent Opening of a Pressurized N/A Water Reactor Pressurizer Pressure Relief Valve (Rated Power) 14.6.1-5 FIGURE 14.6.1-5 Reactivities for an Inadvertent Opening of a Pressurized Water N/A Reactor Pressurizer Pressure Relief Valve (Rated Power)
Figure Number Figure Label Title Drawing Number She 14.6.1-6 FIGURE 14.6.1-6 Secondary Pressure for an Inadvertent Opening of a Pressurized N/A Water Reactor Pressurizer Pressure Relief Valve (Rated Power) 14.6.3-1 FIGURE 14.6.3-1 Steam Generator Tube Rupture with the Loss of Offsite Power N/A RCS Temperature Versus Time 14.6.3-2 FIGURE 14.6.3-2 Steam Generator Tube Rupture with the Loss of Offsite Power N/A Pressurizer Level Versus Time 14.6.3-3 FIGURE 14.6.3-3 Steam Generator Tube Rupture with the Loss of Offsite Power N/A Pressurizer Pressure Versus Time 14.6.3-4 FIGURE 14.6.3-4 Steam Generator Tube Rupture with the Loss of Offsite Power N/A Steam Generator Pressure Versus Time 14.6.3-5 FIGURE 14.6.3-5 Steam Generator Tube Rupture with the Loss of Offsite Power N/A Total Break Flow Rate Versus Time 14.6.3-6 FIGURE 14.6.3-6 Steam Generator Tube Rupture with the Loss of Offsite Power N/A Flashed Break Flow Rate Versus Time 14.6.3-7 FIGURE 14.6.3-7 Steam Generator Tube Rupture with the Loss of Offsite Power Atmospheric Dump Valve Flow Rate per Steam Generator Versus N/A Time 14.6.3-8 FIGURE 14.6.3-8 Steam Generator Tube Rupture with the Loss of Offsite Power Main Steam Safety Valve Flow Rates per Steam Generator Versus N/A Time 14.6.3-9 FIGURE 14.6.3-9 Steam Generator Tube Rupture with the Loss of Offsite Power N/A Auxiliary Feedwater Flow Versus Time 14.6.5.1-1 FIGURE 14.6.5.1-1 Scatter Plot Operational Parameters N/A 14.6.5.1-2 FIGURE 14.6.5.1-2 PCT Versus PCT Time Scatter Plot N/A 14.6.5.1-3 FIGURE 14.6.5.1-3 PCT Versus PCT Time Scatter Plot N/A 14.6.5.1-4 FIGURE 14.6.5.1-4 Maximum Local Oxidation Versus PCT Scatter Plot N/A
Figure Number Figure Label Title Drawing Number She 14.6.5.1-5 FIGURE 14.6.5.1-5 Total Core Wide Oxidation Versus PCT Scatter Plot N/A 14.6.5.1-6 FIGURE 14.6.5.1-6 Peak Cladding Temperature (Independent of Elevation) for the N/A Demonstration Case 14.6.5.1-7 FIGURE 14.6.5.1-7 Break Flow for the Demonstration Case N/A 14.6.5.1-8 FIGURE 14.6.5.1-8 Core Inlet Mass Flux for the Demonstration Case N/A 14.6.5.1-9 FIGURE 14.6.5.1-9 Core Outlet Mass Flux for the Demonstration Case N/A 14.6.5.1-10 FIGURE 14.6.5.1-10 Void Fraction at RCS Pumps for the Demonstration Case N/A 14.6.5.1-11 FIGURE 14.6.5.1-11 ECCS Flows (Includes SIT, HPSI and LPSI) for the N/A Demonstration Case 14.6.5.1-12 FIGURE 14.6.5.1-12 Upper Plenum Pressure for the Demonstration Case N/A 14.6.5.1-13 FIGURE 14.6.5.1-13 Collapsed Liquid Level in the Downcomer for the Demonstration N/A Case 14.6.5.1-14 FIGURE 14.6.5.1-14 Collapsed Liquid Level in the Lower Plenum for the N/A Demonstration Case 14.6.5.1-15 FIGURE 14.6.5.1-15 Collapsed Liquid Level in the Core for the Demonstration Case N/A 14.6.5.1-16 FIGURE 14.6.5.1-16 Containment and Loop Pressures for the Demonstration Case N/A 14.6.5.1-17 FIGURE 14.6.5.1-17 Pressure Differences between Upper Plenum and Downcomer for N/A the Demonstration Case 14.6.5.2-1 FIGURE 14.6.5.2-1 Peak Cladding Temperature Versus Break Size (SBLOCA Break N/A Spectrum) 14.6.5.2-2 FIGURE 14.6.5.2-2 Reactor Power - 3.78-Inch Break N/A 14.6.5.2-3 FIGURE 14.6.5.2-3 Primary and Secondary System Pressures - 3.78-Inch Break N/A 14.6.5.2-4 FIGURE 14.6.5.2-4 Break Mass Flow Rate - 3.78-Inch Break N/A 14.6.5.2-5 FIGURE 14.6.5.2-5 Break Vapor Void Fraction - 3.78-Inch Break N/A
Figure Number Figure Label Title Drawing Number She 14.6.5.2-6 FIGURE 14.6.5.2-6 Loop Seal Void Fraction - 3.78-Inch Break N/A 14.6.5.2-7 FIGURE 14.6.5.2-7 Total Core Inlet Mass Flow Rate - 3.78-Inch Break N/A 14.6.5.2-8 FIGURE 14.6.5.2-8 Downcomer Collapsed Liquid Level - 3.78-Inch Break N/A 14.6.5.2-9 FIGURE 14.6.5.2-9 Inner and Outer Core Collapsed Liquid Level - 3.78-Inch Break N/A 14.6.5.2-10 FIGURE 14.6.5.2-10 Reactor Vessel Mass - 3.78-Inch Break N/A 14.6.5.2-11 FIGURE 14.6.5.2-11 RCS Loop Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-12 FIGURE 14.6.5.2-12 Steam Generator Main Feedwater Mass Flow Rates - 3.78-Inch N/A Break 14.6.5.2-13 FIGURE 14.6.5.2-13 Steam Generator Auxiliary Feedwater Mass Flow Rates - 3.78-N/A Inch Break 14.6.5.2-14 FIGURE 14.6.5.2-14 Steam Generator Total Mass - 3.78-Inch Break N/A 14.6.5.2-15 FIGURE 14.6.5.2-15 Steam Generator Narrow Range Level % - 3.78-Inch Break N/A 14.6.5.2-16 FIGURE 14.6.5.2-16 High Pressure Safety Injection Mass Flow Rates - 3.78-Inch N/A Break 14.6.5.2-17 FIGURE 14.6.5.2-17 Low Pressure Safety Injection Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-18 FIGURE 14.6.5.2-18 Safety Injection Tank Mass Flow Rates - 3.78-Inch Break N/A 14.6.5.2-19 FIGURE 14.6.5.2-19 Integrated Break Flow And ECCS Flow - 3.78-Inch Break N/A 14.6.5.2-20 FIGURE 14.6.5.2-20 Hot Assembly Collapsed Liquid Level - 3.78-Inch Break N/A 14.6.5.2-21 FIGURE 14.6.5.2-21 Hot Assembly Mixture Level - 3.78-Inch Break N/A 14.6.5.2-22 FIGURE 14.6.5.2-22 Peak Cladding Temperature At Pct Location (11.02 Ft) - 3.78-N/A Inch Break 14.6.5.2-23 FIGURE 14.6.5.2-23 (DELETED by FSARCR 00-MP2-023) N/A 14.6.5.2-24 FIGURE 14.6.5.2-24 (DELETED by FSARCR 00-MP2-023) N/A
Figure Number Figure Label Title Drawing Number She 14.6.5.3-1 FIGURE 14.6.5.3-1 Long Term Cooling Plan N/A 14.6.5.3-2 FIGURE 14.6.5.3-2 Reactor Coolant System Refill Time vs. Break Area N/A 14.6.5.3-3 FIGURE 14.6.5.3-3 Core Flush by Hot Side Injection for a Double-Ended Guillotine N/A Cold Leg Break 14.6.5.3-4 FIGURE 14.6.5.3-4 Inner Vessel Boric Acid Concentration vs. Time for a Double-N/A Ended Guillotine Cold Leg Break 14.8.2-1 FIGURE 14.8.2-1 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Containment Pressure vs. Time 14.8.2-2 FIGURE 14.8.2-2 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Containment Temperature vs. Time 14.8.2-3 FIGURE 14.8.2-3 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Mass Flow Rate vs. Time 14.8.2-4 FIGURE 14.8.2-4 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Energy Release Rate vs. Time 14.8.2-5 FIGURE 14.8.2-5 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Integrated Mass Flow vs. Time 14.8.2-6 FIGURE 14.8.2-6 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Integrated Energy Release vs. Time 14.8.2-7 FIGURE 14.8.2-7 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Affected Steam Generator Pressure vs. Time
Figure Number Figure Label Title Drawing Number She 14.8.2-8 FIGURE 14.8.2-8 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Unaffected Steam Generator Pressure vs. Time 14.8.2-9 FIGURE 14.8.2-9 Main Steam Line Break Analysis - 102% Power with Loss of Offsite Power and Failure of Vital Bus Cabinet VA-10 or VA N/A Affected Steam Generator Liquid Mass vs. Time 14.8.3-1 FIGURE 14.8.3-1 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-2 FIGURE 14.8.3-2 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-3 FIGURE 14.8.3-3 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-4 FIGURE 14.8.3-4 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-5 FIGURE 14.8.3-5 Deleted by FSARCR 04-MP2-018 N/A 14.8.3-6 FIGURE 14.8.3-6 Deleted by FSARCR 04-MP2-018 N/A
- a. Incorporated by reference this engineering controlled drawing is, coincidentally, an MPS-2 FSAR figure. Refer to the controlled plant drawing for the revision.