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{{#Wiki_filter:SURRY POWER STATION UPDATED FINAL SAFETY ANALYSIS REPORT Revision 52Updated Online 09/30/20
 
Intentionally Blank Revision 52Updated Online 09/30/20                      SPS UFSAR                                1 Click on Change Package Number Highlighted in Red to View Change Request.
REVISION
 
==SUMMARY==
 
Revision 52---Updated Online 09/30/20 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
Section 7.4.2.5                                Instrumentation equipment design
[SPS-UCR-2017-012]                              modification CA3041565, TSCR 450-3.7 Section 8.3, Figure 8.3-1                      Hopewell 212 Transmission line Name
[SPS-UCR-2020-007]                              Change SU-20-00107 Sections 11.2.5.1, 15.2, 15.2.3, 15.6.1 and    SPS Response to RIS 2015-06, "Tornado Table 15.2-1                                    Missile Protection" ETE-CCE-2018-0002
[SPS-UCR-2020-002]
Section 15.2.3, References 15.2, Table 15.2-1  Surry Tornado Missile Risk Evaluator
[SPS-UCR-2019-010]                              Implementation ETE-SU-2019-0065 Section 9.10.2.1                                Unit 1 and Unit 2 Fire Protection Upgrades.
[SPS-UCR-2017-011]                              SU-17-00132 Section 9.3.2.2, Table 9.3-2                    Correction to Table 9.3-2
[SPS-UCR-2020-003]                              CA7434130 Tables 4.1-14, 4.1-15, 4.3-3, 4.3-4            Update to Unit 1 and Unit 2 Reactor Pressure
[SPS-UCR-2015-019]                              Vessel Toughness Data (Unirradiated)
PA3007476 14.2, 14.3, 14.4, 14.5, 6.2, 6.3, 9.6, Tables  Updated Alternate Source Term Analysis 14.2-2 through 14.2-4, 14.3-7 through          LBDCR/TSCR 405, CR474351, CR1053122 14.3-16, 14.4-1 through 14.4-3, 14.4-5, 14.4-6, 14.5-7, 14.5-8, 14.5-10, 14.5-11, 6.2-6, 6.3-22
[SPS-UCR-2017-014]
15.2.5                                          SPS Units 1 and 2 UFSAR Updates for
[SPS-UCR-2018-010]                              Beyond Design Basis (BDB) Flooding Mods
                                                - Roof Parapets SU-18-00114
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                                2 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 5109/30/19 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
2.2.1.2, 7.7.1, 9.10.1, 9.10.2.2.5, 9.10.2.2.9,  Consolidated Emergency Operations Facility 9.13.1, 9.13.3.10, 11.3.4.7, 12.3, Table 2.2-10, LAR 17-325 Table 11.3-7
[SPS-UCR-2017-010]
8.5                                              Open phase Condition Detection and
[SPS-UCR-2015-012]                              Protection Systems.
SU-15-01023 10.3.5.2                                        Auxiliary Feedwater MOV Hot Short
[SPS-UCR-2018-003]                              Resolution Unit 2.
SU-16-00108 4.1 Refs, Table, 4.1-12, Table 4.1-13            Surveillance Capsule Schedule
[SPS-UCR-2017-006]                              NRC letter 17-243 (draft),
ETE-CEP-2017-001; LA3062568 Figure 6.1-2                                    U2 Hot Short Resolution Charging Cross-tie
[SPS-UCR-2017-013]                              Relocation SU-17-00135 18.2.16, 18.5                                    Steam Generator Program reference update
[SPS-UCR-2018-005]                              PA3063167 8.3, Figure 8.3-1                                500kV Switchyard Circuit Breaker CB58202
[SPS-UCR-2014-022]                              Tie-in bounding package.
SU-14-01148 7.7.1, 9.10.2.6                                  Update reflects modification to the trunked
[SPS-UCR-2016-002]                              radio communications system.
8.3                                              Modified to correct an approved change that
[SPS-UCR-2018-004]                              was not properly incorporated.
Revision 5009/27/18 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
18.3.2.4, 18.5 Refs                              Update reflects license renewal inspection
[SPS-UCR-2017-008]                              frequency of pressurizer surge lines.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                                3 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 5009/27/18 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
10.3.5.2                                          Update reflects auxiliary feedwater motor
[SPS-UCR-2017-002]                                operated valves fire-rated cables for Appendix R.
Figure 6.1-1                                      Update reflects Unit 1 Charging Cross-tie for
[SPS-UCR-2017-004]                                Appendix R.
2.3.1.2.2                                        Modified description of the exhaust dampers
[SPS-UCR-2018-002]                                to correct an error made during UFSAR conversion to electronic.
4.1.4, 7.2.1.2, 7.2.1.8.3, 7.2.2.3, 7.2.3.2.1,    Update reflects automatic rod withdrawal 7.2.3.2.2, Table 7.2-3, Table 7.2-4, 7.3.1,      capability being disabled.
7.3.2, 7.3.2.2.1, 7.3.2.2.3, 7.3.3.2, 7.3.3.3, Figure 7.3-1, 7.4.3.4, 7.4.3.6, 14.1, 14.2.4.1, 14.2.5.4, 14.2.7.2, 14.2.8.1
[SPS-UCR-2016-012]
9C.1.1                                            Update adds description of MER 5 flood dike
[SPS-UCR-2017-016]                                features.
3.3.3.2.1, 3.3 Refs, 3.5 Refs                    Update reflects Reload Nuclear Design and
[SPS-UCR-2017-015]                                CMS5 Methodologies Revision 4909/28/17 Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
Table 14.3-16                                    Modified table to correct orientation and
[SPS-UCR-2017-009]                                restore original isotopes and concentration values.
9.10.4.18 and 10.3.7.1                            Update reflects Turbine Oil Conditioner
[SPS-FS-2006-013]                                System Replacement.
14.2.5, 14.2, and 9.1.3.5                        Update reflects Boron Dilution Safety
[SPS-UCR-2017-003]                                Analysis Revision 10.3.1.4, 10.3.5, and Figure 10.3.8              Update reflects installation of Unit 1
[SPS-FS-2006-028]                                condensate air in-leakage subsystem.
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                                4 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 4909/28/17 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
Table 11.3-5 and Table 11.3-6                  Update reflects replacement of the Surry
[SPS-UCR-2016-009]                              Radwaste Facility ventilation particulate and noble gas monitors.
3.5.2.1                                        Modified to add description of use of
[SPS-UCR-2016-008]                              demonstration or lead fuel assemblies.
9.1.3.1, Table 9.1-2, Figure 9.1-1, 9.10.1,    Updated to reflect isolation of reactor coolant 9.10.3.2                                        pump seal cooling and the charging
[SPS-UCR-2016-007]                              cross-connect during fire events.
14.5.1.4, 14.5.1.7, Table 14.5-1, Table 14.5-6  Updated peak cladding temperatures.
[SPS-UCR-2016-010]
14B.5.1.6.1                                    Modified high energy line inspection for
[SPS-UCR-2016-011]                              consistency with technical requirements manual.
Revision 4809/29/16 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
9.10.1, 9.10.2.1, 9.10.2.2.5, 9.10.2.2.8,      Update reflects code evaluations completed to 9.10.2.2.9, 9.10.2.8                            address code deficiencies are included in the
[SPS-UCR-2016-005]                              Appendix R report.
7.4.3.2                                        Corrected source range pre-amplifier self test
[SPS-UCR-2015-008]                              frequencies.
Figure 15.1-2                                  Added note to Figure that refers the reader to
[SPS-UCR-2016-006]                              the referenced drawing.
3.5.2.6.1                                      Update reflects ASME revised stress criterion
[SPS-UCR-2015-020]                              for optimized ZirloTM high performance fuel cladding 14.1, 14.2.7.2, 14.2.9.1.1, 14.4.1.2            Update reflects increased
[SPS-UCR-2016-003]                              statistical/deterministic Fdelta H limits Table 4.1-5, 9.1.2.1                            Update reflects reactor coolant pump
[SPS-UCR-2015-001]                              abeyance seal upgrade
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                              5 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 4809/29/16 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
9.10.4.8                                          Update clarifies component cooling pump
[SPS-UCR-2015-009]                                classification.
Table 5.2-1, Table 5.2-2, 6.2.2.1.4, 6.3.1.3.4,  Update reflects addition of FLEX mechanical 9.1.2.1, 10.3.5.2                                connections to the AFW, CH, CS & SI
[SPS-UCR-2012-011]                                systems to mitigate effects of a Beyond Design Basis Event.
9.10.2.6, 7.7.1                                  Update reflects addition of communication
[SPS-UCR-2014-014]                                equipment for offsite communication to mitigate effects of a Beyond Design Basis Event.
7.7.2, 7.10.2, 8.4.3, 9.1.2.1, 10.3.1.2, 14.3.1.5 Update reflects addition of electrical and
[SPS-UCR-2015-010]                                mechanical connections to the remote monitoring panels, CH, and backup IA systems to mitigate effects of a Beyond Design Basis Event.
8.4.5                                            Reflects using LEDs for emergency lighting
[SPS-UCR-2015-017]                                systems.
8.4.6                                            Updated to reflect the TSC Alternate Power
[FS-2008-005]                                    Source - Final Package 6.2.2.2.4, 9.3.2.2.3                              Updated to reflect MOVs with the pressure
[SPS-UCR-2010-027]                                locking modification Table 14.5-6                                      Reflects the Westinghouse LBLOCA error
[SPS-UCR-2015-011]
10.3.3.1, 14b.5.1.6.1, 18.2.1                    Update reflects Relocation of TS augmented
[SPS-UCR-2015-016]                                inspection requirements (except RCP flywheel) to the TRM 2.2.1.2, Table 2.2-8, Table 2.2-9, Table 11A-4,  Revised the Primary Met Tower Instrument Table 11A-5, Table 11A-6, Table 11A-7            Height
[SPS-UCR-2015-018]
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                                6 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 4709/30/15 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
6.2.2.2.4                                        Reflects additional MOV pressure locking
[SPS-UCR-2011-001]                              valve modifications.
3.5.2.1, 3.5.2.1.2, Table 3.5-3, Figure 3.5-9    Reflects implementation of the Westinghouse
[SPS-UCR-2015-006]                              integral nozzle design 9.8.1, 9.8.2, Table 9,8-1, 9.10.1, 10.3.9.3,    Reflects the Compressed Air System Upgrade Table 10.3-4, Figure 10.3-11
[SPS-UCR-2010-010]
9.10.1                                          Update to include the Beyond Design Basis
[SPS-UCR-2013-014]                              Storage Building 3.5.2.3                                          Reflects Re-Insertion of Secondary Source
[SPS-UCR-2014-001]                              Assemblies - Bounding Configuration 14.5.3.4.1, References 55, 56, 57, 58, 59, and  Update to include Beyond Design Basis 60, Table 14.5-18, 15.6.2.1, 15.6.2.2.1          Offsite Communications
[SPS-UCR-2015-014]
3.6.1.1                                          Revised Direct Power Distribution
[SPS-UCR-2015-005]                              Measurements for Start-Up to be made at 50%
RTP rather than 30% RTP Figure 8.3-1                                    Update to include the 500kV Switchyard
[SPS-UCR-2015-013]                              Circuit Breaker CB58202 Tie-in Interim Package 8.3, Figure 8.3-1                                Reflects Removal of the 1G/2G 34.5KV
[SPS-UCR-2014-003]                              Overhead Feeders 14.2 Refs, 14.3 Refs, 14B Refs                  Incorporates Topical Report VEP-FRD-41,
[SPS-UCR-2015-003]                              Rev. 02.
4.2.2.4, 9.1.2.6.9, 9.1.2.6.12, 9.1.2.6.13      Reflects removal of the RCP Floating Ring
[SPS-UCR-2015-004]                              Seal.
Table 5.4-17, Table 6.2-12, Figures 6.3-6        Update reflects the revised Surry through 6.3-13, 8.5                              Recirculation Spray Pump NPSH.
[SPS-UCR-2015-002]
18.2.9                                          License Renewal - update clarifies the
[SPS-UCR-2014-024]                              responsibilities for General Condition Monitoring.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                              7 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 4709/30/15 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
9.10.1, 9.10.4.14                                Update reflects Beyond Design Basis
[SPS-UCR-2014-010]                                installation of spent fuel pool external make-up water source.
3.2.1, 3.5.2.6.2.1, 3.5 Refs                      Update reflects Westinghouse revised clad
[SPS-UCR-2014-019]                                corrosion model for ZIRLO and Optimized ZIRLO.
3.2.3.3, 3.2 Refs, Table 3.2-1, 3.3.2.3, 3.4.2.3, Update reflects discussion of the W-3 3.4.3.2, 3.4 Refs, 4.2.9, 14.1, 14.1 Refs,        Alternate DNB correlations approved in 14.3.2.1, 14.3.2.3                                Appendix D to DOM-NAF-2-P-A and
[SPS-UCR-2014-021]                                increase to technical specification minimum temperature for criticality.
9.5.1                                            Update reflects installation of wide range
[SPS-UCR-2013-007]                                spent fuel pool instrumentation.
18.2.19, Table 18-1                              Update reflects that work control inspections
[SPS-UCR-2014-012]                                for license renewal are required to be performed by a VT qualified individual.
5.5.3, 5.5.4, 5.5.6, 5.5.7                        Update replaces reference to Regulatory
[SPS-UCR-2014-017]                                Guide 1.163 with NEI 94-01, Revision 3-A.
Figure 9.12-1                                    Updated figure for Fuel Transfer System.
[SPS-UCR-2014-018]
18.2.16, 18.5 Refs                                Modify reflects program name change from
[SPS-UCR-2014-020]                                Secondary Piping and Component Inspection program to Flow Accelerated Corrosion program.
Revision 46Updated Online 09/30/14 Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
Table 9.10-1                                      Update corrects horsepower value for the
[SPS-UCR-2009-009]                                replacement diesel-driven fire pump.
9.10.2.2.2, Table 9.10-1                          Update reflects replacement of the
[FS-2008-010]                                    diesel-driven fire pump.
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                              8 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 46Updated Online 09/30/14 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                  where indicated in brackets.
9.10.2.6, 9.10.4.5, 9.10.4.6                  Clarified description of the Appendix R
[SPS-UCR-2014-008]                            equipment located in Normal Switchgear and Cable Tray Rooms.
9.10.2.2.2, 9.10.4.24, Table 9.10-1            Update reflects replacement of the
[SPS-UCR-2014-011]                            diesel-driven fire pump fuel tank.
3.5.2.3, 9.1.2.3.1, 9.1.2.3.2.5                Update reflects the re-insertion of secondary
[SPS-UCR-2014-009]                            source assemblies for Unit 2.
11.2.3, 11.3.2.10, 11.3 Refs                  Radiation protection description updated to
[SPS-UCR-2014-006]                            include the Steam Generator Storage Facility.
Table 14.5-6                                  Table updated to reflect a post analysis of
[SPS-UCR-2014-007]                            record evaluation performed to assess the effect of an error in the HOTSPOT burst strain model on peak cladding temperature for the large break loss of coolant accident.
5.1, Table 5.4-11, Table 5.4-12, Table 5.4-13, Update implements revised LOCA Table 5.4-17, Figure 5.4-3, Figure 5.4-4,      containment safety analysis.
Figure 5.4-5, Table 6.2-4, Table 6.2-13, Figure 6.3-6, Figure 6.3-10
[SPS-UCR-2014-004]
9.10.2.2.1                                    Updated the Fire Protection System
[SPS-UCR-2014-002]                            description to reflect backup water supply.
10.3.5.2                                      Updated the Condensate System description
[SPS-UCR-2014-005]                            to reflect use as backup water for the Fire Protection System in an emergency.
4.1.7.3, 4.1 Refs                              Update reflects the Westinghouse documents
[SPS-UCR-2013-017]                            related to MUR Uprate Fluence Evaluations.
Table 9.7-1                                    Update reflects replacement of the last (4 of 4)
[SPS-UCR-2012-003]                            containment sump pump.
Figure 8.3-1                                  Update reflects final configuration of 34.5 kV
[SPS-UCR-2013-013]                            switchyard modifications.
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                                9 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 46Updated Online 09/30/14 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
Table 14.5-6                                    Update reflects post analysis of record
[SPS-UCR-2013-011]                              evaluation performed to assess the effects of revised heat transfer coefficient multiplier distributions on peak cladding temperature for the large break loss of coolant accident.
9.10.2.1                                        Update reflects Fire Detection System
[FS-2007-007]                                  replacement - final configuration.
14.5.1.6, 14.5.3.2, 14.5, 15A.3.3, 15.A.6,      Update reflects the updated reactor vessel 15A, Table 15A-5, Table 15A-6, Table 15A-7,    lower radial key stiffness value.
Table 15A-8, Table 15A-9
[SPS-UCR-2013-009]
3.5.2.1, 3.5.2.1.4, 3.5, Figure 3.5-10          Update reflects incorporation of the Robust
[SPS-UCR-2013-010]                              Protective Grid and modified Debris Filter Bottom Nozzle to the 15 x 15 upgrade fuel assemblies.
15.5.1.11.2                                    Modify corrected the tornado missile velocity
[SPS-UCR-2013-015]                              requirement.
Revision 4509/30/13 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
14.3.3.2.3.1, 14.3.3.2.3.2, 14.3.3.2.3.3,      Reflects implementation of a revised rod 14.3.3.2.3.4, Table 14.3-6, Figure 14.3-25,    ejection analysis (ETE-NAF-2013-0052, Figure 14.3-27                                  Rev. 0).
[SPS-UCR-2013-008]
9.10.4.12                                      Update reflects removal of the stator cooler
[SPS-UCR-2013-004]                              oil collection trays from the reactor coolant pump oil collection system.
Table 9.7-1                                    Update reflects replacement of 3 of 4
[SPS-UCR-2013-001]                              containment sump pumps.
9.8.1, 9.8.2, 9.8.3, Table 9.8-1, Figure 9.8-1, Update reflects interim configuration of the 9.10.1                                          compressed air system upgrade.
[SPS-UCR-2013-002]
 
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Revision 4509/30/13 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                  where indicated in brackets.
Table 4.1-5, 9.1.2.1                          Update reflects all reactor coolant pumps now
[SPS-UCR-2011-026]                            using Flowserve N-9000 seal.
10.3.1.4, 10.3.5.2, Figure 10.3-8            Condensate System description updated to
[SPS-UCR-2013-005]                            reflect installation of Unit 2 air in-leakage subsystem.
11.3.3, 11.3.3.14                            Updated description for new monitors on
[SPS-UCR-2011-009]                            main steam lines and turbine driven auxiliary feedwater pump.
7.2.2.1.1, 8.2                                Station service transformers description
[SPS-UCR-2011-019]                            updated to reflect replacement cables.
18.2.7                                        License renewal section updated to correctly
[SPS-UCR-2011-020]                            identify damper housings inspection requirements.
18.2.9, 18.2.19                              License renewal section updated to clarify
[SPS-UCR-2011-032]                            commitments associated with general condition monitoring and work control process.
18.1.2, Table 18-1                            License renewal section updated to indicate
[SPS-UCR-2012-006]                            commitment 9 is now complete.
18.2.15, Table 18-1                          License renewal section updated to indicate
[SPS-UCR-2012-007]                            commitment 14 is now complete.
Figure 9.9-1                                  Service Water System figure updated to
[SPS-UCR-2012-013]                            reflect Unit 1 flash evaporation demineralizer assembly demolition.
2.5.3.1, Table 2.5-2                          Additional information clarifies earthquake
[SPS-UCR-2012-012]                            history is based on a specific timeframe.
Table 14.5-6                                  Table updated to reflect post analysis of
[SPS-UCR-2012-005]                            record evaluation performed to assess the effects of fuel thermal conductivity degradation on peak cladding temperature for the large break loss of coolant accident.
Figure 3.5-9                                  Figure modified to add fuel type descriptor
[SPS-UCR-2012-010]                            that was previously omitted.
 
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Revision 4409/27/12 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
9.10.2.1                                        Fire Detection System updated to reflect
[SPS-UCR-2012-008]                              replacement of some of the Robertshaw panels with SimplexGrinnell panels.
Table 9.5-3                                    Table updated to reflect alternate power
[SPS-UCR-2010-028]                              sources for the spent fuel pool pump motor.
10.3.1.2                                        Steam generator blowdown discussion
[SPS-UCR-2012-001]                              updated to reflect rerouting of piping.
Table 9.13-1                                    Main control room and emergency switchgear
[SPS-UCR-2011-029]                              and relay room ventilation data updated to reflect minimum air flow required to maintain design ambient conditions following a bounding event.
18.2.15                                        License Renewal commitment on reactor
[SPS-UCR-2011-031]                              vessel internals guide cards updated.
14.5.1.7, Table 14.5-5, Table 14.5-6            Best estimate large break loss of coolant
[SPS-UCR-2012-002]                              accident analysis description updated to reflect change to containment heat sink surface areas.
10.3.5.2, Figure 10.3-9                        Update reflects installation of the
[SPS-UCR-2009-001]                              ultrasonic flowmeters in the feedwater lines.
9.1.2.6.5                                      Deborating demineralizer discussion updated
[SPS-UCR-2010-024]                              to reflect use of deborating vessel as cation demineralizer.
14.2.9.2.4.2, Table 14.2-2, Table 14.2-4,      Updated design basis accident radiological 14.4.1.2.1, 14.4.1.2.2, 14.4.1.3.1, 14.4.1.3.2, analyses for the fuel handling accident and 14.4, Table 14.4-1, Table 14.4-2, Table 14.4-5 locked rotor analysis.
[SPS-UCR-2011-008]
11.1                                            Updated radiation protection description to
[SPS-UCR-2011-023]                              reflect an upgrade to the Stations self contained breathing apparatus.
10.3.5.2                                        Auxiliary feedwater discussion updated for
[SPS-UCR-2010-026]                              use of Carbohydrazide for startup of Unit 1.
 
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Revision 4409/27/12 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
10.3.5.2                                        Auxiliary feedwater discussion updated for
[SPS-UCR-2011-006]                              use of Carbohydrazide for startup.
18.1.3, Table 18-1                              License Renewal commitment on tank
[SPS-UCR-2011-014]                              inspections updated.
18.1.4                                          License Renewal commitment on non-EQ
[SPS-UCR-2011-028]                              cable inspections updated.
18.2.19                                          License Renewal completion of work control
[SPS-UCR-2011-030]                              audit commitment updated.
1.2.7, Figure 10.2-3, Figure 10.2-4, 10.3.3.1,  Updated descriptions and associated analyses 10.3 Refs, Figure 10.3-1, 14.2.13, 14.2.13.1,    to reflect Unit 1 turbine retrofit.
14.2.13.2, 14.2.13.3, 14.2 Refs, Figure 14.2-72, Figure 14.2-73, Figure 14.2-74, Figure 14.2-75, Figure 14.2-76, Figure 14.2-77, Figure 14.2-78
[SPS-UCR-2009-017]
Revision 4309/29/11 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
4.1.7.1, 4.1 Refs, Table 4.1-14, Table 4.1-15,  Update reflects increase to the cumulative 4.2.5, 4.3.3.2, 4.3.4, 4.3 Refs, Table 4.3-3,    core burnup applicability limit (effective full Table 4.3-4                                      power years) for reactor coolant system
[SPS-UCR-2010-007]                              pressure/temperature limits, low temperature overpressure protection system setpoints and low temperature overpressure protection system enabling temperature, to 48 effective full power years.
Table 3.2-1                                      Modification reflects correction of departure
[SPS-UCR-2011-025]                              from nucleate boiling ratio limit type on DNBR Limits Table.
6.2.2.2.4                                        Update reflects current listing of motor
[SPS-UCR-2010-017]                              operated valves that incorporate a pressure locking modification.
 
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Revision 4309/29/11 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                  where indicated in brackets.
18.1.2, 18.2.6, Table 18-1                    License Renewal completion of concrete
[SPS-UCR-2011-010]                            aging commitment updated.
18.3.5.3, Table 18-1                          License Renewal implementation of Alloy
[SPS-UCR-2011-011]                            Management Program commitment updated.
18.2.7, Table 18-1                            License Renewal completion of fire protection
[SPS-UCR-2011-012]                            piping aging effects commitment updated.
18.2.19                                      License Renewal Work Control Process audits
[SPS-UCR-2011-016]                            commitment updated.
18.2.7, Table 18-1                            License Renewal completion of fire protection
[SPS-UCR-2011-017]                            sprinkler commitment updated.
18.3.2.4                                      License Renewal added dates the inspection
[SPS-UCR-2011-021]                            of the pressurizer surge lines was completed.
Table 18-1                                    License Renewal completion of worker
[SPS-UCR-2011-022]                            qualification commitment updated.
6.2.2.2.3, 9.1.2.6.21                        Globe valve description updated.
[SPS-UCR-2010-015]
9.10.4.12                                    Fire protection description updated to reflect
[SPS-UCR-2010-031]                            addition of an oil collection assembly on each reactor coolant pump stator cooler.
8.2, 10.3.3.2, Table 10.3-4, Figure 10.3-11  Update reflects upgrading the isolated phase
[SPS-UCR-2010-032]                            bus duct for both Units.
3.5.2.2                                      Updated section to reflect a replacement batch
[SPS-UCR-2010-014]                            of enhanced performance control rod assemblies will be placed in service for cycle 24 operation.
4.1.7.1, 4.1 Refs, Table 4.1-12, Table 4.1-13 Updated the reactor vessel surveillance
[SPS-UCR-2011-007]                            capsule withdrawal schedule for 60-year operation.
2.3.1.2.2                                    Updated emergency service water pump
[SPS-UCR-2010-008]                            house discussion to reflect addition of missile shield.
 
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Revision 4309/29/11 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
9C.2                                                Appendix on flooding updated to reflect the
[SPS-UCR-2011-003]                                  high level stop log roller removal.
14.2.9.2.4.3                                        Modified locked rotor accident discussion to
[SPS-UCR-2011-005]                                  make it consistent with other sections.
1.1.5, 1.1.6, 3.2.2.1, 3.2.2.7, 3.2.3.3, 3.2 Refs,  Updated descriptions and associated analyses Table 3.2-1, Table 3.2-2, Table 3.2-3,              to reflect implementation of the Westinghouse 3.3.3.2.2, 3.4.1, 3.4.1.1.2, 3.4.1.1.4, 3.4.1.2,    15 x 15 upgrade fuel design.
3.4.1.3, 3.4.2, 3.4.2.1, 3.4.2.2, 3.4.2.3, 3.4.3.1, 3.4.3.2, 3.4.3.3, 3.4.3.4, 3.4.3.5, 3.4.3.6 (new),
3.4 Refs, Table 3.4-1, 3.5, 3.5.2.1, 3.5.2.1.2, 3.5.2.1.3, 3.5.2.1.4, 3.5.2.1.5, 3.5.2.6.1, 3.5 Refs, Table 3.5-3, Figure 3.5-9, Figure 3.5-17 (new), Table 4.3-1, Table 4.3-2, 9.1.2.3.2.1, 9.1.3.6, 9.1 Refs, 14.1, 14.1 Refs, 14.2.1.1, 14.2.1.2, 14.2.2.1, 14.2.2.2, 14.2.4.1, 14.2.7.2, 14.2.7.3.2, 14.2.7.4, 14.2.8.1, 14.2.9.1.1, 14.2.9.1.2, 14.2.9.1.7, 14.2.9.2.1, 14.2.9.2.2.2, 14.2.10.2, 14.2.10.3, 14.2 Refs, 14.3.2.1, 14.3.2.3, 14.3.3.2.1, 14.3 Refs, 14.4.1.1, 14.4 Refs, 14.5.1.5, 14.5.1.6, 14.5.1.7, 14.5.2.4.2, 14.5.2.5, 14.5.2.6, 14.5.3.4.1, 14.5.3.4.2, Table 14.5-1, Table 14.5-2, Table 14.5-3, Table 14.5-5, Table 14.5-6, Table 14.5-7, Table 14.5-13, Table 14.5-17, Table 14.5-18 (new),
Figure 14.5-1, Figure 14.5-2, Figure 14.5-3, Figure 14.5-4, Figure 14.5-5, Figure 14.5-6, Figure 14.5-7, Figure 14.5-8, Figure 14.5-9, Figure 14.5-10, Figure 14.5-11, Figure 14.5-12, Figure 14.5-13, Figure 14.5-14, Figure 14.5-76, 15A.5, 15A.5.2.5, 15A.6 (new), 15A Refs, Table 15A-8 (new), Table 15A-9 (new)
[SPS-UCR-2009-023]
 
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Revision 4309/29/11 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                  where indicated in brackets.
1.2.7, Figure 10.2-1, 10.3.1.1, 10.3.3.1,    Updated descriptions and associated analyses 10.3 Refs, Figure 10.3-1, 14.2.13.1 (new),    to reflect Unit 1 turbine retrofit.
14.2.13.2, 14.2.13.3, 14.2 Refs, Figure 14.2-81, Figure 14.2-82, Figure 14.2-83 (new), Figure 14.2-84 (new),
Figure 14.2-85 (new), Figure 14.2-86 (new),
Figure 14.2-87 (new)
[SPS-UCR-2009-012]
1.1.6, 3.5 Refs                              Discussion corrected to state that mid-grids
[SPS-UCR-2011-004]                            are made of ZIRLO and NOT Optimized ZIRLO.
Table 9.7-1                                  Updated pump data for Unit 1 containment
[SPS-UCR-2009-024]                            sump pump replacements.
Table 4.1-5, 9.1.2.1                          Revised description of reactor coolant pump
[SPS-UCR-2010-012]                            seal leakoff to reflect Flowserve N-9000 seals.
8.2, 10.3.3.2, Table 10.3-4, Figure 10.3-11  Revised discussion on isolated phase bus duct
[SPS-UCR-2010-013]                            coolers to reflect Unit 1 upgrade.
9.10.4.12                                    Updated discussion to reflect addition of
[SPS-UCR-2011-002]                            reactor coolant pump stator cooler outlet trough oil collection assemblies.
Table 18-1                                    Updated license renewal commitment related
[SPS-UCR-2010-018]                            to alloy 82/182 weld material.
18.2.15, 18.5 Refs                            Updated license renewal commitment to
[SPS-UCR-2010-022]                            perform enhanced inspections of reactor vessel internals in accordance with EPRI MRP-227.
3.5.2.2                                      Reflects replacement of enhanced
[SPS-UCR-2010-025]                            performance control rod assemblies for Unit 1 cycle 24 operation.
9.10.4.8, 9.10 Refs, 9.13.3.1                Removed requirement to use 1-VS-F-58B
[SPS-UCR-2010-033]                            after an Appendix R fire to ventilate the charging pump cubicles.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                                16 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 4309/29/11 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
1.1, 1.1.2, 1.1 Refs, 3.2.1, 3.3.3.2.2, 3.4.1.3,  Reflects the Measurement Uncertainty Table 3.4-1, 4.1.7.1, 4.1.7.3, 4.1.7.4, 4.1 Refs, Recapture Power Uprate.
Table 4.1-2, Table 4.1-4, Table 4.1-5, Table 4.1-8, Table 4.1-14, Table 4.1-15, 4.2.5, 4.3.3.2, 4.3.4, 4.3 Refs, 5.3.1.1, 5.4.1.2, 5.4.3.1, 5.4.3.2.2, Table 5.4-1, Table 5.4-17, 6.2.1.1, 7.2.2.5, 7.3.2.6.1, 8.1, 9.1.2.2, 9.1.2.3.2.6, Table 9.1-4, Table 9.1-5, Table 9.1-6, Table 9.1-7, 9.4, 9.5, 9.9, 9.13.3.6, Figures 10.2-1 thru Figure 10.2-4, 10.3.1, 10.3.1.1, 10.3.1.2, 10.3.2, 10.3.3, 10.3.4, 10.3.5,10.3.5.2, 10.3.5.3, 10.3.9, Table 10.3-4, 11.2.5.1, Table 11.2-2, Table 11.2-3, 11.3.2.2, Table 11.3-3, Table 11A-1, 14.1, 14.1 Refs, 14.2.1.1, 14.2.1.2, 14.2.2, 14.2.2.1, 14.2.2.3, 14.2.4.1, 14.2.4.2, 14.2.4.3, 14.2.7.1, 14.2.7.2, 14.2.7.3.1, 14.2.7.3.2, 14.2.8, 14.2.8.1, 14.2.8.2, 14.2.8.3, 14.2.9.1, 14.2.9.1.1, 14.2.9.1.2, 14.2.9.1.6, 14.2.9.2.2.1, 14.2.9.2.2.2, 14.2.9.2.4.1, 14.2.9.2.4.3, 14.2.10.2, 14.2.10.3, 14.2.10.4.2, 14.2.10.5, 14.2.11.1, 14.2 Refs, Table 14.2-1, Table 14.2-2, Table 14.2-3, Table 14.2-4, Figure 14.2-1, Figure 14.2-2, Figure 14.2-3, Figure 14.2-4a, Figures 14.2-5 thru Figure 14.2-14, Figure 14.2-16, Figure 14.2-21, Figure 14.2-23, Figures 14.2-27 thru Figure 14.2-42, Figure 14.2-45, Figure 14.2-49, Figure 14.2-50, Figure 14.2-51, Figure 14.2-55, Figure 14.2-56, Figure 14.2-62, Figure 14.2-67,
[SPS-UCR-2009-022]
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                                17 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 4309/29/11 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
Figure 14.2-68, 14.3.1.2, 14.3.1.3, 14.3.1.4.3,  (continued) 14.3.1.4.4, 14.3.2.1, 14.3.2.3, 14.3.2.4.2, 14.3.2.4.4, 14.3.2.5, 14.3.3.1.2, 14.3.3.2.2, 14.3.3.2.2.5, Tables 14.3-4 thru 14.3-11, Table 14.3-13, Table 14.3-15, Table 14.3-16, Figures 14.3-1 thru 14.3-9, Figure 14.3-14, Figure 14.3-19, Figure 14.3-24, Figure 14.3-26, 14.4.1.3.1, 14.4.2.1, Table 14.4-6, 14.5.2.3, 14.5.5, Table 14.5-1, Table 14.5-13, Appendix 14A, Table 14A-1, Table 14A-2
[SPS-UCR-2009-022]
14.3.1.4.4, 14.3.2.4.4                          Removed discussion of 20 gpd primary to
[SPS-UCR-2010-030]                              secondary leakage limit for Unit 1 B steam generator.
Table 9.7-1                                      Updated pump data for Unit 2 containment
[SPS-UCR-2010-034]                              sump pump replacements.
10.3.5.2, Figure 10.3-9                          Update reflects installation of the ultrasonic
[SPS-UCR-2009-014]                              flowmeters in the feedwater lines.
10.3.1.2                                        Description of the feedwater flow distribution
[SPS-UCR-2010-020]                              removed to reflect new J-nozzle design, which provides even distribution.
Revision 4209/30/10 Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
14.2.9.1.6, Figure 14.2-49, Figure 14.2-50,      Loss of Reactor Coolant Flow Analysis Figure 14.2-55, Figure 14.2-56                  updated to reflect the DNB transient for the
[SPS-UCR-2010-019]                              underfrequency and undervoltage events in the LOFA reanalysis.
Table of Contents, List of Tables, List of      Table of Contents modified to include the Figures for following chapters: 9, 11, 14, & 15 Appendices Table of Content.
[SPS-UCR-2010-021]
 
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Revision 4209/30/10 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
9.10.1, 9.10.2.2.5, 9.10.4.19                    Fire Protection discussions updated to include
[SPS-UCR-2009-027]                                the addition of the Turbine Deck Security Office.
15A.3.2, 15A Refs                                Modified references to reflect procedures
[SPS-UCR-2010-009]                                updated.
9.9.2                                            Modified the total flow for each intake
[SPS-UCR-2010-011]                                structure to be consistent with the circulating water pump flow rate.
7.7.2, 11.3.6                                    Removed discussion of the Main Control
[SPS-UCR-2010-003]                                Room Bottled Air System.
11.2.3.2                                          Final configuration reflects portions of the
[FS-2003-045]                                    blowdown water treatment subsystem that are no longer used at the station.
9.10.2.1                                          Interim configuration reflects portions of the
[SPS-UCR-2010-002]                                Surry Fire Detection System that have been replaced.
11.2.3.2                                          Corrects FS 2003-045 to reflect portions of the
[SPS-UCR-2010-005]                                blowdown water treatment subsystem that is no longer in use.
2.1.5.2, 2.1 Refs                                Adds a new reference to Chapter 2.
[SPS-UCR-2010-006]
6.2.2.2.13, 6.3.1.2.5                            Description of the containment strainer
[SPS-UCR-2009-003]                                assembly seals was updated to reflect installation of the U2 seal closure frames.
7.2.1.1, Table 7.5-2, 7.7.2, 9.10.4.17, 9.13.2,  Discussion of the Main Control Room Bottled 9.13.3.6, 9.13.4.1, 9.13.4.2, Table 9.13-1,      Air System was removed.
14.2.9.2.4.3, 14.3.1.4.4, 14.3.2.4.4, 14.4.1.2.1, 14.4.1.3.1, 14.5.5.2
[SPS-UCR-2009-026]
10.3.5.2                                          A discussion was added describing the use of
[SPS-UCR-2009-028]                                Carbohydrazide for startup of Unit 2 using Auxiliary Feedwater.
9.1, 9.1.2.6.23, Figure 9.1-1                    Reflects installation of Zinc Injection System
[FS 2007-014]                                    for Unit 1.
9.1, 9.1.2.6.23, Figure 9.1-1                    Reflects final configuration of Zinc Injection
[FS 2008-023]                                    System.
 
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Revision 4209/30/10 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
4.1.7.1, 4.1.7.3, Table 4.1-13                  Clarifies the capsule locations were original
[SPS-UCR-2009-021]                              locations. Annotates Table to reflect relocation of Surry Unit 2 surveillance capsule U.
Table 9.7-1                                      Corrected the containment sump pump data to
[SPS-UCR-2009-025]                              reflect the current pumps.
18.3.5.6                                        Updated discussion on reactor coolant pump
[SPS-UCR-2009-011]                              and ASME code case N-481.
4.2.2.4, Table 4.1-5, 9.1.2.1                    Revised description of reactor coolant pump
[SPS-UCR-2009-019]                              seal arrangement to reflect the Flowserve N-9000 seal.
14.5.2.1, 14.5.2.3, 14.5.2.4.1, 14.5.2.4.2,      Revised to incorporate the reanalysis of the 14.5.2.5, 14.2.5.6, 14.5 Refs, Table 14.5-13,    Westinghouse small break loss of coolant Table 14.5-14, Table 14.5-15, Table 14.5-16,    accident (SBLOCA).
Table 14.5-17, Figure 14.5-15 through Figure 14.5-76
[SPS-UCR-2009-008]
Revision 4109/30/09 Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
Figure 10.2-1 (sh 2), 10.3.3.2                  Reflects the Unit 2 main generator change in
[FS 2008-011]                                    hydrogen pressure.
10.3.5.2, 10.3.5.3                              Clarified description of AFW system
[FS 2007-020]                                    alignments to ensure minimum AFW flow requirements are met for design basis accident with the RCS above 350 degrees for both Units.
KWI                                              Removed key word index.
[SPS-UCR-2009-020]
8.3, Figure 8.3-1                                Reflects the redirection of the 531 transmission
[SPS-UCR-2009-010]                              line to Suffolk substation.
14.3.1.4.4, 14.3.2.4.4                          Reflects a 20 gpd leakage limit for Unit 1 B
[SPS-UCR-2009-013]                              steam generator for operating cycle 23.
6.2.2.2.13, 6.3.1.2.5                            Added a description of Unit 1 seal closure
[FS 2008-024]                                    frames installed over the containment sump strainer flexible metal seals.
 
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Revision 4109/30/09 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
9.4.3.5                                          Raised the upper pH limit of the charging pump
[SPS-UCR-2009-005]                              component cooling water system.
8.3, Figure 8.3-1, 8.5                          Incorporates addition of Bus 7 and breakers in
[FS 2005-026]                                    switchyard.
6.2.2.2.6, 6.2.4, 6.2.4.1.5, 6.2 Refs            Added new section, Gas Accumulation in
[SPS-UCR-2009-004]                              ECCS Piping in response to Generic Letter 2008-01.
14.5.1.7, Table 14.5-5, Table 14.5-6            Incorporates increase of carbon steel surface
[SPS-UCR-2009-006]                              area in containment and the impact on the best estimate large break loss of coolant accident analysis.
9B.1.1, 9B.2.1, 9B.1 Refs, Table 9B.2-1          Updated the discussion on heavy loads to
[FS 2008-021]                                    include reliance on a RV head drop analysis and revised the weight of the U1 RV head and lifting device.
5.4.2.1.7, Table 5.4-12, Table 5.4-13,          Implements changes to the Surry containment Table 5.4-17, 6.1, 6.2.3.11, 6.3.1.3.2          analysis using revised IRS/ORS pump
[SPS-UCR-2009-002]                              flowrates.
9.4.3.3                                          Removed description of Chilled Water
[FS 2007-028]                                    circulating pump low suction pressure trip.
5.4.2.1.7, Table 5.4-12, Table 5.4-13,          Incorporates increasing the SW inlet (river Table 5.4-17, Figure 5.4-3, Figure 5.4-4,        water) temperature to 100 degrees in Figure 5.4-5, 6.3.1.4.3, 9.4.1.1, 9.4.3.3, 9.9.1 accordance with Technical Specification
[FS 2008-017]                                    change request 397.
14.5.1.6, 14.5.1.7, Table 14.5-1, Table 14.5-2,  Incorporated the results of a reanalysis of the Table 14.5-3, Table 14.5-4, Table 14.5-5,        Westinghouse Best-Estimate Large Break Loss Table 14.5-6, Figure 14.5-1, Figure 14.5-2,      of Coolant Accident (BE-LOCA) analysis Figure 14.5-3, Figure 14.5-4, Figure 14.5-5,    using the Automated Statistical Treatment of Figure 14.5-6, Figure 14.5-7, Figure 14.5-8,    Uncertainty Method (ASTRUM).
Figure 14.5-9, Figure 14.5-10, Figure 14.5-11, Figure 14.5-12, Figure 14.5-13, Figure 14.5-14
[FS 2008-022]
18.5 Refs                                        Editorial - Updated UFSAR references to
[FS 2008-025]                                    reflect current revisions for the steam generator management program.
 
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Revision 4109/30/09 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
6.2.2.1.3, 6.2.2.2.13, 6.2.3.11.1, 6.2.3.3,      Updated various sections to reflect compliance 6.2.4.1.4, 6.2 Refs, Table 6.2-3, 6.3.1.2.5,      with GSI-191 for the strainer assembly.
6.3.1.3.1, 6.3.1.3.2, 6.3.1.3.3, 6.3.1.3.4, 6.3.1.4.1, 6.3.1.4.3, 6.3.1.4.4, 6.3 Refs Table 6.3-3
[FS 2007-011]
Table 4.1-1                                      Revised Low-Pressure trip setpoint to be
[FS 2008-013]                                    consistent with TSCR 318.
3.5 Refs, 14.4 Refs                              Updated reference placeholders with standard
[FS 2008-020]                                    reference information.
18.2.11, Table 18-1                              Updated to reflect license renewal
[FS 2008-018]                                    commitments that have been completed.
12.3, 12.3 Refs, KWI                              Added NEI 99-01 as a reference.
[FS 2008-019]
Revision 4009/30/08 Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
2.1.5.2, Table 2.1-4                              Adds limitation on dimethylamine to chemical
[FS 2007-022]                                    section.
9.10.2.2.7                                        Modifies description on the actuation of the
[FS 2008-008]                                    Low Pressure CO2 Fire Protection System dampers.
9.10.4.8, 9.10 Refs                              Reflects that forced ventilation of the charging
[FS 2008-009]                                    pump cubicles is not required after an Appendix R fire.
8.3, Figure 8.3-1, 8.5                            Reflects changes associated with partial
[FS 2008-014]                                    implementation of modification to 34.5 kV switchyard buses 5 and 7.
8.4.1                                            Incorporates the disconnect of the auto start
[FS 2007-019]                                    circuitry for the high pressure heater drain pumps.
6.3.1.3                                          Reflects the installation of the entire sump
[FS 2008-006]                                    strainer for Unit 2.
 
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Revision 4009/30/08 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
8.4.6                                                Incorporates changes associated with partial
[FS 2008-012]                                        implementation of the modification of D transfer bus breaker to supply power to the TSC MCC and TSC UPS from the ACC diesel generator.
Table 9.4-1, Table 9.4-8                            Corrected component cooling water pump
[FS 2008-007]                                        design parameters.
5.4.1.2, 5.4.1.3.3, 5.4.1.3.5.4, 5.4.1.4, 5.4.2.1.6, Incorporates the containment response using 5.4.3, 5.4 Refs, Table 5.4-1, Table 5.4-2,          new mass and energy data tables. Updates the Table 5.4-3, Table 5.4-4, Table 5.4-5,              minimum NPSH valves.
Table 5.4-6, Table 5.4-7, Table 5.4-8, Table 5.4-9, Table 5.4-13, Table 5.4-14, Table 5.4-15, Figure 5.4-1, Figure 5.4-2, Table 6.2-12, Table 6.2-13
[FS 2008-003]
10.3.5.3                                            Updated the total accuracy value for the
[FS 2007-024]                                        auxiliary feed flow loop.
10.3.5.2, 10.3.5.3                                  Incorporated changes associated with the
[FS 2008-001]                                        modification of the operator selector switches for the AFW discharge MOVs.
9.10.4.23                                            Corrected the value of the concrete wall
[FS 2008-004]                                        thickness separating the two fuel oil pump houses.
6.3.1.3, 11.3.2.1, Table 11.3-2, Figure 11.3-2 Modifies text associated with Incore Sump
[FS 2006-024]                                        Room Drain Modifications.
3.5.2.6.1, 3.5 Refs, 14.4.1.1, 14.4 Refs            Modifies lead rod average burnup limit for
[FS 2006-033]                                        Surry fuel.
Figure 6.1-1, 6.2, 6.2.2.2.13, 6.2.3.11.3,          Modifies text to reflect changes associated with Table 6.2-3,Table 6.2-13, 6.3, 6.3.1.2.5, 6.3.1.3, Containment Sump Strainer Design.
6.3.1.4, Table 6.3-1, Table 6.3-3, Figure 6.3-2, Figure 6.3-5
[FS 2007-025]
 
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Revision 4009/30/08 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
1.1.8, 1.4.49, 5.3.4.1, 5.3.4.3, 5.3 Refs,          Performed containment analyses and LOCA Table 5.3-5, 5.4, 5.4.1.1, 5.4.1.3.1, 5.4.1.3.2,    alternate source term analyses to support GSI 5.4.1.3.3, 5.4.1.3.4, 5.4.1.3.5.2, 5.4.1.3.5.3,      191 modifications Unit 1.
5.4.1.3.5.4, 5.4.1.3.5.5, 5.4.1.3.6, 5.4.1.4, 5.4.2, 5.4.2.1, 5.4.2.1.1, 5.4.2.1.2, 5.4.2.1.3, 5.4.2.1.4, 5.4.1.2.5, 5.4.2.1.6, 5.4.2.1.7, 5.4 Refs, Tables 5.4-6, 5.4-7, 5.4-8, 5.4-9, 5.4-10, 5.4-11, 5.4-12, 5.4-13, 5.4-14, 5.4-15, 5.4-16, 5.4-17, 5.4-18, 5.4-19, 5.4-20, 5.4-21, 5.4-22, 5.4-23, 5.4-24, & 5.4-25, Figures 5.4-1, 5.4-2, 5.4-3, 5.4-4, 5.4-5, 5.4-6, 5.4-7, 5.4-8, 5.4-9, 5.4-10, 5.4-11, 5.4-12, & 5.4-13, 6.2.2.1.4, 6.2.3.11.1, 6.2 Refs, Tables 6.2-11, 6.2-12, & 6.2-13, Figures 6.2-3, 6.2-4, 6.2-5, 6.2-6, & 6.2-7, 6.3.1.3, 6.3.1.4, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-11, 6.3-12, 6.3-13, 6.3-14, 6.3-15, 6.3-16, & 6.3-17, 14.5.4, 14.5.5, 14.5.5.2, 14.5.5.3, 14.5 Refs, Tables 14.5-7, 14.5-8,
& 14.5-11, 14B.2.3.3.1, 14B.2.3.3.2.1, 15.5.1.2
[FS 2005-027]
7.6.2.1                                              Removed information that specifies which flux
[FS 2006-035]                                        thimble locations are plugged.
6.3.1.3, 7.5.1.3, Figure 7.5-2, Figure 7.5-3        Modified the refueling water storage tank
[FS 2007-002]                                        engineered safety features actuation system to support GSI 191 containment sump modifications for Unit 1.
7.2, 7.2.1.8.6                                      Added replacement of the Westinghouse
[FS 2007-021]                                        process modules with NUS Scientech modules.
1.1.8, 1.4.49, 14.5.4, 14.5.5, 14.5.5.2, 14.5.5.3, Editorial changes; clarifies final markups for Table 14.5-8, Table 14.5-9, Table 14.5-12,          GSI-191 multiple packages.
15.5.1.2
[FS 2008-002]
5.4.2.1.6, 5.4 Refs                                  Revised text to describe an alternate
[FS 2007-023]                                        containment analysis method that can be used for the calculation of NPSHa for the recirculation spray pumps, and containment pressure and sump temperature response.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                              24 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 4009/30/08 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
14.5.1.1, 14.5.1.2, 14.5.1.3, 14.5.1.4, 14.5.1.5, Incorporated an analysis performed for 14.5.1.6, 14.5.1.7, 14.5.2.5, 14.5 Refs,          LBLOCA using the Westinghouse Tables 14.5-1, 14.5-2, 14.5-3, 14.5-4, 14.5-5,    Best-Estimate Large Break Loss of Coolant
& 14.5-6, Figures 14.5-1, 14.5-2, 14.5-3,        Accident (BE-LBLOCA) analysis 14.5-4, 14.5-5, 14.5-6, 14.5-7, 14.5-8, 14.5-9,  methodology using the Automated Statistical 14.5-10, 14.5-11, 14.5-12, 14.5-13, 14.5-14,      Treatment of Uncertainty Method (ASTRUM).
14.5-15, 14.5-16, 14.5-17, 14.5-18, 14.5-19,      Revised text for consistency and removed 14.5-20, 14.5-21, 14.5-22, 14.5-23, 14.5-24,      unnecessary references.
14.5-25, 14.5-26, 14.5-27, 14.5-28, 14.5-29, 14.5-30, 14.5-31, 14.5-32, 14.5-33, 14.5-34, 14.5-35, 14.5-36, & 14.5-37
[FS 2006-021]
14.5.1.6, 14.5.1.7, 14.5.2.5, Table 14.5-6        Revised table to incorporate a penalty to PCT
[FS 2007-026]                                    for the analysis performed for the LBLOCA analysis using the Westinghouse BE-LBLOCA analysis methodology using ASTRUM.
4.3.4.2                                          Clarified the description of the pressurizer
[FS 2007-013]                                    PORV backup air supply.
14.5.2.5, 14.5.2.6, 14.5 Refs, Table 14.5-15      Updated peak cladding temperature for small
[FS 2007-009]                                    break LOCA analysis for Westinghouse fuel.
14.5 Refs, Table 14.5-5                          Updated peak cladding temperature for large
[FS 2007-010]                                    break LOCA analysis for Westinghouse fuel.
9.1, 9.1.2.6.23, Figure 9.1-1                    Installed the Unit 2 zinc injection system.
[FS 2007-018]
14.2.9.2.4.2, 14.2.9.2.4.3, 14.3.1.4.4,          Revised the steam generator tube rupture and 14.3.2.4.2, 14.3.2.4.4, 14.3 Refs, Tables 14.3-9, main steam line break accident analyses to 14.3-10, & 14.3-15                                reflect the change in the technical specification
[FS 2006-005 & FS 2006-020]                      allowable primary-to-secondary leakage rate.
[10 CFR 50.90 License Amendment]
18.2.11, 18.2.13, 18.2.15                        Corrected the description of the Inservice
[FS 2007-017]                                    Inspection Plan.
 
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Revision 3909/27/07 Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
KWI, 12.4                                            Reflected the audit and review functions
[FS 2007-016]                                        contained in the Nuclear Facility Quality Assurance Program Description.
1.1.8, 1.4.49, 5.3.4.1, 5.3.4.3, 5.3 Refs,          Performed containment analyses and LOCA Table 5.3-5, 5.4, 5.4.1.1, 5.4.1.3.1, 5.4.1.3.2,    alternate source term analyses to support 5.4.1.3.3, 5.4.1.3.4, 5.4.1.3.5.2, 5.4.1.3.5.3,      GSI 191 modifications Unit 2.
5.4.1.3.5.4, 5.4.1.3.5.5, 5.4.1.3.6, 5.4.1.4, 5.4.2, 5.4.2.1, 5.4.2.1.1, 5.4.2.1.2, 5.4.2.1.3, 5.4.2.1.4, 5.4.1.2.5, 5.4.2.1.6, 5.4.2.1.7, 5.4 Refs, Tables 5.4-6, 5.4-7, 5.4-8, 5.4-9, 5.4-10, 5.4-11, 5.4-12, 5.4-13, 5.4-14, 5.4-15, 5.4-16, 5.4-17, 5.4-18, 5.4-19, 5.4-20, 5.4-21, 5.4-22, 5.4-23, 5.4-24, & 5.4-25, Figures 5.4-1, 5.4-2, 5.4-3, 5.4-4, 5.4-5, 5.4-6, 5.4-7, 5.4-8, 5.4-9, 5.4-10, 5.4-11, 5.4-12, & 5.4-13, 6.2.2.1.4, 6.2.3.11.1, 6.2 Refs, Tables 6.2-11, 6.2-12, & 6.2-13, Figures 6.2-3, 6.2-4, 6.2-5, 6.2-6, & 6.2-7, 6.3.1.3, 6.3.1.4, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-11, 6.3-12, 6.3-13, 6.3-14, 6.3-15, 6.3-16, & 6.3-17, 14.5.4, 14.5.5, 14.5.5.2, 14.5.5.3, 14.5 Refs, Tables 14.5-7, 14.5-8,
& 14.5-11, 14B.2.3.3.1, 14B.2.3.3.2.1, 15.5.1.2
[FS 2007-027]
4.1.7.1, 4.1.7.3, 4.1.7.4, 4.1 Refs, Tables 4.1-14  Incorporated the revised RTPTS values
& 4.1-15, 4.2.5, 4.3.3.2, 4.3 Refs, Tables 4.3-3    provided for the Reactor Vessel Integrity
& 4.3-4                                              Program. [10 CFR 50.61]
[FS 2006-015]
4.3.4.2                                              Changed the description of the pressurizer
[FS 2006-022]                                        PORV backup air supply.
Figure 6.1-2, 6.2.2.2.13, 6.2.3.11.3,                Completed partial installation of Unit 2 Tables 6.2-3 & 6.2-12, 6.3.1.2.5, 6.3.1.3,          containment sump strainers to support GSI 191 Tables 6.3-1 & 6.3-3, Figures 6.3-3 & 6.3-5          modifications.
[FS 2006-029]
6.3.1.3, 6.3.1.4, 11.3.2.1, Table 11.3-2,            Added the Unit 2 incore sump room drain to Figure 11.3-3                                        support GSI 191 containment sump
[FS 2006-014]                                        modifications.
 
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Revision 3909/27/07 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
6.3.1.3, Figure 6.3-17, 7.5.1.3, 7.5.2.1,        Modified the Unit 2 refueling water storage Figures 7.5-2 & 7.5-3                            tank engineered safety features actuation
[FS 2006-007]                                    system to support GSI 191 containment sump modifications.
Figures 6.3-2 & 6.3-3                            Modified the Unit 2 outside recirculation spray
[FS 2006-012]                                    pumps test loops.
7.3.2.4                                          Revised the description of pressurizer pressure
[FS 2007-001]                                    control.
7.7.1, 7.9.1, 7.9.3, 8.2, 8.4.4, Figure 8.4-1,  Replaced the intake structure supervisory 9.10.2.1.                                        system in the low level intake structure and in
[FS 2005-015]                                    the main control room.
7.7.2, 7.11.2, 8.4.3                            Updated the description of the power supply
[FS 2005-009]                                    for the remote monitoring panels.
9.1.2.1, 9.1.3.5.3, 9.6.3.1, 9.6.3.2, 9.10.3.3,  Replaced operable terminology with 9C.2, 10.3.1.5, 11.3.4.2, 11.3.4.3, 11.3.4.4    functional terminology in accordance with
[FS 2007-004]                                    Regulatory Issue Summary 2005-20.
Table 9.7-1                                      Updated the description of the component
[FS 2006-034]                                    cooling heat exchanger pit sump pump shaft material.
9.10.4.18                                        Provided additional fire hazard analysis
[FS 2007-005]                                    discussion in order to address Mechanical Equipment Room No. 4.
9.12.9, 9.12.9.1, 9.12.9.2, 9.12.9.3, 19.2 Refs, Revised the description of handling ISFSI cask 9B.1.5                                          systems.
[FS 2007-003]
9.14.2, Table 9.14-1                            Added the dry shielded canister drain and
[FS 2005-024]                                    reflood pumps.
Table 9.14-1                                    Replaced the spent fuel storage cask vacuum
[FS 2004-017]                                    pumps.
10.3.1.1, 14.2.13                                Modified the turbine overspeed protection
[FS 2006-032]                                    control permissive logic and circuitry.
10.3.5.2, 10.3.5.3                              Defeated the auto-open function for auxiliary
[FS 2006-030]                                    feedwater flow isolation motor-operated valves.
Figure 10.3-10                                  Replaced chemical feed system pumps.
[FS 2005-025]
 
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Revision 3909/27/07 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
11.2.6.2, 11.3.3, 11.3.3.1, 11.3.3.2, 11.3.3.13,    Replaced ventilation system radiation 11.3.3.14, Tables 11.3-5, 11.3-6, & 11.3-8          monitors.
[FS 2005-012]
14.2.11.1, 14.2.11.1.1, 14.2.12,                    Revised the analysis description of auxiliary Figures 14.2-73, 14.2-74, 14.2-75, & 14.2-76        feedwater flow following loss of normal
[FS 2006-031]                                      feedwater and loss of AC power events.
18.1.4, 18.2.6, 18.2.13, 18.2.19, Table 18-1        Reflected the completion of License Renewal
[FS 2006-025]                                      Commitment Item Nos. 4, 12, 18, 26, and 27.
18.3.2.4, Table 18-1                                Reflected the completion of License Renewal
[FS 2007-008]                                      Commitment Item No. 24.
Revision 3809/29/06 Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
2.1.2.1                                            Revised the Exclusion Area Boundary to be the
[FS 2006-023]                                      site boundary. [10 CFR 50.90]
2.2.1.2                                            Clarified the description of the applicability of
[FS 2004-016]                                      Regulatory Guide 1.23 to meteorological equipment.
3.1, 3.1 Refs, 3.3.1, 3.3.2.3, 3.3.2.13, 3.3.3.2.2, Incorporated the use of integral fuel burnable 3.5.2.1.5, 3.5.2.5, 3.5.2.6.3, 3.5.2.6.4,          absorber (IFBA) rods.
Table 3.5-3, Figure 3.5-15, 3.6.3.13
[FS 2006-006]
Figures 6.3-2 & 6.3-3                              Modified the Unit 1 outside recirculation spray
[FS 2006-004]                                      pumps test loops.
7.6.2.1                                            Isolated the flux thimble tube at location
[FS 2006-017]                                      1-RC-TW-J3.
8.5                                                Modified the #1 and #3 emergency diesel
[FS 2004-023]                                      generators auto start circuits.
8.5                                                Aligned the description of engineered
[FS 2006-009]                                      safeguards equipment powered by each emergency bus with the list contained in Technical Specification 3.16 Basis.
9.8                                                Corrected the description of the containment
[FS 2006-016]                                      instrument air compressors capacity.
 
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Revision 3809/29/06 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                  where indicated in brackets.
9C.1.2                                        Augmented the description of the water level
[FS 2005-013]                                  monitoring system to include the Amertap pit monitors and a description of the system power supply.
10.3.1.1                                      Clarified the description of the turbine-driven
[FS 2005-008]                                  auxiliary feedwater pump design and operating conditions.
10.3.3.2                                      Added the new Unit 1 generator and exciter
[FS 2005-022]                                  ratings and revised the cooling water flow value for the Unit 1 generator hydrogen coolers.
10.3.5.4                                      Revised the description of auxiliary feedwater
[FS 2006-010]                                  pump surveillance test and inspections.
[10 CFR 50.90]
11.2.3.1.7, 11.2.4.1.1, 11.2.4.1.5, 11.2.4.2.2 Corrected the description of Radwaste Facility
[FS 2005-016]                                  reducing and processing functions.
14.3.3.2.1, 14.3.3.2.3.1, 14.3.3.2.3.2,        Reanalyzed the control rod assembly ejection 14.3.3.2.3.3, 14.3.3.2.3.4, 14.3 Refs,        accident in support of the transition to Integral Table 14.3-6, Figures 14.3-24, 14.3-25,        Fuel Burnable Poison (IFBA) fuel.
14.3-26, and 14.3-27
[FS 2006-001]
14.5.1.6, 14.5.2.5, 14.5.2.6, 14.5 Refs,      Incorporated the peak clad temperature Tables 14.5-5 & 14.5-15                        penalties and benefits for the large break and
[FS 2006-003]                                  small break LOCA associated with implementation of IFBA fuel. [10 CFR 50.46]
14.5 Refs, Table 14.5-5                        Incorporated the peak clad temperature
[FS 2005-007]                                  penalties and benefits for the large break LOCA. [10 CFR 50.46]
14.5 Refs, Table 14.5-5                        Incorporated the peak clad temperature
[FS 2006-002]                                  penalties and benefits for the large break LOCA. [10 CFR 50.46]
 
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Revision 3809/29/06 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
Chapter 17 (all)                                  Replaced Chapter 17 in its entirety with a brief
[QA 2004-002]                                      description of and reference to the recently implemented Topical Report DOM-QA-1. The Dominion Nuclear Facility Quality Assurance Program Description is based on ANSI/ASME NQA-1-1994 and will be maintained as a separate, single document for Dominion facilities.
[10 CFR 50.54(a)]
18.2.12                                            Removed the ASME XI edition and addenda
[FS 2005-023]                                      reference for containment inservice inspection to allow periodic update as required by regulation.
Revision 3709/30/05 Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
1.1, 1.4.41, 2.1.3.5, 4.3.5, 5.1, 6.2.1.1,        Corrected citations to regulation and regulatory 6.2.2.1.3, 7.2.1.8.3, 14.1, 15.2.1                guide dose limits for design basis accident
[FS 2004-031]                                      analysis.
3.6.3.2                                            Indicated that ultrasonic or x-ray testing is no
[FS 2004-029]                                      longer performed for burnable poison rods beginning with Cycle 20.
4.2.2.2, 4.2.6                                    Updated the estimated pressurizer heatup rate
[FS 2004-018]                                      during startup for a reduced heater capacity of 1200 kW.
4.2.7.2, 7.5.2.2, 7.5.3.5, 7.6.2.2, 7.9.2          Replaced the emergency response facilities
[FS 2004-027]                                      computer system.
4.3.3.1, 4.3 Refs                                  Extended the inspection interval for reactor
[FS 2004-026]                                      coolant pump flywheels from 10 to 20 years.
[10 CFR 50.90]
Tables 4.3-2 & 4.3-4                              Revised the stress intensity value for the Unit 2
[FS 2004-028]                                      reactor vessel flange.
4.4.1.7, 6.2.2.2.4, 6.2.2.2.10, 6.2.4, 6.3.1.5.1,  Changed the ASME Code reference for 6.3.1.5.2, 9.3.4, 9.4.5                            inservice testing activities from Section XI to a
[FS 2004-033]                                      general reference to the ASME Code.
 
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Revision 3709/30/05 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
Tables 5.2-1 & 5.2-2                            Reflected the removal of valves 1-MS-118 and
[FS 2005-011]                                  2-MS-118 as part of the decay heat subsystem removal.
5.3.5, 5.3 Refs, 6.2.3.3, 6.2.3.12.1, 6.2 Refs, Reflected that the Hydrogen analyzers and Tables 6.2-14 & 6.2-15, Figures 6.2-3, 6.2-4,  recombiners will continue to function and be 6.2-5, 6.2-6, 6.2-7, & 6.2-8                    periodically tested, but are no longer part of the
[FS 2005-002]                                  plant design basis or credited in accident analyses.
6.3.1.3, Figure 6.3-16                          Changed the refueling water storage tank low
[FS 2004-021]                                  level alarm setpoint from 16.0% to 20.0%.
7.2.2.1.1                                      Increased the design temperature limit for
[FS 2000-006]                                  power cable from 85°C to 90°C and described randomly spaced power cable having less than 1/4 diameter spacing.
7.2.3.2.7, Figure 8.4-1, 10.3.5.3              Changed electrical power feeds associated with
[FS 2003-030]                                  replacement of the plant computer and the emergency response facilities computer system.
8.2                                            Provided clarification of the operating
[FS 2003-060]                                  conditions and analysis required for electrical equipment and cables.
8.3, Figure 8.3-1                              Installed redundant, underground feeder cables
[FS 2004-006]                                  to the low level intake structure buses.
8.5                                            Corrected the description of the loads served by
[FS 2003-037]                                  the emergency diesel generators.
[10 CFR 50.90]
8.5                                            Clarified that three low head safety injection
[FS 2004-025]                                  pump motors are analyzed to start at 72% of rated voltage.
8.5                                            Modified the #2 emergency diesel generator
[FS 2005-018]                                  auto start circuit.
Table 9.4-2                                    Corrected the description of the capacity of the
[FS 2005-019]                                  chilled water system chillers.
9.13.3.6, 9.13.4.2                              Revised the description of the main control
[FS 2004-022]                                  room and emergency switchgear and relay room ventilation system to rely on operating either one or two chillers.
 
Revision 52Updated Online 09/30/20                    SPS UFSAR                                31 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3709/30/05 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                  where indicated in brackets.
9B.2.3, 9B.2.4.7, 9B.2 Refs, Table 9B.2-1      Replaced the 6-ton Auxiliary Building hoist
[FS 2004-038]                                  with a 5-ton hoist.
10.3.5.2, Figure 10.3-9                        Replaced Unit 2 auxiliary feedwater system
[FS 2004-003]                                  isolation valves with stop-check valves.
10.3.5.2, Figure 10.3-9                        Replaced Unit 1 auxiliary feedwater system
[FS 2004-015]                                  isolation valves with stop-check valves.
Table 10.3-4                                  Revised the cooling water flow value for the
[FS 2004-004]                                  Unit 2 generator hydrogen coolers.
Figure 10.3-11                                Corrected tie-in locations between Sheets 1 & 2
[FS 2004-036]                                  describing the bearing cooling system.
Tables 11.3-5 & 11.3-7                        Reflected consistent mark number format for
[FS 2005-017]                                  the radiation monitoring system.
14.2 Refs, 14.3 Refs, 14B Refs                Updated the references to the RETRAN
[FS 2004-030]                                  Topical Report.
14.3.1.4.4, 14.3.2.4.2, Table 14.3-7, 14.3-8,  Corrected and clarified the description of the 14.3-9, 14.3-10, 14.3-12, & 14.3-15            dose consequences of the main steam line
[FS 2005-010]                                  break, locked rotor accident, and steam generator tube rupture based on the alternative source term methodology.
Table 14.3-8                                  Incorporated an editorial correction of the
[FS 2005-021]                                  event time ranges.
14.5.1.6, 14.5 Refs, Table 14.5-5              Incorporated the peak clad temperature
[FS 2005-001]                                  penalties and benefits for the large break LOCA. [10 CFR 50.46]
Figure 15.1-1                                  Provided the location of well-water supply
[FS 2004-032]                                  system Well E and removed the incorrectly identified information center.
Figure 15.1-2                                  Added delay fencing in the Protected Area.
[FS 2004-010]
Figure 15.1-2                                  Added sally port fencing in the Protected Area.
[FS 2004-012]
15.6.2.1                                      Incorporated an editorial correction replacing
[FS 2005-004]                                  stem generator with steam generator.
15.7, 15.7 Refs                                Clarified the scope of statistical information
[FS 2004-034]                                  regarding the evaluation of masonry block walls in response to IE Bulletin 80-11.
 
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Revision 3709/30/05 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
18.1.1, 18.1.4, 18.2.1, 18.2.9, 18.2.19,          Reflected the completion of License Renewal Table 18-1                                        Commitment Item Nos. 1, 2, 3, 7, 8, 19, and 29.
[FS 2004-037]
Revision 3609/30/04 Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
KWI                                                Updated the Key Word Index to incorporate an
[FS 2004-002]                                      editorial correction.
3.3.3.2.1, 3.3 Refs, 3.5 Refs                      Updated references to the topical report for
[FS 2003-035]                                      reload design methodology. [10 CFR 50.90 License Amendment]
3.5.3.1, 3.5.3.1.6, 4.1.2.8, 4.1.6, 4.1 Refs,      Replaced the Unit 2 reactor vessel closure Tables 4.1-2, 4.1-8, & 4.1-15, 4.2.2.1,            head.
Table 4.2-1, 4.3.1.1, Tables 4.3-2, 4.3-4, 4.4-1,
& 9B.2-1, 14.3.3.1.1.1, 14.5.3, 14.5.3.3.4, 14.5 Refs, 15.2 Refs, Table 15.2-2
[FS 2003-040 & FS 2003-052]
Table 4.1-2                                        Identified the replacement reactor vessel heads
[FS 2003-051]                                      dome insulation thickness.
4.2.2.1, 5.3.1.3.2, 9.12.5.2, 9.12.5.4, 9B.2.5,    Upgraded the Unit 2 reactor head assembly.
Table 9B.2-1, Table 11.3-2, Figures 11.3-2
& 11.3-3, 14.3.3.1.1.4.2, 15.5.1.1, 15.5.1.8, 15.5.1.11.1, 15A.3.5.2, 15A.3.5.2.4, 15A Refs
[FS 2003-048]
4.2.7.2                                            Completed the installation of the Unit 2 N-16
[FS 2003-042]                                      primary-to-secondary leakage detection system.
4.3.1.1, Table 4.3-1 & 4.3-2                      Provided a text description of cumulative usage
[FS 2004-008]                                      factors for reactor vessel components in lieu of a tabular format. Updated stresses for reactor vessel components.
Table 5.3-2, 9.4.1.3, 9.4.3.3, Table 9.4-2,        Updated the description of the Unit 2 chilled Figure 9.9-1, Table 10.3-4, Figure 10.3-11        water system to reflect equipment replacement
[FS 99-065]                                        and changing the systems source of cooling water.
 
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Revision 3609/30/04 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
5.5.3, 7.2.3.2.7, 7.3.2.3.2, 7.4.2.4, 7.4.3.2,  Replaced the Unit 2 plant computer.
7.4.3.6, Tables 7.4-1, 7.4-2, & 7.4-3, 7.6.2.2, 7.7.2, Figure 7.7-1, 7.9.2, 7.9.2.2, 7.9.2.3, 7.9.2.5, 7.9.2.6, 7.9.3, 7.9.4, 9.10.4.1
[FS 2003-059]
6.2.2.2.4                                        Replaced the Unit 2 charging pump discharge
[FS 2003-053]                                    alternate header isolation valve, 2-CH-MOV-2287C.
7.2.1.2, 7.3.2.3.2, 14.2.4                      Replaced the Unit 2 benchboard individual rod
[FS 2003-023]                                    position indicators and the rod bottom lights with redundant flat panel displays.
7.5.2.2, 7.5.3.5, 7.6.2.2, 7.7.2, Figure 7.7-1,  Replaced the Unit 1 plant computer.
7.9.2, 7.9.2.2, 7.9.2.5, 7.9.3
[FS 2002-019]
7.6.2.1                                          Clarified the description of the Unit 2 incore
[FS 2003-049]                                    instrumentation system.
8.5                                              Added provisions for inspection and repair of a
[FS 2001-037]                                    buried fuel oil storage tank during plant operation. [10 CFR 50.90 License Amendment]
9.4.1.1                                          Added the vacuum priming system to the
[FS 2004-014]                                    description of the component cooling heat exchangers.
9.4.1.3                                          Clarified the description of the chilled water
[FS 2003-064]                                    used to cool the water in the refueling water storage tank.
9.4.1.3, Table 9.4-2                            Updated the Unit 1 chilled water system
[FS 2003-050]                                    capacity.
Table 9.6-1, 11.2.3.1.5, Table 11.2-1            Designated the waste disposal evaporator test
[FS 2003-058]                                    tanks as installed but no longer used.
9.10.4.7                                        Removed the steam heating coils from the
[FS 2004-011]                                    motor control center rooms ventilation units.
9.12.4.14, 9B.2.4.6, 9B.2.4.7, Table 9B.2-1      Uprated the Unit 2 polar crane capacity for
[FS 2003-011]                                    each of the two hooks from 125 to 140 tons.
Figure 10.2-1, 10.3.3.2, Table 10.3-4            Replaced the Unit 2 main generator with an
[FS 2003-012]                                    upgraded, refurbished generator.
 
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Revision 3609/30/04 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
10.3.1.2                                        Restored the automatic control mode for the
[FS 2003-039]                                  Unit 2 steam header pressure controller.
10.3.3.2, Table 10.3-4                          Replaced the Unit 2 main generator exciter.
[FS 2003-009]
10.3.5.1                                        Increased the Unit 2 feedwater recirculation
[FS 2003-041]                                  flow from 2800 to 4300 gpm.
10.3.5.2, Figure 10.3-9                        Modified the Unit 2 feedwater bypass
[FS 2003-038]                                  regulating valve line to provide bypass flow indication during unit startup.
10.3.5.3                                        Incorporated editorial correction of punctuation
[FS 2003-054]                                  errors.
11.2.4.1.6                                      Added the low-level waste storage facility and
[FS 2003-029]                                  sea van storage pad to the description of the solid waste disposal system.
14.2.9.2.2.2, 14.2.9.2.3, 14.2.9.2.4.1,        Reflected the reanalyzed dose consequences of 14.2.9.2.4.2, 14.2.9.2.4.3, 14.2.9.2.4.4,      a locked rotor accident using alternate source 14.2 Refs, Tables 14.2-2, 14.2-4, & 14.3-14    term and methodologies described in
[FS 2003-044]                                  Regulatory Guide 1.183.
14.2.10.3, 14.2.10.4.2, Figures 14.2-68,        Updated the reanalyzed information and figures 14.2-69, 14.2-70, 14.2-71, & 14.2-72            for loss of external electrical load/turbine trip.
[FS 2004-007]
14.3.1.4, 14.3.1.4.1, 14.3.1.4.2, 14.3.1.4.3,  Incorporated the reanalysis of the dose 14.3.1.4.4, 14.3.1.4.5, 14.3.2.4, 14.3.2.4.2,  consequences of the steam generator tube 14.3.2.4.3, 14.3.2.4.4, 14.3.2.4.5, 14.3 Refs,  rupture and main steam line break using the Tables 14.3-9, 14.3-10, 14.3-11, 14.3-12,      alternative source term methodology.
14.3-14, & 14.3-16
[FS 2003-057]
14.4.1.2.1, 14.4.1.2.2, 14.4.1.3.1, 14.4.1.3.2, Incorporated the reanalysis of the dose 14.4 Refs, Table 14.4-5                        consequences of a fuel handling accident using
[FS 2003-055]                                  the alternative source term methodology.
14.5.2.4.2, 14.5.2.5                            Made editorial corrections to correctly refer to
[FS 2004-024]                                  Tables 14.5-15 & 14.5-16.
14.5.2.6, 14.5 Refs, Table 14.5-16              Incorporated a change to the summary of peak
[FS 2004-019]                                  clad temperature penalties and benefits for the small break LOCA. [10 CFR 50.46]
 
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Revision 3609/30/04 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                  where indicated in brackets.
14.5.5.2, 14.5.5.3, 14.5 Refs, Table 14.5-12  Revised the discussion of dose consequences of
[FS 2003-061]                                  the loss of coolant accident using 500 cfm instead of 10 cfm for the control room in-leakage and out-leakage parameters.
15.5.2, 15.5.2.1, 15.5.2.3, 15 Refs            Completed the restoration of construction
[FS 2003-031]                                  opening in the containment structure for the Unit 2 reactor pressure vessel head replacement.
17.2.1.2.D.3.c, Figure 17.2.1-3                Deleted the Manager Nuclear Engineerings
[QA 2004-004]                                  responsibility for development of Improved Technical Specifications. Updated the title of and line of reporting for Supervisor Nuclear Records. [10 CFR 50.54(a)(3)]
17.2.2.8                                      Updated terminology to the current naming
[QA 2004-005]                                  convention for inservice inspection personnel.
[10 CFR 50.54(a)(3)]
17.2.10                                        Updated the description of qualification
[QA 2003-001]                                  requirements for personnel performing non-destructive examinations.
[10 CFR 50.54(a)(3)]
18.2.3                                        Established acceptance criteria for borated
[FS 2004-001]                                  water leakage.
18.2.6, 18.2.10, Table 18-1                    Described completion of commitments
[FS 2004-005]                                  regarding inspection of inaccessible areas, groundwater monitoring, and internal inspections of containment polar crane girders.
18.2.19, Table 18-1                            Described completion of commitments
[FS 2004-009]                                  regarding procedures to assure consistent inspection of components for aging effects during work activities.
18.3.2.4, 18.5 Refs, Table 18-1                Completed detailed engineering evaluation for
[FS 2003-062]                                  the potential effect of environmentally-assisted fatigue in safety injection accumulator nozzles and charging line nozzles.
 
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Revision 3509/30/03 Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
1.1, 1.6.2.3, 2.1.3.1, 3.1, 4.1, 4.1.4, 4.1.5,      Reflected the increased operating life basis Tables 4.1-8, 4.1-12, & 4.1-13, 4.3.1.1, 4.3.1.2,  from 40 to 60 years and added Chapter 18 Tables 4.3-3 & 4.3-4, 5.0, 6.1, 6.3.1.2.1, 7.1,    [10 CFR 54.21] to describe the programs and 7.5.3.5, 8.0, 9.0, Table 9.1-3, 10.1, 11.1,        activities that manage the effects of aging 11.3.2.9.1, 15.5.1.8, 18.0, 18.1, 18.1.1, 18.1.2,  materials during the extended operation period 18.1.3, 18.1.4, 18.2, 18.2.1, 18.2.2, 18.2.3,      associated with license renewal.
18.2.4, 18.2.5, 18.2.6, 18.2.7, 18.2.8, 18.2.9, 18.2.10, 18.2.11, 18.2.12, 18.2.13, 18.2.14, 18.2.15, 18.2.16, 18.2.17, 18.2.18, 18.2.19, 18.2.20, 18.3, 18.3.1, 18.3.1.1, 18.3.1.2, 18.3.1.3, 18.3.2, 18.3.2.1, 18.3.2.2, 18.3.2.3, 18.3.2.4, 18.3.3, 18.3.4, 18.3.5, 18.3.5.1, 18.3.5.2, 18.3.5.3, 18.3.5.4, 18.3.5.5, 18.3.5.6, 18.3.6, 18.4, 18.4.1, 18.4.2, 18.5, Table 18-1
[FS 2002-016]
Table 2.1-4, Figure 15.1-2                          Installed a tank farm and feed system for
[FS 99-064]                                        treating the circulating water system with sodium bromide and sodium hypochlorite.
2.2.1.2, 3.3.2.13, 6.2.2.1.2, 7.4.3.3.3, 7.4.3.5.2, Replaced paper strip chart recorders in the 7.4.3.7.2, 7.4.3.7.4, 7.4.3.7.5, 11.3.3, 11.3.4.1, control room with video display recorders.
11.3.4.5
[FS 2001-044]
3.5.2.6.1, 3.5 Refs                                Identified the references for the design
[FS 2002-034]                                      requirements for fuel assembly structural components.
3.5.3.1, 4.1.2.8, 4.1.6, 4.1 Refs, Tables 4.1-2, Replaced the Unit 1 reactor vessel closure 4.1-9, & 4.1-14, 4.2.2.1, 4.2.5, 4.2 Refs,          head.
Table 4.2-1, 4.3.1.1, Tables 4.3-1, 4.3-2, 4.3-3,
& 4.3-4, 4.4.1.3, Table 4.4-1, 15A.5.2, 15A.5.2.1, 15.A.5.2.2, 15A.5.2.3, 15A.5.2.4, 15A.5.2.5, 15A Refs
[FS 2003-018 & FS 2003-026]
4.1 Refs, Table 4.1-14                              Reflected a new reference nil ductility
[FS 2003-001]                                      transition temperature for the Unit 1 reactor vessel closure head dome.
[10 CFR 50.55a(a)(3)(ii) and 10 CFR 50.55a(g)(6)(i) Relief Requests]
 
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Revision 3509/30/03 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
Table 4.1-1, 7.5.1.4.1, 7.5.1.4.2              Changed the reactor coolant system
[FS 2001-022]                                  low-pressure alarm from 2205 to 2210 psig.
4.2.2.1, Figures 4.2-2 & 4.2-3, 9B.2.4.4,      Modified the service structure, cooling air 9B.2 Refs, Table 9B.2-1                        shroud and shroud support, radiation shield,
[FS 2003-019]                                  insulation, and intermediate lift ring for the Unit 1 reactor vessel head replacement.
4.2.2.1, 4.3.1.1, Table 4.3-1                  Enhanced the description of repairs performed
[FS 2002-031]                                  on the Unit 1 reactor vessel head and control rod drive mechanism nozzles.
4.2.2.6                                        Clarified the description of flanges used in the
[FS 2002-029]                                  reactor coolant system.
4.2.7.2                                        Installed the Unit 1 N-16 primary-to-secondary
[FS 2001-035]                                  leakage detection system.
4.2.7.2                                        Installed the initial phase of the Unit 2 N-16
[FS 2003-043]                                  primary-to-secondary leakage detection system.
4.2 Refs, Table 4.3-3 & 4.3-4                  Corrected typographical errors.
[FS 2003-014]
4.3.3.2, 4.3 Refs, Table 4.3-4                  Reflected the revised RTPTS values provided
[FS 2003-007]                                  for the Unit 2 Reactor Vessel Integrity Program.
Table 6.2-5                                    Replaced charging pump 1-CH-P-1B.
[FS 2002-028]
6.3.1.5.1, 6.3.1.5.2                            Revised the frequency of inspection for the
[FS 2002-002]                                  containment spray and recirculation spray nozzles. [10 CFR 50.90 License Amendment]
Figure 6.3-1                                    Removed the vent caps from the refueling
[FS 2000-021]                                  water storage tanks.
7.2.1.2, 7.3.2.3.2, 14.2.4                      Replaced the Unit 1 benchboard individual rod
[FS 2003-005]                                  position indicators and the rod bottom lights with redundant flat panel displays.
7.2.2.1.6                                      Removed the reactor protection system logic
[FS 99-062]                                    channel testing event recorder.
7.2.2.5, Table 7.2-3, 7.8, 7.8.1, Figure 7.8-1  Removed the load frequency recorder and the
[FS 2002-022]                                  automatic load control system.
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                                38 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3509/30/03 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
7.2.3.2.7, 7.9.4, 8.4.4, 8.4.5, 8.4.6,          Provided power feed changes in preparation for Figure 8.4-1, 9.10.2.7, 10.3.5.3                plant computer replacement, installed a portion
[FS 2002-017]                                    of the new computer for parallel testing, and permitted use of engineering-approved cable.
7.6.2.1, 7.6.3                                  Clarified the description of the incore
[FS 2002-021]                                    instrumentation system.
8.4.4                                            Installed an additional 125V dc switchboard
[FS 2003-003]                                    crosstie circuit breaker.
8.5                                              Modified the #3 emergency diesel generator
[FS 2003-013]                                    breaker closure circuit.
9.4.3.5                                          Restored the original configuration of the
[FS 2001-009]                                    charging pump component cooling water system.
9.10.2.2.2                                      Changed the pressure of the firewater system.
[FS 2001-028]
9.12.4.14, 9B.2.4.6, 9B.2.4.7, 9B.2 Refs,        Uprated the Unit 1 polar crane capacity for Table 9B.2-1                                    each of the two hooks from 125 to 140 tons.
[FS 2003-010]
9.12.5.3                                        Provided an alternate method for monitoring
[FS 2003-017]                                    subcriticality during fuel onload.
9.13.3.6                                        Installed an alternate power feed to Mechanical
[FS 97-028]                                      Equipment Room-5 for use in the event of a fire.
9.13.3.6, 9.13.4.1                              Provided shutdown of fans serving areas
[FS 2000-019]                                    adjacent to the main control room (MCR) due to a safety injection signal or manual actuation in the MCR.
10.3.1.2                                        Restored the automatic control mode for the
[FS 2003-028]                                    Unit 1 steam header pressure controller.
10.3.1.2, 10.3.8, 11.2.3, 11.2.3.2, 11.2.3.2.1,  Reflected partial implementation of 11.2.3.2.2, Tables 11.2-4, 11.2-5, 11.2-6,      discontinued use of the steam generator
& 11.2-7, Figures 11.2-2 & 11.2-3, 11.3.2.6,    blowdown treatment facility.
11A.4, Tables 11A-10 & 11A-12
[FS 2003-047]
10.3.4.1, 10.3.4.2                              Increased the flow rate of the circulating water
[FS 98-045]                                      pumps from 210,000 gpm to 220,000 gpm.
 
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Revision 3509/30/03 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
10.3.5.1                                          Increased the Unit 1 feedwater recirculation
[FS 2003-004]                                    flow from 2800 to 4300 gpm.
10.3.5.2, Figure 10.3-9                          Modified the Unit 1 feedwater bypass
[FS 2003-024]                                    regulating valve line to provide bypass flow indication during unit startup.
10.3.9, 10.3.9.2, Figure 10.3-11                  Added description of the bearing cooling
[FS 2001-003 & FS 2003-046]                      normal makeup water supply and treatment system.
Figure 10.3-7                                    Installed an additional cross-connect valve for
[FS 2001-030A]                                    isolation of the Unit 1 auxiliary steam header.
Figure 10.3-11                                    Replaced turbine lube oil coolers temperature
[FS 2000-029]                                    control valves with manual throttle valves.
Figure 10.3-11                                    Removed and capped dead-leg piping to the
[FS 2001-006]                                    flash evaporators that are abandoned in place.
14.2.1.1, 14.2.1.2                                Corrected the description of the reactor trip
[FS 2003-032]                                    setpoint for the rod withdrawal from subcritical event.
14.4.1.2.1                                        Updated a cross-reference number.
[FS 2003-006]
14.5.3.2, 14.5 Refs                              Added text describing that it has been shown
[FS 2003-002]                                    that the control rods will insert for cold leg breaks.
14.5 Refs, Table 14.5-5                          Incorporated a change to the summary of peak
[FS 2003-027]                                    clad temperature penalties and benefits for the large break LOCA. [10 CFR 50.46]
15.3.1, 15.3.2, 15.4, 15.4.1, 15.4.2, 15.4.3,    Completed the restoration of construction 15.5.1.6, 15.5.1.8, 15.5.1.9, 15.5.1.9.1,        opening in the containment structure for the 15.5.1.9.3, 15.5.1.9.4, 15.5.1.10, 15.5.2,        Unit 1 reactor pressure vessel head 15.5.2.1, 15.5.2.2, 15.5.2.3, 15.5.2.4, 15.5.2.5, replacement.
15.5 Refs
[FS 2003-020 & FS 2003-025]
17.2.0.2, Table 17.2-0, 17.2.2.1, 17.2.2.5,      Made editorial corrections to correctly refer to 17.2.2.6, 17.2.10, 17.2.17                        Table 17.2-0.
[FS 2003-021]
 
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Revision 3509/30/03 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
17.2.1.1.A, 17.2.1.2.B, 17.2.1.2.B.1,              Revised organizational titles of the Senior Vice 17.2.1.2.B.1.b.1.1, 17.2.1.2.C.1, 17.2.16.2.B.2,  President Nuclear Operations, Shift Manager, 17.2.16.2.C, 17.2.1.16.2.D, Figures 17.2.1-1      and Unit Supervisor. [10 CFR 50.54(a)(3)]
& 17.2.1-2, Table 17.2-0, App C A.8.e, B.6.e, B.6.i, B.7.c, & B.8
[FS 2003-015]
17.2.1.2                                          Assigned responsibility for maintenance of
[FS 2003-008]                                      plant equipment history to the Manager Nuclear Maintenance. [10 CFR 50.54(a)(3)]
17.2.1.2.A.2, Figure 17.2.1-1                      Deleted the description of and reference to the
[FS 2002-006]                                      Nuclear Oversight Board.
[10 CFR 50.54(a)(4)]
Table 17.2-0                                      Provided for the repair and testing of a
[FS 2002-033]                                      temporary opening in the containment due to reactor vessel head replacement.
[10 CFR 50.54(a)(3)]
Revision 3409/03/02 Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
1.1.8, 1.4.11, 1.4.47, 2.1.2.1, Figure 2.1-3,      Incorporated the reanalysis of the LOCA and 5.3.1.2, 5.3.1.3.4, 5.3.1.4, 5.3.1.4.1, 5.3.1.4.2, Fuel Handling Accidents resulting from the 5.4, 6.1, Table 6.2-6, 6.3.1.1, 7.7.1, 9.12.6,    implementation of alternative source term.
9.12.6.1, 9.13.1, 9.13.2, 9.13.3.1, 9.13.3.2,      [10 CFR 50.67]
9.13.3.6, 9.13.3.7, 9.13.4.1, 11.3.1, 11.3.3.13, 11.3.4.2, 11.3.4.3, 11.3.4.4, 11.3.6, Table 11.3-1, 14.4.1.1, 14.4.1.2, 14.4.1.2.1, 14.4.1.2.2, 14.4.1.2.2.1, 14.4.1.2.2.2, 14.4.1.2.2.3, 14.4.1.2.2.4, 14.4.1.2.3, 14.4.1.3.1, 14.4.1.3.2, 14.4.1.3.3, 14.4.1.3.4, 14.4 Refs, Tables 14.4-1, 14.4-2, 14.4-3, 14.4-4, & 14.4-6, 14.5.4, 14.5.5, 14.5.5.1, 14.5.5.2, 14.5.5.3, 14.5.6, 14.5 Refs, Tables 14.5-7, 14.5-8, 14.5-10, 14.5-11,
& 14.5-12
[FS 2000-005A]
 
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Revision 3409/03/02 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
3.4.1.1, 3.4.1.1.4, 3.4.1.2, 3.4 Refs, 3.5.2.1,  Reflected the physical description of Surry 2 3.5.2.6.1, 3.5 Refs, Table 3.5-3                Batch 20 and subsequent reload fuel batches
[FS 2002-003]                                    for Units 1 and 2. Identified the fuel performance models for cycle-specific evaluations.
4.2.2.4                                          Replaced reactor coolant pump main flange
[FS 99-053]                                      bolts with main flange fasteners.
4.3.1.1                                          Described the repairs performed on the Unit 1
[FS 2001-043]                                    reactor vessel head and control rod drive mechanism nozzles.
4.3.1.1, Figure 4.3-2                            Clarified the stress analysis boundary
[FS 2001-046]                                    conditions at the vessel head penetration shrink fit for the control rod drive mechanism housings. Showed the vessel head penetration welds in their correct orientation.
5.4.1.3.5.4, 8.4.4                              Updated a reference document number and
[FS 2002-024]                                    corrected a typographical error.
6.2.3.12.1, 6.2 Refs, Tables 6.2-14 & 6.2-15,    Re-evaluated the hydrogen concentration in Figures 6.2-3, 6.2-4, 6.2-5, 6.2-6, 6.2-7,      containment following a LOCA.
& 6.2-8
[FS 2002-012]
Table 6.2-13, 6.3.1.3, Table 14B-3              Changed the bleed flow contribution to outside
[FS 2001-026]                                    recirculation spray pump NPSHa, clarified the function of the recirculation spray suction cross-connect line, and deleted the component cooling heat exchangers from the list of postulated targets in the auxiliary building.
7.6.2.1                                          Installed a plug in the high pressure seal at
[FS 2001-042]                                    Unit 1 core location J5 (1-RC-TW-J5).
7.6.2.1, 7.6.2.2, 7.6.2.3.1, Figures 7.6-1 &    Provided the description of a second flux 7.6-2                                            thimble tube and seal table seals design.
[FS 2000-049]                                    Described the process for converting to the new design.
7.6.2.1, Figure 7.6-1                            Installed a plug in the high pressure seal at
[FS 2002-013]                                    Unit 2 core location N8 (2-RC-TW-N8).
 
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Revision 3409/03/02 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
7.7.2, 9.10.3.5, 9.10.4.13, 10.3.1.2              Incorporated changes to reflect that the decay
[FS 99-034]                                        heat release subsystem is no longer used and that decay heat release components have been removed on Unit 1.
Figure 8.3-1, 8.4.4                                Installed an additional 125V dc switchboard
[FS 2002-004]                                      crosstie circuit breaker.
8.5                                                Removed the diesel generator voltage and
[FS 2001-001]                                      speed relay from the residual voltage time delay relay circuit and increased the time delay from 2.0 to 2.2 seconds.
8.5                                                Clarified the description of the analysis
[FS 2002-020]                                      consideration of a loss of offsite power being sequenced with a loss of coolant accident.
8.5, Table 8.5-1                                  Updated the setting of the emergency bus
[FS 99-025]                                        degraded voltage relays. [10 CFR 50.90 License Amendment]
9.1.2.1                                            Clarified auxiliary spray valve operation
[FS 2001-036]                                      meeting the requirements of the Appendix R analysis.
9.4.3.1                                            Clarified component cooling system thermal
[FS 2002-008]                                      relief requirements.
9.6.1.2, 9.6.2.2, 9.6.2.2.1, 9.6.2.2.3, 9.6.2.2.6, Clarified the status of the High Radiation 9.6.3.2, 9.6.4.2, 9.6 Refs, Tables 9.6-3 & 9.6-7 Sampling SystemPost-Accident Operation.
[FS 2002-011]                                      [10 CFR 50.90 License Amendment]
9.6.2.1                                            Reflected the abandonment of recorders from
[FS 2001-024]                                      the secondary sampling system on-line chemistry monitoring panels.
9.10.1                                            Identified fire protection systems that are not
[FS 2001-039]                                      required to satisfy regulatory criterion.
[10 CFR 50.48]
9.10.1, 16.2, 17.2.1.2, 17.2.5                    Removed terminology associated with the
[FS 2001-034]                                      former 10 CFR 50.59 regulation and incorporated wording from the current rule.
9.13.1, 9.13.4.1                                  Clarified the description of auxiliary building
[FS 2002-009]                                      ventilation fan performance.
 
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Revision 3409/03/02 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
9.13.3.3, 9.13.4.1                              Enhanced the text description of the
[FS 2002-015]                                  decontamination building ventilation system operation.
9B.2.4.4                                        Added the reactor vessel head stud racks to the
[FS 2001-002]                                  description of special lifting devices.
9B.2.4.4, Table 9B.2-1                          Removed the pneumatic reactor cavity seal ring
[FS 2001-017]                                  and its lifting rig.
11.2.3, 11.2.3.1.7, 11.2.3.2, Tables 11.2-5    Updated the description of steam generator
& 11.2-6                                        blowdown to reflect system lineup and
[FS 98-001]                                    chemistry guidelines.
11.2.4.1.2                                      Incorporated current methodology for handling
[FS 97-011]                                    and storing spent radioactive filters.
11.3.3.8, Tables 11.3-6 & 11.3-7                Changed the Unit 1 condenser air ejector
[FS 2001-025]                                  radiation monitor to a more sensitive detector.
11.3.3.8, Tables 11.3-6 & 11.3-7                Changed the Unit 2 condenser air ejector
[FS 2001-038A]                                  radiation monitor to a more sensitive detector.
14.2.10.3, 14.2.10.4, 14.2.10.4.1, 14.2.10.4.2, Incorporated an improved analysis technique Figures 14.2-62, 14.2-63, 14.2-64, 14.2-65,    concerning loss of external electrical load.
14.2-66, 14.2-67, 14.2-68, 14.2-69, 14.2-70, 14.2-71, & 14.2-62
[FS 2001-018]
Table 14.2-4                                    Cited the regulatory whole body dose limit.
[FS 2001-031]                                  [10 CFR 100]
14.5 Refs, Table 14B-2, 15.5 Refs              Corrected typographical errors.
[FS 2001-041]
14B.3.3, 14B.5.3.3                              Provided discussion of the auxiliary building
[FS 2001-045]                                  ambient temperature monitoring system for detection of a high energy line break and associated automatic/manual actions.
17.2.1.1, 17.2.1.2, 17.2.10, Figures 17.2.1-1,  Modified organizational titles and realigned 17.2.1-2, & 17.2.1-3                            certain reporting relationships within the
[FS 2002-005]                                  Nuclear Business Unit. [10 CFR 50.54(a)(3)]
17.2.1.2, Figures 17.2.1-1 & 17.2.1-3          Relocated the Records Management Program
[FS 2001-040]                                  organization from General Services to Nuclear Engineering. [10 CFR 50.54(a)(3)]
 
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Revision 3409/03/02 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
17.2.1.2, 17.2.3, 17.2.5, 17.2.6, 17.2.11,          Relocated North Anna Power Station current 17.2.15, 17.2.16, 17.2.18, 17.2 Refs,                technical specification requirements for the Table 17.2-0, Appendix C                            Management Safety Review Committee,
[FS 2001-023]                                        Station Nuclear Safety and Operating Committee, and Station Nuclear Safety to the QA Topical Report. [10 CFR 50.90 License Amendment]
17.2.7                                              Updated the description of the organizational
[FS 2002-023]                                        structure to reflect the responsibilities of the Vice President Nuclear Engineering and Vice President Nuclear Support Services with respect to procurement, vendor surveillance, and document reviews. [10 CFR 50.54(a)(3)]
Revision 3309/04/01 Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
1.1.6, 1.2.3, 3.3.2.12, 3.5, 3.5.1.3, 3.5.2.1,      Incorporated technical and editorial corrections 3.5.2.1.1, 3.5.2.1.2, 3.5.2.1.4, 3.5.2.1.5, 3.5.2.2, and clarifications resulting from the integration 3.5.2.3, 3.5.2.4, 3.5.2.5, 3.5.2.6.1, 3.5.2.6.3,    review of mechanical reactor design.
3.5.2.6.4, 3.5.3.1, 3.5.3.1.1, 3.5.3.1.2, 3.5.3.2.1, 3.5.4, 3.5.4.1, 3.5 Refs, Tables 3.5-1 & 3.5-3, Figures 3.5-3, 3.5-4, 3.5-5, 3.5-7, 3.5-9, 3.5-11, 3.5-12, & 3.5-13
[FS 2000-027]
1.4.23, 7.5.1, 8.4.3                                Provided clarification of the design and
[FS 2001-011]                                        licensing basis for the power supplies to the vital bus systems.
2.4.1, Table 9.2-1, Table 15.2-1, 15.5.1.8          Corrected typographical, administrative, and
[FS 2000-051]                                        format errors.
3.4.1.1.2, 3.4.1.1.3, 3.4.1.1.4, 3.4.1.1.5, 3.4.1.2, Incorporated technical and editorial corrections 3.4.1.3, 3.4.2, 3.4.2.1, 3.4.2.1.1, 3.4.2.1.2,      and clarifications resulting from the integration 3.4.2.2, 3.4.2.2.1, 3.4.2.2.2, 3.4.2.2.3, 3.4.2.2.4, review of thermal/hydraulic reactor design.
3.4.2.3, 3.4.2.4, 3.4.2.5, 3.4.2.6, 3.4.3.1, 3.4.3.2, 3.4.3.2.1, 3.4.3.3, 3.4.3.5, 3.4.3.8, 3.4 Refs, Table 3.4-1, Figures 3.4-1, 3.4-4, 3.4-8, & 3.4-10, Table 4.2-1, 8.5, 10.3.5.3
[FS 2000-028]
 
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Revision 3309/04/01 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
4.2.2.8, 14.2.6.2.2, 14.2.6.2.3                Established additional reactivity controls and
[FS 99-042A]                                    surveillance for the vacuum-assisted backfill method of returning an RCS loop to service.
[10 CFR 50.90 License Amendment]
Table 5.4-20                                    Revised the containment analysis results for
[FS 2001-013]                                  depressurization time and subatmospheric peak pressure.
6.2.3.12.1, Table 6.2-14                        Updated the description of the containment
[FS 2001-010]                                  hydrogen generation analysis.
6.2.3.12.1, Table 6.2-14, 14.5.1.3, 14.5.1.4,  Corrected typographical, administrative, and Table 14.5-3, 15A References                    format errors.
[FS 2001-027]
Figures 6.2-1 & 6.2-2                          Incorporated modifications to the Unit 1 safety
[FS 99-063]                                    injection system.
7.6.2.1, Figure 7.6-1                          Installed a seal welded cap on the flux thimble
[FS 2000-046]                                  tube at location 2-RC-TW-N8.
8.5                                            Added definition of loss of offsite power
[FS 2000-037]                                  (LOOP) as a LOOP to both units to the introduction of the emergency power system.
8.5                                            Added a time delay relay to each filter exhaust
[FS 2000-045]                                  fan start circuit to allow proper damper alignment.
9.4.4.3                                        Provided a description of the air lockup valve
[FS 2000-043]                                  on the reactor coolant pump thermal barrier inside and outside containment component cooling trip valves.
9.6.1.2, 9.6.2.2.6, Table 9.6-7                Deleted time restraints for containment sump
[FS 2000-052]                                  sampling or analysis with the high radiation sampling system.
9.8.1, Table 9.8-1                              Deleted statement that the compressed air
[FS 2001-007]                                  system air receivers are sized to provide ten minutes of breathing quality air and air to essential systems after shutdown of all compressors following a loss-of-power accident. Corrected compressed air system design data.
 
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Revision 3309/04/01 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
9.10.4.4                                        Included a description of the two-hour design
[FS 2000-048]                                  basis discharge/recharge case for the station batteries.
9.10.4.4                                        Revised the description of hydrogen generation
[FS 99-043]                                    and fire potential in the station battery rooms.
9.10.4.12                                      Incorporated modifications to the reactor
[FS 2000-041]                                  coolant pump motor oil collection system.
9.10.6, 12.2.2.3, 17.2.1.1, 17.2.1.2, 17.2.2.1, Modified organizational titles and reporting 17.2.2.5, 17.2.3, 17.2.7, 17.2.10, 17.2.15,    relationships associated with the entire Nuclear 17.2.16.2, 17.2.17, 17.2.18, Figures 17.2.1-1,  Business Unit. [10 CFR 50.54(a)(3)]
17.2.1-2, & 17.2.1-3, Table 17.2-0
[FS 2001-019]
9.12.3.1, 9.12.5.2                              Changed the design of the reactor cavity seal
[FS 2000-017]                                  from pneumatic to mechanical.
9.12.5.2                                        Corrected the description of lifting the reactor
[FS 2000-044]                                  vessel head with the reactor containment polar crane.
9.13.1, 9.13.4.1, 14.3.2                        Updated the description of feedwater isolation
[FS 2000-024]                                  for the rupture of a main steam pipe accident and of auxiliary building ventilation system capability.
9.13.2                                          Clarified the design and testing of the
[FS 99-046A]                                    safety-related charcoal filters installed in the auxiliary ventilation exhaust system.
[10 CFR 50.90 License Amendment]
9.13.3.7, 9.13.4.1                              Clarified auxiliary filtration requirements
[FS2000-053A]                                  consistent with the Basis for Technical Specification 3.22.
9C.1.1, 9C.2                                    Deleted carbon steel from the description of
[FS 97-020]                                    the flow restriction shields installed around circulating water system expansion joints.
10.3.1.2, 14.3.1.5                              Added the description of the backup bottled air
[FS 99-057]                                    system for the steam generator power operated relief valves.
 
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Revision 3309/04/01 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
11.2.3, 11.2.3.1.10, Table 11.2-1,                Installed a cross-connect line between the Figures 11.2-2 & 11.2-5                          Radwaste Facility building drain system and
[FS 2000-047]                                    the laundry waste system. Installed a second laundry drain pre-filter.
Tables 11.2-2 & 11.2-3                            Corrected typographical errors.
[FS 2001-014]
14.2.11.1, 14.2.12, Figures 14.2-73, 14.2-74,    Described the reanalysis of the loss of normal 14.2-75, 14.2-76, 14.2-77, 14.2-78, 14.2-79,      feedwater (LONF) and loss of ac power to the
& 14.2-80, 14B.5.1.7                              station auxiliaries (LOAC) events with
[FS 2001-005]                                    500 gpm auxiliary feedwater flow during the transient.
14.3.1.4.2, 14.3.1.4.4, 14.3.1.4.5, 14.3.2.4.2,  Reflected the reanalysis of the dose 14.3.2.4.4, 14.3.2.4.5, 14.3 Refs, Tables 14.3-9, consequences of the steam generator tube 14.3-10, 14.3-11, 14.3-12, & 14.3-16              rupture and main steam line break events.
[FS 2000-032]
14.5.1.1, 14.5.1.2, 14.5.1.3, 14.5.1.4, 14.5.1.5, Updated the analysis of the large break 14.5.1.7, 14.5.1.8, 14.5 Refs, Tables 14.5-2,    loss-of-coolant accident.
14.5-3, 14.5-4, 14.5-5, 14.5-6, 14.5-7, 14.5-8,
& 14.5-9, Figures 14.5-2, 14.5-3, 14.5-4, 14.5-5, 14.5-6, 14.5-7, 14.5-8, 14.5-9, 14.5-10, 14.5-11, 14.5-12, 14.5-13, 14.5-14, 14.5-15, 14.5-16, 14.5-17, 14.5-18, 14.5-19, 14.5-20, 14.5-21, 14.5-22, 14.5-23, 14.5-24, 14.5-25, 14.5-26, 14.5-27, 14.5-28, 14.5-29, 14.5-30, 14.5-31, 14.5-32, 14.5-33, 14.5-34, 14.5-35, 14.5-36, 14.5-37
[FS 2001-008]
Table 15.2-1                                      Restored the seismic Category I designation for
[FS 2000-054]                                    the yard hydrant piping system.
15.5.1.8, 15.5 Refs.                              Documented the evaluation of isolated
[FS 99-013]                                      containment penetration piping for susceptibility to thermal over-pressurization following a DBA. [NRC Generic Letter 96-06]
15A.3.2, 15A Refs                                Incorporated generic implementation procedure
[FS 2001-004]                                    criteria and methodology for seismic verification of equipment.
 
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Revision 3309/04/01 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                where indicated in brackets.
17.2.17, Table 17.2-0                        Updated the Quality Assurance Topical Report
[FS 99-067]                                  description of the retention of quality assurance records in electronic media.
[10 CFR 50.54(a)(4)]
Table 17.2-0                                Clarified the provision for substitution of
[FS 2001-020]                                experience for a bachelors degree.
[10 CFR 50.54(a)(3)]
Tables 17.2-0, 17.2-2, & 17.2-3              Reduced records retention requirements
[FS 2000-003]                                consistent with ANSI N45.2.9 or applicable regulations. [10 CFR 50.54(a)(4)]
 
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Revision 3209/01/00 Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
KWI, 1.4.2, 1.4.5, Ch 2, 2.2.2.1, 2.3.1.2.2,      Incorporated technical and editorial corrections Tbl 2.3-7, 2.4.7.2, 2.4.7.6, 2.4.9, Tbls 2.4-9,  and clarifications resulting from the integration 2.4-10, & 2.4-12, Figs 2.4-5 & 2.4-6, 2.5.4.3,    review of civil/structural/seismic topics.
4.3.1.2, 4.3 Refs, Tbl 4.3-3, Fig 4.3-3, 7.2.1, 7.5.1, 9.2.3.1, 9A.2, 9A.3.1.3.1, 15.1, 15.2.4, Tbl 15.2-1, 15.4.1, 15.4.4, 15.4.5, 15.4.6, 15.4.6.1, 16.4.6.2, 15.4.6.3, 15.4.6.4, 15.4.6.4.1, 15.4.6.4.2, 15.4.6.4.3, 15.4.6.4.4, 15.4.6.4.5, 15.4.6.4.6, 15.4.6.4.7, 15.4.6.4.8, 15.4.6.4.9, 15.4.6.4.10, 15.4.6.4.11, 15.4.6.4.12, 15.4.6.4.13, 15.4.6.4.14, 15.4.6.4.15, 15.4.6.4.16, 15.4.6.4.17, 15.4.6.4.18, 15.4.6.4.19, 15.4.6.5, 15.4.6.5.1, 15.4.6.5.2, 15.4.6.5.3, 15.4.6.5.4, 15.4.6.5.5, 15.4.6.5.6, 15.4.6.5.7, 15.4.6.5.8, 15.4.6.5.8.1, 15.4.6.5.8.2, 15.4.6.5.8.3, 15.4.6.5.8.4, 15.4.6.5.8.5, 15.4.6.5.9, 15.4.6.5.9.1, 15.4.6.5.9.2, 15.4.6.5.9.3, 15.4.6.5.10, 15.4.6.5.10.1, 15.4.6.5.10.2, 15.4.6.5.10.3, 15.4.6.5.11, 15.4.6.5.11.1, 15.4.6.5.11.2, 15.4.6.5.11.3, 15.4.6.5.11.4, 15.4.6.5.11.5, Figs 15.4-1 thru 15.4-3, 15.5.1.6, 15.5.1.8, 15.5.1.10, 15.5.1.12, 15.5.1.13.3, Figs 15.5-5
& 15.5-6, 15.6, 15.6.1, 15.7, 15.7 Refs, 15A, 15A.3.1, 15A.3.2, 15A.3.3, 15A.3.4, 15A.3.5, 15A.3.5.1, 15A.3.5.2, 15A.3.5.2.1, 15A.3.5.2.2, 15A.3.4.2.3, 15A.3.5.2.4, 15A.3.5.3, 15A.4, 15A Refs, Tbl 15A-5
[FS 99-050]
KWI, Table 4.1-9, 5.4.1.3.5.4, Table 9.1-7,      Incorporated updates to the key word index and 9.4.4.7, Table 9.4-1, Figure 9.9-1, 14.2.5.2.1    corrected typographical, spelling, grammar and
[FS 99-044]                                      administrative errors.
 
Revision 52Updated Online 09/30/20                          SPS UFSAR                                50 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3209/01/00 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
KWI, 5.3.1.1, 5.3.1.3.1, 9.3.3.2, 9.4, 9.4.1.1,    Incorporated technical and editorial corrections 9.4.1.2, 9.4.1.3, 9.4.1.4, 9.4.1.5, 9.4.3.1,        and clarifications resulting from the integration 9.4.3.2, 9.4.3.3, 9.4.3.5, 9.4.4.1, 9.4.4.3,        review of the component cooling water system.
9.4.4.5, 9.4.5, 9.4 Refs, 9.4 RefDwgs, Tables 9.4-7 through 9.4-10, Figures 9.4-1 through 9.4-5, 9.9, 9.9.1, 9.9.2.1, 9.9.3.2, Table 9.9-3
[FS 99-022]
1.1, 1.4.2, 1.4.28, 1.4.29, 1.4.31, 1.4.33, 1.6,    Incorporated technical and editorial corrections 1.6.1.1, 1.6.2.8, 3.1, 3.2.1, 3.2.2.1, 3.2.3.1,    and clarifications resulting from the integration 3.2.3.3, 3.2 Refs, 3.3.1, 3.3.2.1, 3.3.2.3,        review of reactor design.
3.3.2.10, 3.3.2.12, 3.3.2.13, 3.3.3.2.2, Table 3.3-1, Figures 3.3-1, 3.3-2, 3.3-3, 3.3-7, 3.3-8, & 3.3-9, Table 3.4-1, 3.6.1.2, 3.6.2, 3.6.3.1, 4.3.1.1, 4.3 Refs, 9.1.1.2, 9.1.2.3.1, 9.1 Refs
[FS 2000-025]
1.2.5, 1.4.70, 7.2.1.1, 7.7.1, 9.1.2.1, 9.1.2.6.15, Incorporated technical and editorial corrections 9.2, 9.2.1, 9.2.2, 9.2.3, 9.2.4, Tables 9.2-1      and clarifications resulting from the integration
& 9.2-2, Figure 9.2-1, 9.7.2, 11.2.3, 11.2.3.1.1,  review of the boron recovery and waste 11.2.3.1.2, 11.2.3.1.3, 11.2.3.1.11, 11.2.3.2,      disposal systems.
11.2.3.2.1, 11.2.4.1.3, 11.2.4.1.5, 11.2.4.2, 11.2.4.2.1, 11.2.4.2.3, 11.2.4.2.5, 11.2.4.2.7, 11.2.4.2.11, 11.2 RefDwgs, Tables 11.2-1, 11.2-8 through 11.2-10, Figures 11.2-1
& 11.2-2, 11A.4.2
[FS 99-031]
1.2.8, 1.4.24, 1.4 RefDwgs, 4.3.6, 7.7.1, 8.1,      Incorporated technical and editorial corrections Figure 8.1-1, 8.2, 8.3, 8.3 RefDwgs,                and clarifications resulting from the integration Figure 8.3-2, 8.4.1, 8.4.2, 8.4.3, 8.4.4, 8.4.6,    review of the vital bus and station service 8.5, 8.6, 9.1.3.1                                  systems.
[FS 99-051]
 
Revision 52Updated Online 09/30/20                          SPS UFSAR                                51 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3209/01/00 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
1.4.3, 7.2.2.1.1, 7.7.2, 9.1.2.1, 9.3.2.1, 9.4.3.1, Incorporated technical and editorial corrections 9.10.1, 9.10.2.1, 9.10.2.2.1, 9.10.2.2.3,          and clarifications resulting from the integration 9.10.2.2.5, 9.10.2.2.7, 9.10.2.2.9, 9.10.2.3.2,    review of the fire protection system.
9.10.2.3.3, 9.10.2.4, 9.10.2.6, 9.10.2.8, 9.10.2.9, 9.10.3.3, 9.10.3.4, 9.10.3.5, 9.10.4.1, 9.10.4.3, 9.10.4.4, 9.10.4.5, 9.10.4.7, 9.10.4.8, 9.10.4.9, 9.10.4.10, 9.10.4.11, 9.10.4.12, 9.10.4.14, 9.10.4.15, 9.10.4.16, 9.10.4.17, 9.10.4.18, 9.10.4.19, 9.10.4.20, 9.10.4.22, 9.10.4.23, 9.10.4.24, 9.10.4.25, 9.10.4.26, 9.10.4.27, 9.10.5, 9.10.6, Table 9.10-1, 9.11.1, Table 9.11-1, Figure 9.11-1, 9.13.4.1, 10.3.9.3, 11.1, 11.1 Refs
[FS 99-027]
1.4.5, 7.7.2, 9.1.2.2, Figure 10.3-2, 12.1.1.2.1,  Corrected typographical, administrative, and 12.4, 12.5, 12.6, 13.1, 14.2.2, 14.2.2.1,          format errors.
14.2.5.1, 14.2.5.2.2, 14.2.9.2.3, 14.2.9.2.4.1, Table 14.2-4, Figure 14.2-84, 14.3.2.1, 14.3.2.2.1, 14.3.3.2.2.2, 14.3.3.2.2.4, 14.4.1.2.2.1, 14.4.2.1, Table 14.4-6, 14.5.2.3, 14.5.2.4.2, 14.5.3.3.2, 14.5.3.4.1, 14.5.5.2, 14.5 Refs, Table 14.5-14, Figures 14.5-5
& 14.5-38, 15.4.6
[FS 2000-023]
1.4.11, 5.3.1.2, 5.3.1.3.2, 3.1.3.3, 5.3.1.3.4,    Incorporated technical and editorial corrections 5.3.1.4, 5.3.1.4.1, 5.3.1.5, Table 5.3-1, 6.3.1.4,  and clarifications resulting from the integration 7.7.2, 9.13.1, 9.13.3.2, 9.13.3.1, 9.13.3.2,        review of the ventilation system.
9.13.3.3, 9.13.3.4, 9.13.3.5, 9.13.3.6, 9.13.3.7, 9.13.3.9, 9.13.4, 9.13.4.1, 9.13.4.2, 9.14.2, 9.14.3, 10.3.6.2, 10.3.8.2, 11.2.2, 11.2.5, Table 11.2-11, 11.3.3.14, 11.3.6
[FS 99-040]
1.4.18, 9.4.1.3, 9.4.3.3, Tables 9.4-2 through      Incorporated technical and editorial corrections 9.4-5, 9.5.1, 9.5.3.4, 9.5 Refs, 9.5 RefDwgs,      and clarifications resulting from the integration Figure 9.5-1, Table 10.3-4, Figure 10.3-11          review of spent fuel pool cooling, chilled water,
[FS 99-049]                                        and bearing cooling systems.
 
Revision 52Updated Online 09/30/20                          SPS UFSAR                                52 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3209/01/00 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
1.4.24, 2.1.3.2, 2.4.3.3, 2.4.7.4, 2.4.8,          Corrected typographical, administrative, and Tables 2.4-13 & 9.5-1, 9.10.6, Figure 9A-1,        format errors.
11.1 Refs, 15.2.4, Table 15.2-1, 15.4.1
[FS 99-058]
1.4.46, 6.2.2.2.3, 6.2.2.2.4, Tables 6.2-5          Incorporated technical and editorial corrections
& 6.2-8                                            and clarifications resulting from the integration
[FS 98-042]                                        review of the safety injection system.
1.4.49, 1.4.55, 1.4.57, 5.2.1, 5.2.2, Tables 5.2-1  Incorporated technical and editorial corrections
& 5.2-2, 5.3.4, 5.3.4.1, 5.3.4.2, 5.3.4.3, 5.3.4.4, and clarifications resulting from the integration Tables 5.3-4 & 5.3-5, Figure 5.3-2, 5.4.2,          review of the containment systems.
5.4.2.1, 5.4 Refs, 5.5.1, 6.1, Table 6.2-7, 6.3.1.1, 6.3.2, 6.3.2.1, 6.3.2.2, 6.3.2.3, 6.3.2.4, Tables 6.3-4 & 6.3-5, Figure 6.3-6, 7.5.1.4.2, 15.5.1.2, 15.5.1.8
[FS 99-039]
1.5, 9.1, 9.1.1, 9.1.1.2, 9.1.1.3, 9.1.2, 9.1.2.1,  Incorporated technical and editorial corrections 9.1.2.4, 9.1.2.4.1, 9.1.2.5, 9.1.2.6.1, 9.1.2.6.2,  and clarifications resulting from the integration 9.1.2.6.7, 9.1.2.6.8, 9.1.2.6.9, 9.1.2.6.12,        review of the chemical and volume control and 9.1.2.6.15, 9.1.2.6.16, 9.1.2.6.17, 9.1.2.6.18,    residual heat removal systems.
9.1.2.6.19, 9.1.2.6.20, 9.1.3.1, 9.1.3.3, 9.1.3.5.2, 9.1.3.5.3, 9.1 Refs, Tables 9.1-1 through 9.1-3, 9.1-8, & 9.1-9, 9.3.1, 9.3.2.1, 9.3.2.2.2, 9.3.2.2.3, 9.3.3.1, 9.3.3.2, Tables 9.3-2 through 9.3-4, 9.4.1.1, 9.9.1.3
[FS 99-041]
Figures 2.4-6 & 2.4-7, 6.2.3.10, 7.9.2.5,          Corrected typographical, administrative, and 7.10.2.1, 7.10.2.2, 12.1.1.2.1, 14.5 Refs          format errors.
[FS 2000-018]
3.6.3.1, 9A.2, 14.5.2.3                            Corrected typographical, administrative, and
[FS 2000-040]                                      format errors.
4.1.7.4, 4.1 Refs, Tables 4.1-13 through 4.1-15    Incorporated the most recently acquired and
[FS 2000-035]                                      currently applicable reactor vessel material properties data.
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                                53 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3209/01/00 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                    where indicated in brackets.
Table 4.1-2, 9.10.3.3, 9.10.4.2, 9.10.4.3,      Incorporated technical and editorial corrections 9.10.4.13, 10.3.1.2, 10.3.1.5, 10.3.3.1,        and clarifications resulting from the integration 11.3.3.14, 14.3.1.2, 14.3.1.3, 14B.2.3.2.3,    review of the high energy line break.
14B.4.2, 14B.4.3, 14B.5.1.1, 14B.5.1.4, 14B.5.1.5, 14B.5.1.6, 14B.5.1.6.1, 14B.5.1.6.2, 14B.5.1.6.3, 14B.5.1.6.4, 14B.5.1.6.4.2, 14B.5.1.6.4.3, 14B.5.1.6.4.5, 14B.5.2.1, 14B.5.2.5, 14B.5.3.3, 14B.5.4.2, 14B Refs, Tables 14B-2, 14B-3, & 14B-9, Figures 14B-1
& 14B-10
[FS 2000-007]
Table 4.1-4, 10.3.1.2, 10.3.4.2, 10.3.5.2,      Incorporated technical and editorial corrections 10.3.6.2, Figure 10.3-2                        and clarifications resulting from the integration
[FS 99-038]                                    review of the feedwater, condensate, steam generator blowdown, and condensate polishing systems.
4.2.11, 4.2 Refs, 9.3.1, 9.6.2.1, 9.6.2.2.6,    Incorporated technical and editorial corrections 9.6.3.2, Tables 9.6-7 & 9.7-1, Figure 9.7-1,    and clarifications resulting from the integration 10.3.8.1                                        review of the sampling and primary vents and
[FS 99-047]                                    drains systems.
5.2.2, 5.2 Refs                                Updated the discussion of acceptable closure
[FS 2000-031]                                  time of a normally closed manual isolation valve.
Table 5.2-1                                    Reflected the addition of a new inside
[FS 99-054]                                    containment isolation valve.
Tables 5.2-1 & 5.2-2                            Updated Table 5.2-1 to reflect changes to
[FS 99-045]                                    valves subject to Type C testing as defined in 10 CFR 50, Appendix J. [10 CFR 50, Appendix J]
 
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Revision 3209/01/00 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
5.4.1.3.4, 6.2.2.1.4, 14.1, 14.1 Refs, 14.2.1,    Incorporated technical and editorial corrections 14.2.2.2, 14.2.2.3, 14.2.4.2, 14.2.7.2,          and clarifications resulting from the integration 14.2.7.3.1, 14.2.7.3.3, 14.2.7.4, 14.2.9.2.1,    review of the plant safety analyses.
14.2.9.2.2.2, 14.2.9.2.4.1, 14.2.9.2.4.3, 14.2.10.4.2, 14.2.13, 14.2 Refs, Figures 14.2-16 through 14.2-21, & 14.2-27, 14.3.1.1, 14.3.1.4.3, 14.3.1.4.4, 14.3.2.1, 14.3.2.2.1, 14.3.2.5, 14.3.3.1.1.2, 14.3.3.2.1, 14.3.3.2.1.2, 14.3 Refs, Tables 14.3-8, 14.3-11,
& 14.3-12, 14.4.1.1, 14.4.1.2, 14.4.1.2.1, 14.4.1.2.2.2, 14.4.1.3.1, 14.4.2.1, 14.4.2.2.1, 14.5.1.2, 14.5.1.3, 14.5.1.8, 14.5.2.3, 14.5.2.4.2, 14.5.6, 14.5 Refs, Tables 14.5-2, 14.5-11, & 14.5-12, Figures 14.5-30 & 14.5-31
[FS 2000-016]
Table 6.2-6, Table 6.3-2, 14.5.5.3, 14.5 Refs    Updated the allowable leakage from the safety
[FS 2000-008]                                    injection and charging systems.
7.2.2.2.10, 7.3.2.2.3, 7.4.3.4, 7.4.3.6, 7.4.3.8, Incorporated technical and editorial corrections 7.4.4.1, 7.4.4.3, 7.4.4.4.2, 7.4.4.4.3,          and clarifications resulting from the integration Table 7.4-3, Figure 7.4-2, 7.6.1, 7.6.2.1,        review of the nuclear instrumentation system.
7.6.2.3.1, Figure 7.6-1, 7.11.1
[FS 99-035]
7.3.1, 7.3.2.1, 7.3.2.2.1, 7.3.2.2.2, 7.3.2.3.1,  Incorporated technical and editorial corrections 7.3.2.3.2, 7.3.3.2, 7.3.3.5, 7.3 RefDwgs, 7.7.2,  and clarifications resulting from the integration 7.8.1, 7.8.2, 7.8.3, Figure 7.8-1                review of the nuclear control system.
[FS 99-059]
7.7.2, 9.10.3.5, 9.10.4.13, 10.3.1.2              Incorporated changes to reflect that the decay
[FS 99-033]                                      heat release subsystem is no longer used and that decay heat release components have been removed on Unit 2.
7.12.1.1, 10.3.5.3                                Incorporated technical and editorial corrections
[FS 2000-022]                                    and clarifications resulting from the integration review of the electrical instrumentation and plant computer system.
9.4.4.3, 9.8.1, 9.8.2, 9.8.3, 9.8.4, Table 9.8-1, Incorporated technical and editorial corrections Figure 9.8-1, 10.3.9.3, Table 15.2-1              and clarifications resulting from the integration
[FS 2000-011]                                    review of the instrumentation air system.
 
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Revision 3209/01/00 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
Table 9.4-1                                        Updated the design data for the component
[FS 96-032]                                        cooling water heat exchangers to describe the replacement heat exchangers.
9.7.2, 11.2.2, 11.2.5, 11.2.5.1, 11.2.5.2.3,      Incorporated technical and editorial corrections 11.2.6.1, Tables 11.2-2 & 11.2-3                  and clarifications resulting from the integration
[FS 99-028]                                        review of the gaseous waste disposal system.
9.7.3                                              Incorporated a modification to the level
[FS 99-023]                                        detector and controls for the auxiliary building sump pumps.
9.9.1.2                                            Updated the description of emergency service
[FS 99-007]                                        water pump capacity associated with a design change to improve pump reliability.
9.9.1.3                                            Provided additional information concerning the
[FS 2000-034]                                      response required for hurricane conditions that are less severe than those produced by the probable maximum hurricane.
9.10.2.2.9, 9.10 Refs                              Added a description of the design basis for the
[FS 99-021]                                        halon system in the emergency switchgear rooms.
9.10.3.3, 10.3.1.2                                Added a description of the local operation of
[FS 99-019]                                        the atmospheric steam dump valves.
9.10.4.8                                          Incorporated terminology from new EPA
[FS 2000-010]                                      regulation, 40 CFR 279.22(c)(1).
9.12.4.4, 9.12.4.5, 9.12.4.6, 9.12.4.9, 9.12.4.13, Incorporated technical and editorial corrections 9.12.4.14, 9.12.5.2, 9.12.5.4, 9.12.6.2, 9.12.8, and clarifications resulting from the integration 9.14.2, 9A.2                                      review of fuel handling and storage.
[FS 2000-014]
9.13.2, 14B.5.2.1                                  Incorporated the environmental impact of a
[FS 2000-004]                                      turbine building high energy line break on the control room envelope, mechanical equipment room no. 5, and the emergency diesel generator room.
10.3.5.3, 14.2.11, 14.2.11.1, 14.2.11.1.1,        Incorporated the description of the reanalysis 14.2.11.1.2, 14.2.11.1.3, 14.2.11.1.4, 14.2.11.2, of the loss of normal feedwater event and the 14.2.12, 14.2 Refs, Figures 14.2-79                loss of ac power to the station auxiliaries event.
through 14.2-89
[FS 2000-015]
 
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Revision 3209/01/00 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
11A.4.1, 11A.4.2, Table 11A-1                      Added descriptions of the application of the
[FS 96-065]                                        Offsite Dose Calculation Manual.
12.4                                              Corrected the reference to the personnel
[FS 2000-026]                                      qualification requirements for SNSOC and station supervisory personnel. [10 CFR 50.90 License Amendment]
14.2.13                                            Specified that the governor and main stop
[FS 98-050]                                        valves are exercised on a periodic basis in order to eliminate part of the transient experienced during turbine inlet valve freedom testing.
14.5.1.6, 14.5.1.7, 14.5.2.6, 14.5.2.7, 14.5 Refs, Incorporated descriptions of the peak clad Tables 14.5-5 & 14.5-18                            temperature penalties and benefits in the large
[FS 99-060]                                        and small break LOCA analyses.
16.2                                              Revised the description of the administrative
[FS 99-052]                                        controls that apply to the Technical Requirements Manual.
17.2.1.2, 17.2.2.1, 17.2.17, Figure 17.2.1-1      Modified organizational titles and reporting
[FS 2000-033]                                      relationships associated with information technology.
17.2.1.2, 17.2.2.6, Figure 17.2.2-1                Updated organizational description to reflect
[FS 2000-009]                                      Supply Chain Management (Generation) titles.
17.2.1.2, Figure 17.2.1-2                          Modified organizational titles and reporting
[FS 2000-020]                                      relationships associated with records management.
17.2.1.2, Figure 17.2.1-2                          Modified organizational titles and reporting
[FS 2000-036]                                      relationships associated with the radwaste facility.
 
Revision 52Updated Online 09/30/20                            SPS UFSAR                                57 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3109/01/99 Changes Made under the provisions of 10 CFR 50.59 except Section                                                          where indicated in brackets.
KWI, 1.4.9, 1.4.16, 4.1.3.1, 4.1.4, 4.1.7.1,          Incorporated technical and editorial corrections 4.1.7.2, 4.1.7.4, 4.1 Refs, Tables 4.1-1, 4.1-5,      and clarifications resulting from the integration 4.1-8, 4.1-10, & 4.1-11, 4.2.1, 4.2.2.1, 4.2.2.3,      review of the reactor coolant system.
4.2.2.3.1, 4.2.2.3.2, 4.2.2.3.3, 4.2.2.4, 4.2.2.7, 4.2.2.8, 4.2.3, 4.2.5, 4.2.6, 4.2.7.2, 4.2.9, 4.2.9.1, 4.2.9.2, 4.2.9.3, 4.2.9.4, 4.2.9.5, 4.2.9.6, 4.2.9.7, 4.2.10, 4.2.10.1, 4.2.10.2, 4.2 RefDwgs, Tables 4.2-3 & 4.2-4, Figures 4.2-8 & 4.2-11, 4.3.1.3, 4.3.2, 4.3.3.1, 4.3.3.2, 4.3.4.2, 4.3.6, 4.3 Refs, Tables 4.3-4
& 4.3-5, 4.4.1.4, 7.2.3.2.3, 7.3.2.4, 7.10.1, 7.10.2.3, Table 7.10-1, 9.10.3.2
[FS 99-001]
KWI, 4.2.2.2, 6.2.3.3, 6.3.2.1, Tables 6.3-1          Provided grammatical and editorial corrections.
& 3, 7.6.2.1, 7.6.3, 7.10 References, 8.4.1, 8.4.4, Tables 11.2-8 & 9, 11.3.3.10, 14.2.6, 14.5.1.1, 14.5.1.4, 14.5.2.3, Table 14.5-14
[FS 98-052]
KWI, Tables 5.2-1 & 5.2-2, 7.5 References,            Revised key word references, corrected 9.1.2.3, Table 9.5-1, App 9B, 10.3.5.2,                formatting, typing, and capitalization errors, 10.3.5.3, 11.2.2, 11.2.3, 11.2.4, Tables 11.2-1 &      updated reference lists and references in text, 11.2-11, Figures 11.2-4 through 11.2-6,                added a list of tables to App 9B, and replaced a 11.3.3.1, 14.2.11, 14B.5.1.7, 16.2.2.1                non-standard drawing symbol.
[FS 99-004]
KWI, 15.3.2                                            Added references to the key word index and
[FS 95-045]                                            expanded the description of the containment reinforcing steel.
Ref Dwgs: 1.2, 1.4, 2.1, 2.3, 4.2, 5.3, 6.2, 7.2, Corrected reference drawing descriptions, 7.3, 7.7, 8.3, 8.4, 9.1, 9.2, 9.3, 9.4, 9.5, 9.6, 9.7, eliminated duplicate entries, and added 9.8, 9.9, 9.10, 9.11, 9.12, 9.13, 9.14, 10.2, 10.3, companion Unit 2 drawings, where 11.2, 11.3, 15.1, 15.5; Section 9.9                    appropriate, in the reference drawing list and
[FS 99-006]                                            revised drawing reference numbers in the text.
1.4.16, 1.4.17, 4.2.7.1, 7.7.2, 9.13.1, 9.13.4.1, Incorporated technical and editorial corrections 11.3.3, 11.3.3.1, 11.3.3.3, 11.3.3.7, 11.3.3.8,        and clarifications resulting from the integration 11.3.3.10, 11.3.3.13, 11.3.3.14, 11.3.4.1,            review of the radiation monitoring system.
11.3.4.2, 11.3.4.3, 11.3.4.4, 11.3.4.7, 11.3.6, 11.3 RefDwgs, Tables 11.3-6 through 11.3-9
[FS 99-002]
 
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Revision 3109/01/99 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
1.4.17, 6.3.1.2, Table 9.4-7, 9.9,              Incorporated technical and editorial corrections Tables 9.9-1&2, Figure 9.9-1, 9.10.4.17 & 18    and clarifications related to the Service Water
[FS 98-014]                                      (SW) System: deleted singular SW flow rate through recirculation spray heat exchangers, corrected the description of the emergency service water pumps, and enhanced the description of the high-level intake canal.
1.4.39, 8.5, Table 8.5-1, 9.10.2.4, & 9.10.4.19 Incorporated technical and editorial corrections
[FS 98-022]                                      and clarifications related to the Emergency Diesel Generator (EDG) System: improved the description of testing, enhanced the description of the auto tap changer configuration, corrected the EDG day tank capacity, rewrote the description of the undervoltage setpoint scheme, and improved the description of load sequencing.
1.4.59, Table 5.4-20, 6.1, Figures 6.1-1 & 2,    Incorporated technical and editorial corrections 6.2.3.3, 6.3.1.3, 6.3.1.5.1, 6.3.1.5.2,          and clarifications related to the Containment 6.3 References, Tables 6.3-1 & 3, Figure 6.3-1, Spray (CS) System: improved the description 13.1, Table 13.1-1, 13.5, 13.5.1, 13.5.1.1,      of testing; designated historical information; 13.5.1.2, 13.5.1.3, 13.5.1.3.1, 13.5.1.3.2,      corrected a cross-reference; corrected the figure 13.5.1.3.3, 13.5.1.3.4, 13.5.1.3.5, 13.5.2,      depiction of the RWST, CS pumps, and spray 13.5 References, Tables 13.5-1 & 13.5-2          headers; reflected the analyzed amount of time
[FS 98-027]                                      of system operation; enhanced the description of electrical cables; reworded RWST welding requirements; changed the RWST material description; clarified the capacity, heat tracing, and insulation of the chemical addition tank (CAT); resolved discrepancy regarding the manifold drain line; clarified description of electrical equipment testing; corrected rated pump flow; corrected pump motor insulation class; corrected nominal RWST operating temperature; clarified CAT pump horsepower rating; clarified pump operating temperature and test pressure description; clarified the description of check valves; and changed the depressurization time and subatmospheric peak pressure.
 
Revision 52Updated Online 09/30/20                          SPS UFSAR                                59 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3109/01/99 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
1.4.68, 1.4.69, 9.1.2.2, 11.2.2, 11.2.3, 11.3.2.1,  Incorporated technical and editorial corrections 11.3.2.2, 11.3.2.6, 11.3.2.9, 11.3.5.8,            and clarifications resulting from the integration Tables 11.3-3 & 11.3-4, 11A, Table 11A-1            review of the radiation protection system.
[FS 99-016]
1.5, 4.3.1.2, 6.2.2.2.7, 10.2 RefDwgs,              Incorporated technical and editorial corrections Figure 10.2-1, 10.3.1, 10.3.1.1, 10.3.1.2,          and clarifications resulting from the integration 10.3.1.3, 10.3.3, 10.3 RefDwgs, 14.3.2              review of the main steam system.
[FS 99-012]
Table 2.1-4, 10.3.1.4, 10.3.5.2                    Added ethanolamine to the list of chemicals
[FS 96-063]                                        used for pH control.
2.2.1.1, 2.2.1.2, 2.3.1.2.2, Table 9.4-9, 9.12.9.2, Updated text, table, and figure cross references; 11.3.4.5, Table 11A-1                              corrected typographical errors; revised
[FS 99-024]                                        non-standard number and unit formats; and sorted a table in alpha-numeric order.
2.3.1.1, 2.3.1.2.1, 2.3.2, 2.3 Refs, Tables 2.3-1 Updated the mean monthly discharge and flood through 2.3-4                                      discharge rates, added new references, and
[FS 95-038]                                        revised the descriptions of on-site and off-site wells.
3.2.1                                              Removed the description of boron injection via
[FS 96-054]                                        the safety injection system.
3.5.2.3                                            Revised the description of secondary neutron
[FS 97-008]                                        sources to reflect that they are optional in reload cores.
4.1.2.6, 4.2.7.1                                    Removed references to monitoring containment
[FS 96-059]                                        leakage by monitoring containment humidity.
4.1.7.4, 4.1 Refs, Tables 4.1-14 & 4.1-15          Updated reactor pressure vessel toughness data
[FS 99-018]                                        associated with Technical Specification Basis change.
Table 4.2-2, 9.1.2.6.8                              Revised the reactor coolant dissolved hydrogen
[FS 97-005]                                        guidelines to include startup, shutdown, and off-normal conditions.
4.3.3.1                                            Modified the description of inservice
[FS 98-006]                                        inspection requirements on the reactor coolant pump flywheel. [10 CFR 50.90 License Amendment]
4.3.4.2                                            Clarified the function of the PORV backup-air
[FS 96-053]                                        spare bottles.
 
Revision 52Updated Online 09/30/20                          SPS UFSAR                                60 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3109/01/99 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
Table 5.2-1, 5.3.1.3.1, 9.4.1.1, 9.4.4.7, 9.12.9.3, Updated text cross references, corrected 9.13.4.2, 11.2.3.1.7                                typographical errors, and improved
[FS 99-037]                                        grammatical usage.
Table 5.2-2                                        Added the description of a new valve to
[FS 96-021]                                        containment penetration No. 24.
Table 5.3-2, 9.4.1.2, 9.4.3.2, Tables 9.4-2,        Updated the description of the Unit 1 chilled 9.4-5, & 9.9-2, Figure 9.9-1, Table 10.3-4,        water system to reflect equipment replacement Figure 10.3-11                                      and changing the systems source of cooling
[FS 98-030]                                        water.
5.4.1.2                                            Incorporated a description of the revised
[FS 97-009]                                        method of calculating core stored energy.
6.2.2.2.4                                          Incorporated modifications to the safety
[FS 99-029]                                        injection system.
6.2.3.12, 6.2.3.13                                  Added a description of the portable passive
[FS 99-020]                                        autocatalytic recombiner and its use.
Table 6.2-6, Table 6.3-2, & 14.5.5.2                Improved consistency with the Technical
[FS 96-030]                                        Specifications description of safety injection and recirculation spray loop leakage limits.
Figures 6.2-1 & 6.2-2                              Incorporated modifications to the Unit 2 safety
[FS 99-005]                                        injection system.
6.3.1.3                                            Corrected typographical omission of a passage
[FS 98-043]                                        of recirculation spray pumps cylindrical suction screens.
6.3.1.5.2                                          Clarified the description of the initial testing of
[FS 98-026]                                        the recirculation spray system.
7.1, 7.1.1, 7.1.2, 7.2 Refs, 7.2.2.1.1, 7.2.2.1.4,  Incorporated technical and editorial corrections 7.2.2.1.6, 7.2.2.4, 7.2.3.3, 7.2 RefDwgs,          and clarifications resulting from the integration Tables 7.2-1 & 7.2-3, Figures 7.2-6, & 7.2-8        review of the reactor protection system.
through 7.2-11, 7.5.1, 7.5.1.2, 7.5.1.3, 7.5.1.4.1, 7.5.1.4.2, 7.5.2.2, 7.5.2.3.2, 7.5.3.5, Tables 7.5-1 & 7.5-2, Figures 7.5-1, 7.5-2, 7.5-4, & 7.7-1, 10.3.5.3, Table 13.1-1
[FS 98-048]
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                              61 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3109/01/99 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
7.3.2.6, 8.1, 9.2, 9.4, 9.4.4.5, 9.5, 9.9,      Incorporated editorial changes and corrections 9A.3.2.2.1, 9C.1, 9C.1.1, 10.3.1, 10.3.1.2,      to typographical errors.
10.3.2, 10.3.4, 10.3.5, 10.3.5.3, 10.3.9, 11.2.3.2, & Table 11.2-11
[FS 99-015]
7.4.3.2                                          Added new type of cable to the description of
[FS 97-030]                                      the source range nuclear instrument channels.
8.4, 8.5                                        Incorporated technical and editorial corrections
[FS 99-010]                                      and clarifications resulting from the integration review of the emergency power system.
8.4.4, 8.4.5                                    Added descriptions of concurrent power
[FS 98-029]                                      supplies to the new Unit 1 main control room Hathaway annunciator.
8.4.4, 8.4.5                                    Adds a description of the concurrent electrical
[FS 99-009]                                      supplies to the main control room Hathaway annunciators.
8.5                                              Clarified the EDG start/load acceptance time
[FS 98-031]                                      and power rating.
9.1.2.4, 9.1.2.4.1, 9.1.2.4.2, 9.1.2.4.3        Clarified the description of operation of the
[FS 96-050]                                      reactor makeup control.
9.1.2.6.22                                      Correct the description of chemical and volume
[FS 97-003]                                      control system piping operation an inspection.
Table 9.1-6 & 14.4.2.1                          Revised the description of the volume control
[FS 98-046]                                      tank rupture accident analysis.
9.2 & 10.3                                      Identified equipment described in the UFSAR
[FS 93-22]                                      that is installed but no longer used.
9.3.3.1                                          Removed non-combustible from the
[FS 98-017]                                      description of the radiant energy shield between the RHR pump motors.
9.4.1.1, 9.4.3.1, 9.4.3.2, 9.4.4.1, 9.4.4.3,    Incorporate changes to the description and 9.4.4.5, 9.4.5, Table 9.4-2                      operation of the component cooling system.
[FS 97-006]
9.4.3.1                                          Revises the component cooling water
[FS 98-002]                                      chemistry chromate concentration and pH limits.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                                62 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3109/01/99 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
9.4.3.2                                          Incorporated a revised description of the
[FS 96-008]                                      modified chiller alarms.
9.4.3.4                                          Added a description of the charging pump seal
[FS 97-018]                                      cooling system modification to a once-through cooling system.
9.4.4.1                                          Removed the description of automatic closure
[FS 96-025]                                      of the primary drain cooler component cooling return line.
Table 9.4-8                                      Deleted the table description of the condensate
[FS 97-023]                                      makeup line check valve.
9.5.1, 9.12.5.5, 9.12.9.1, 9.12.9.2, 9.12.9.3,    Updated the description of spent fuel handling Table 9.12-1                                      and the requirements for cask handling in and
[FS 96-012]                                      around the spent fuel pool.
9.5.3.4                                          Deleted the reference to an assumed value for
[FS 97-016]                                      fuel assembly offload rate.
Table 9.5-3                                      Added description that power to the spent fuel
[FS 97-029]                                      pool cooling pumps is supplied from emergency buses.
9.9 & 9.10.4.17                                  Provided grammatical and editorial corrections.
[FS 98-041]
9.9.1.3, 9.10.4.13, 10.3.1.5, 10.3.5.1, 10.3.5.2, Incorporated technical and editorial corrections 10.3.5.3, 10.3.5.4, Table 13.5-2, 14B.5.1.7,      and clarifications resulting from the integration Figure 14B-20                                    review of the Auxiliary Feedwater System.
[FS 98-037]
9.9.2                                            Added the description of a temporary service
[FS 98-018]                                      water supply path to the component cooling heat exchangers. [10 CFR 50.90 License Amendment]
9.12.3.4, 11.3.4.1, 11.3 References              Incorporated the exemption form criticality
[FS 97-042]                                      monitoring in the fuel storage and handling areas. [10 CFR 70.14 Exemption]
9.12.4 & App. 9B.1                                Enhanced the description of heavy loads and
[FS 97-002]                                      their handling.
9.12.5.4                                          Revised the refueling reassembly sequence to
[FS 97-022]                                      reflect current practice.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                              63 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3109/01/99 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
9.12.5.4                                          Improved the refueling procedure reassembly
[FS 98-040]                                      sequence.
9.12.9, 9.12.9.2, 9.12.9.3                        Incorporated technical and editorial corrections
[FS 99-030]                                      and clarifications resulting from the integration review of the Surry ISFSI.
9A.1, 9A.2, 9A.3.1.2, 9A.3.1.3.2, 9A.3.1.4,      Revised the fuel assembly drop discussions 9A.3.1.5, 14.4.1.3.2, 14.4.1.3.2.1, 14.4.1.3.2.2, using a 42 inch drop in lieu of a 24 inch drop 14.4.1.3.2.3, Table 14.4-3                        and corrected typographical errors.
[FS 97-017]
9B.2.4.4                                          Added the SFP transfer canal gate lift rig to the
[FS 97-001]                                      list of special lifting devices.
9C.1, 10.3.4.2, 10.3.4.3                          Incorporated technical and editorial corrections
[FS 99-014]                                      and clarifications resulting from the integration review of the circulating water system.
10.3.1.2                                          Added a description of the new condensate
[FS 94-040]                                      return divert line to the steam generator blowdown heat exchangers.
10.3.1.4                                          Updated the description of the secondary plant
[FS 98-036]                                      chemistry monitoring and control.
10.3.5.1                                          Removed extraneous detail from the
[FS 95-017]                                      description of the steam generator feedwater pumps.
10.3.7.3, 10.3.7.4                                Corrected the description of the function and
[FS 96-058]                                      testing of the dc motor-driven oil pump.
10.3.12                                          Clarified the description of the main steam trip
[FS 97-021]                                      valve Appendix R solenoid operated valves.
11.2.3, 11.2.3.1.8, Figure 11.2-4                Revised the description of the RF liquid waste
[FS 97-041]                                      reverse osmosis system.
11.2.3.1.7, 11.2.4.1.4, Table 11.2-1              Added a description of the new RF liquid waste
[FS 96-039]                                      reverse osmosis system and revised liquid waste handling descriptions.
11.2.3.1.8, Figure 11.2-4                        Clarified the operation of the liquid waste
[FS 99-017]                                      reverse osmosis and demineralizer system.
11.2.5.3.4                                        Incorporated a revised description of the
[FS 95-036]                                      modified waste gas decay tank oxygen analyzer.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                                64 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3109/01/99 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
11.3.4.3                                          Corrected the nominal counting rates for
[FS 96-007]                                      limiting isotopes of the containment gas monitors.
11.3.5.1, 11.3.5.3, 11.3.5.5, 11.3.5.6, 11.3.5.7, Incorporated changes to the Radiological 11.3.5.9                                          Environmental Monitoring Program
[FS 96-033]
12.2.2.3, 12.2 References                        Revised reactor operator training program
[FS 97-045]                                      references.
12.7                                              Incorporated revised security plan references.
[FS 97-014]
14.2.6, 14.2.6.1, 14.2.6.1.1, 14.2.6.1.2,        Revised the startup on an inactive loop accident 14.2.6.2, 14.2.6.2.1, 14.2.6.2.2, 14.2.6.2.3,    analysis description.
14.2.6.2.4, 14.2.6.2.5, & 14.2.6.3
[FS 95-041]
14.2.11, 14.3.2, 14B.4.2, 14B.6, 14B.6.1,        Augmented the description of effects of piping 14B.6.2, 14B Refs                                system breaks outside containment with a
[FS 99-032]                                      transient analysis of a high-energy line break in the main steam valve house.
14.3.2                                            Revised wording to clarify the main steam pipe
[FS 96-044]                                      break description.
14.5.5.3, 14.5 Refs                              Incorporated the results of a sensitivity analysis
[FS 99-036]                                      performed to evaluate acceptable quantities of emergency core cooling system in conjunction with potentially unfiltered exhaust from the Auxiliary Building.
15.5.1.8                                          Revised the description of containment
[FS 96-051]                                      electrical penetrations to address variations between manufacturers.
16, 16.1, 16.2, 16.2.1, 16.2.1.1, 16.2.1.2,      Relocated requirements for plant operation and 16.2.2, 16.2.2.1, 16.2.2.2, 16.2.2.3,            surveillance of systems to the Technical Tables 16.2-1, 16.2-2, & 16.2-3                  Requirements Manual (TRM). Explicitly
[FS 99-008]                                      incorporated the TRM into the UFSAR.
17.2.2.5                                          Updated the qualification requirements for
[FS 98-049]                                      Oversight personnel.
17.2.16.2                                        Incorporated a title change.
[FS 98-051]
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                                65 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3109/01/99 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
Table 17.2-0                                      Revised the description to indicate the both
[FS 98-038]                                        Innsbrook record vaults meet ANSI requirements.
Revision 3009/01/98 Changes Made under the provisions of 10 CFR 50.59 except Section                                                        where indicated in brackets.
1.4, 6.1, 6.2, 6.3.1.5, 7.5.3.5, Tables 5.2-1&2,  Incorporated technical and editorial corrections Tables 5.4-18, 19, & 20, Tables 6.2-2, 3, 4, 5, 6, and clarifications related to the Safety Injection 10, 11, 12, &13, Figs. 6.1-1 & 6.2-2              System.
[FS 98-015]
1.4.59, 5.3.3, 6.2.3, 6.3.1, 7.5.2.2, 11.3.3.10,  Incorporated technical and editorial corrections Tables 6.3-1 & 3, Figs. 6.3-2, 3, & 5              and clarifications related to the Recirculation
[FS 98-019]                                        Spray System.
2.2.1.1, Table 2.2-7, 2.5.3.2, 6.1, 6.2.2.1.2,    Corrected references, typographical errors, and Table 6.2-1, 6.2.3.12.1, 6.2.4.1.4, 6.2            verb tense; clarified an abbreviated term and References, 7.4.3.6, Figure 7.5-1, 8.3, 9.6, 9.8,  illegible text; and corrected format of numbers, 9.10, 9B.2.1, 9B.2.4.1, 9B.2.4.4, 9B.2.4.7, 9C,    upper/lower case usage, and text lists.
11.2, Tables 11A-6, 7,9 & 10, Table 14.3-15, Table 14.5-11, 15.5.1.8 & Table 16.2-2
[FS 98-032]
3.3.3.2.2, 3.5, App. 9A & Tables 3.3-1 &          Increased the maximum fuel enrichment from 9.12-1                                            4.1 to 4.3 weight percent U-235.
[FS 97-043]                                        [10 CFR 50.90 License Amendment]
4.2.2.3.2                                          Added a description of the removal of the
[FS 98-024]                                        steam generator channel head drain lines.
5.3.1 & 9.13                                      Revised description of auxiliary ventilation and
[FS 96-061]                                        containment ventilation systems to reflect changes in these systems design and operation.
5.4 & Tables 5.4-17, 5.4-18, 5.4-19, 5.4-20,      Removed Containment concrete floor plugs 6.2-11, 6.2-12 & 6.2-13                            and the Pressurizer cubicle roof plug.
[FS 97-040]
6.2.2.1.1 & Table 6.2-2                            Updated the description of the Safety Injection
[FS 96-047]                                        control board indication.
6.2.2.1.3                                          Changed to state that pressure-relieving devices
[FS 96-027]                                        discharge to the liquid waste disposal system.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                              66 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3009/01/98 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
6.2.2.2.1                                        Clarified the tanks to which the accumulators
[FS 97-039]                                      may be drained.
6.2.2.2.4 & 6.2 References                        Revised description of safety injection valves
[FS 96-040]                                      MOV-1890A/B and MOV-2890A/B to reflect addition of pressure equalization line. Added Reference to NRC Generic Letter 95-07.
6.2.3.3                                          Changed containment spray and minimum
[FS 98-007]                                      recirculation spray pH ranges.
6.2.3.10, 6.2.4.1.4, 6.3.1.4, 15.5.1.3, 15.5.1.12 Revised the description of the Containment
& Figure 15.5-1                                  ground water control equipment, ground water
[FS 97-007]                                      protection methods, and liquid level alarms.
6.2.3.12                                          Changed post-LOCA containment hydrogen
[FS 98-009]                                      concentration for new initial conditions.
6.2.3.12.1                                        Revised valve stroke time for isolation of the
[FS 96-052]                                      volume control tank.
6.2.4.1.3, 6.2.4.1.4                              Changed to describe SI system testing as a
[FS 96-046]                                      series of tests during refueling, and to state that accumulator discharge check valves are tested during refueling.
6.3.1.2.1                                        Removed the statement that sodium hydroxide
[FS 97-004]                                      solution was only present in the containment spray system during system operation.
6.3.1.4, Tables 6.2-12 & 13                      Revised description of NPSH to the
[FS 98-021]                                      recirculation spray pumps to include impact several minor phenomena with impact on post-LOCA sump level.
7.2.3.2.7                                        Clarified the description of the AMSAC C-20
[FS 98-010]                                      setpoint.
8.6                                              Clarified preventive maintenance program
[FS 93-33]                                        requirements by deleting the statement which implies that insulation testing is performed on all electrical equipment.
9.9.1.2 & 9.9.3                                  Updated the description of Emergency Service
[FS 96-011]                                      Water Pump, 1-SW-P-1A, to indicate the removal of the electric motor drive.
 
Revision 52Updated Online 09/30/20                    SPS UFSAR                                67 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3009/01/98 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                  where indicated in brackets.
9.9.1.3 & 9.10.4.18                          Clarified the description of actions taken prior
[FS 96-055]                                  to the arrival of a hurricane onsite and corrected the classification of the circulating water valves as safety related.
9.9.2 & Table 2.1-4                          Updated the description of service water
[FS 96-036]                                  chemical treatment and updated the list of onsite chemicals.
9.10.4.16                                    Updated the description of Emergency Service
[FS 98-025]                                  Water Pump, 1-SW-P-1A, to indicate the removal of the electric motor drive.
10.3.1.2                                      Removed the statement that the Main Steam
[FS 98-013]                                  Safety Valves temperature flow probes are required for compliance with Regulatory Guide 1.97.
10.3.5.3, 14.2.11.1.3                        Relocated the stated numerical value of
[FS 96-041]                                  auxiliary feedwater (AFW) flowrate from the section describing the AFW system to the section where event analysis is described.
11.2.2, 11.2.5, & Tbl. 11.2-11                Modified descriptions of process vent system
[FS 97-035]                                  to remove implied wind speed limitations for system operation.
12.1.1.2.1, 17.2, & KWI                      Updated Station Manager title to Site Vice
[FS 98-003]                                  President and Assistant Station Managers titles to Manager-Station O&M and Manager-Station S&L. [10 CFR 50.90 License Amendment]
14.2.7                                        Updated the description of the feedwater
[FS 98-11]                                    temperature reduction event.
14.3.1                                        Revised the steam generator tube rupture
[FS 97-034]                                  accident analysis to reflect the evaluation of the effect of steam generator tube bundle uncovery on radioiodine release.
17.2.1.2.B.1                                  Identified the Site Vice President as the station
[FS 98-028]                                  position fulfilling the Plant Manager position identified in the ISFSI Technical Specifications.
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                              68 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 3009/01/98 (continued)
Changes Made under the provisions of 10 CFR 50.59 except Section                                                      where indicated in brackets.
17.2.3                                            Revised to reflect replacement of A/E
[FS 98-016]                                      Instruction Manual with an Engineering Standard.
Revision 293/1998 Section                                                              Changes 17.2, 17.2.1.2, 17.2.2.1, 17.2.3, 17.2.4, 17.2.5, Deleted reference to Nuclear Operations Figure 17.2.1-1, and Table 17.2-0                Department Standards and replaced with
[FS 97-026]                                      Nuclear Business Unit Standard. Added position of Project Manager (Configuration Management).
17.2.1.1 and 17.2.1.2                            Clarified organizational position descriptions
[FS 98-004]                                      by noting responsibilities for the ISFSI as they already exist.
17.2.1.2, Figure 17.2.1-2, and Figure 17.2.1-3    Deleted the position of Supervisor
[FS 98-005]                                      Administrative Services in the Nuclear Management organization and assigned duties and responsibilities to other positions.
17.2.2.6 and 17.2.2.8                            Clarified Quality Inspection Coordinator
[FS 97-038]                                      qualifications.
17.2.17, Tables 17.2-2 and 17.2-3                Added Generic Letter 88-18 commitment
[FS 97-048]                                      regarding storage of quality assurance records on optical disk media.
Table 17.2.0                                      Added provision for storage of quality
[FS 96-049]                                      assurance records in an approved offsite facility.
Table 17.2-0                                      Provided an additional alternative to
[FS 97-044]                                      ANSI/ANS 3.1.
Tables 17.2-2 and 17.2-3                          Clarified the description of onsite and offsite
[FS 98-012]                                      nuclear safety review committees.
 
Revision 52Updated Online 09/30/20                SPS UFSAR                              69 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 2802/11/98 Section                                                      Changes Foreword                                  Updated to reflect recent NRC initiatives regarding UFSAR submittal requirements, and adequacy and consistency of design basis information; and to note Virginia Powers adoption of electronic methods to enhance UFSAR maintenance, and UFSAR distribution in both hardcopy and electronic media.
5.5                                        Modified leak rate testing discussion to include
[FS 95-039]                                10 CFR 50, Appendix J, Option B performance-based leak rate testing rulemaking.
7.5.1.1                                    Changed low-low pressurizer SI manual block
[FS 96-045]                                setpoint from 2000 psia to 2000 psig.
9.6
* Added introduction and revised subsection
[FS 95-043]                                  headings
* Clarified the 3-hour requirement for PASS samples
* Deleted references to sampling abandoned flash evaporators
* Noted that condenser tube leakage monitoring may be by means other than chlorides monitoring
* Deleted superfluous HRSS equipment brand names
* Clarified operation of the HRSS waste tank
* Clarified remote indication of HRSS parameters
* Clarified SS valve isolation on an SI signal
* Clarified environmental qualification of HRSS containment sump pump 9.10 & 17.2                                Deleted references to the Training Center
[FS 96-042]                                records vault and associated features.
9.12                                      Updated to reflect current refueling practices.
[FS 96-022 R1]
14.5.2                                    Updated to reflect reanalysis of small break
[FS 96-057]                                loss of coolant accident (SBLOCA), including Tables 14.5-14 thru 16, and Figures 14.5-36, and 38 thru 68.
 
Revision 52Updated Online 09/30/20              SPS UFSAR                          70 Click on Change Package Number Highlighted in Red to View Change Request.
Revision 2802/11/98 (continued)
Section                                                      Changes Table 17.2-3                              Corrected typos.
[FS 97-037]
All (no change bars)
* Consolidated 7 volumes to 4 volumes
[FS 97-012] [FS 97-013]
* Referenced Station Drawings previously included in UFSAR; inserted simplified diagrams
* Removed notations associated with previously deleted material and renumbered sequentially
* Renumbered previously inserted items that had suffixes (e.g., 4A, 4B)
* Applied consistent typeface and page layouts
* Improved consistency of measurement notation (e.g., time, mass, velocity),
including abbreviations
 
Volume I Assignment Sheet General Table of Contents Revision 52Updated Online 09/30/20                                                  SPS UFSAR                                      TOC-i Surry Power Station Updated Final Safety Analysis Report Table of Contents Section                                                            Title                                                              Page
                          .....................................................................                                                                  1-1 VOLUME I Assignment Sheet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      TOC-i General Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .            TOC-i Foreword . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 List of Effective Pages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        LEP-1 CHAPTER 1 INTRODUCTION AND
 
==SUMMARY==
. . . . . . . . . . . . . . . . . . . . . . . .                                                    1.1-1 1.1        Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          1.1-1 1.2        Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          1.2-1 1.3        Comparison with other Stations . . . . . . . . . . . . . . . . . . . . . . . . .                      1.3-1 1.4        Compliance with Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                  1.4-1 1.5        Common Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                1.5-1 1.6        Research and Development Requirements. . . . . . . . . . . . . . . . .                                1.6-1 CHAPTER 2 SITE CHARACTERISTICS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                                        2.1-1 2.1        Geography, Demography and Potential External Hazards. . . . .                                          2.1-1 2.2        Meteorology and Climatology . . . . . . . . . . . . . . . . . . . . . . . . . .                        2.2-1 2.3        Hydrology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          2.3-1 2.4        Geology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          2.4-1 2.5        Seismology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          2.5-1 CHAPTER 3 REACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                        3.1-1 3.1        General . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        3.1-1 3.2        Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .            3.2-1 3.3        Nuclear Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .            3.3-1 3.4        Thermal/Hydraulic Design and Evaluation . . . . . . . . . . . . . . . .                                3.4-1 3.5        Mechanical Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                3.5-1 3.6        Tests and Inspections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                3.6-1
 
Revision 52Updated Online 09/30/20                              SPS UFSAR                                      TOC-ii Surry Power Station Updated Final Safety Analysis Report Table of Contents (continued)
Section                                        Title                                                              Page CHAPTER 4 REACTOR COOLANT SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . .                            4.1-1 4.1    Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1 4.2    System Design and Operation . . . . . . . . . . . . . . . . . . . . . . . . . .              4.2-1 4.3    System Design Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . .            4.3-1 4.4    Tests and Inspections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      4.4-1 VOLUME II CHAPTER 5 CONTAINMENT SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                      5.1-1 5.1    General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      5.1-1 5.2    Containment Isolation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        5.2-1 5.3    Containment Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        5.3-1 5.4    Containment Design Evaluation. . . . . . . . . . . . . . . . . . . . . . . . .                5.4-1 5.5    Containment Tests and Inspections . . . . . . . . . . . . . . . . . . . . . .                5.5-1 CHAPTER 6 ENGINEERED SAFEGUARDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                        6.1-1 6.1    General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      6.1-1 6.2    Safety Injection System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        6.2-1 6.3    Consequence-Limiting Safeguards. . . . . . . . . . . . . . . . . . . . . . .                  6.3-1 CHAPTER 7 INSTRUMENTATION AND CONTROL . . . . . . . . . . . . . . . . . . . . .                                  7.1-1 7.1    Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.1-1 7.2    Reactor Protection System . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          7.2-1 7.3    Reactor Control System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          7.3-1 7.4    Nuclear Instrumentation System . . . . . . . . . . . . . . . . . . . . . . . .                7.4-1 7.5    Engineered Safeguards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        7.5-1 7.6    Incore Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        7.6-1 7.7    Operating Control Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          7.7-1 7.8    Computer System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      7.8-1 7.9    Inadequate Core Cooling (ICC) System. . . . . . . . . . . . . . . . . . .                    7.9-1
 
Revision 52Updated Online 09/30/20                            SPS UFSAR                                      TOC-iii Surry Power Station Updated Final Safety Analysis Report Table of Contents (continued)
Section                                      Title                                                              Page 7.10  Ex-Core Neutron Flux Monitor System . . . . . . . . . . . . . . . . . . .                    7.10-1 7.11  Level Instrumentation to Prevent Loss of Shutdown Cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      7.11-1 CHAPTER 8 ELECTRICAL SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                    8.1-1 8.1    General Description and Summary . . . . . . . . . . . . . . . . . . . . . .                  8.1-1 8.2    Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.2-1 8.3    System Interconnections. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          8.3-1 8.4    Station Service Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        8.4-1 8.5    Emergency Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . .              8.5-1 8.6    Tests and Inspections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      8.6-1 VOLUME III CHAPTER 9 AUXILIARY AND EMERGENCY SYSTEMS . . . . . . . . . . . . . . . .                                        9.1-1 9.1    Chemical and Volume Control System . . . . . . . . . . . . . . . . . . .                      9.1-1 9.2    Boron Recovery System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          9.2-1 9.3    Residual Heat Removal System . . . . . . . . . . . . . . . . . . . . . . . . .                9.3-1 9.4    Component Cooling Systems . . . . . . . . . . . . . . . . . . . . . . . . . . .              9.4-1 9.5    Fuel Pool Cooling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . .            9.5-1 9.6    Sampling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      9.6-1 9.7    Vent and Drain System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          9.7-1 9.8    Compressed Air System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          9.8-1 9.9    Service Water System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        9.9-1 9.10  Fire Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.10-1 9.11  Water Supply and Treatment Systems . . . . . . . . . . . . . . . . . . . .                  9.11-1 9.12  Fuel Handling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        9.12-1 9.13  Auxiliary Ventilation Systems . . . . . . . . . . . . . . . . . . . . . . . . . .            9.13-1 9.14  Decontamination Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        9.14-1
 
Revision 52Updated Online 09/30/20                            SPS UFSAR                                        TOC-iv Surry Power Station Updated Final Safety Analysis Report Table of Contents (continued)
Section                                      Title                                                                  Page Appendix 9A    High-Density Spent-Fuel Storage Rack Design. . . . . .                                9A-i 9A.1  Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-1 9A.2  Storage Rack Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .            9A-1 9A.3  Storage Rack Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          9A-3 Appendix 9B    Movement of Heavy Loads . . . . . . . . . . . . . . . . . . . . .                      9B-i 9B.1  Heavy Loads Over Spent Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . .              9B-1 9B.2  Heavy Loads Over Safe-Shutdown Equipment . . . . . . . . . . . . . .                            9B-4 Appendix 9C    Flood Control System . . . . . . . . . . . . . . . . . . . . . . . . .                  9C-i 9C.1  Design Basis Flooding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        9C-1 9C.2  Individual Plant Examination Internal Flooding . . . . . . . . . . . . .                        9C-4 CHAPTER 10 STEAM AND POWER CONVERSION . . . . . . . . . . . . . . . . . . . . . .                                10.1-1 10.1  General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      10.1-1 10.2  Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.2-1 10.3  System Design and Operation . . . . . . . . . . . . . . . . . . . . . . . . . .              10.3-1 CHAPTER 11 RADIOACTIVE WASTES AND RADIATION PROTECTION . .                                                        11.1-1 11.1  General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      11.1-1 11.2  Radioactive Waste Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . .            11.2-1 11.3  Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      11.3-1 Appendix 11A Radiation Exposure Evaluation for Expected Radioactive Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-i 11A.1 Analytical Basis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-1 11A.2 Input Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-1 11A.3 Plant and Animal Census . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          11A-3 11A.4 Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      11A-3 CHAPTER 12 CONDUCT OF OPERATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                        12.1-1 12.1  Organizational Structure of Virginia Electric and Power Company 12.1-1 12.2  Training Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      12.2-1
 
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Section                                          Title                                                              Page 12.3  Emergency Planning. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          12.3-1 12.4  Review and Audit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .        12.4-1 12.5  Plant Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      12.5-1 12.6  Plant Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.6-1 12.7  Industrial Security . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .      12.7-1 12.8  Shift Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.8-1 CHAPTER 13 INITIAL TESTS AND OPERATION . . . . . . . . . . . . . . . . . . . . . . . .                              13.1-1 13.1  Tests Prior to Initial Reactor Fueling . . . . . . . . . . . . . . . . . . . . .                13.1-1 13.2  Final Station Preparation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          13.2-1 13.3  Initial Testing in the Operating Reactor . . . . . . . . . . . . . . . . . . .                  13.3-1 13.4  Operating Restrictions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          13.4-1 13.5  Steam Generator Postrepair Start-Up Test Program . . . . . . . . .                              13.5-1 VOLUME IV CHAPTER 14 SAFETY ANALYSIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .              14.1-1 14.1  General . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.1-1 14.2  Core and Coolant Boundary Protection Analysis. . . . . . . . . . . .                            14.2-1 14.3  Standby Safeguards Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . .              14.3-1 14.4  General Station Accident Analysis. . . . . . . . . . . . . . . . . . . . . . .                  14.4-1 14.5  Loss-of-Coolant Accident . . . . . . . . . . . . . . . . . . . . . . . . . . . . .              14.5-1 Appendix 14A Radiation Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . .                  14A-i 14A.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14A-1 14A.2 Total Activity in the Core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          14A-1 14A.3 Activity in the Fuel Rod Gap. . . . . . . . . . . . . . . . . . . . . . . . . . . .              14A-1 Appendix 14B Effects of Piping System Breaks Outside Containment                                        14B-i 14B.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-1 14B.2 Criteria for Pipe Breaks and Methods for Analysis . . . . . . . . . . .                          14B-2
 
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Section                                          Title                                                                  Page 14B.3 High-Energy Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-12 14B.4 Plant Shutdown and Safety-Related Equipment . . . . . . . . . . . . . 14B-13 14B.5 Effects of Pipe Breaks and Cracks. . . . . . . . . . . . . . . . . . . . . . . . 14B-14 14B.6 Transient Analysis of a High-Energy Line Break in the Main Steam Valve House . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-29 14B.7 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-30 CHAPTER 15 STRUCTURES AND CONSTRUCTION . . . . . . . . . . . . . . . . . . . . .                                      15.1-1 15.1  Structures and Machinery Arrangement. . . . . . . . . . . . . . . . . . .                          15.1-1 15.2  Structural Design Criteria. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .              15.2-1 15.3  Material. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.3-1 15.4  Construction Procedures and Practices . . . . . . . . . . . . . . . . . . .                        15.4-1 15.5  Specific Containment Structural Designs. . . . . . . . . . . . . . . . . .                        15.5-1 15.6  Other Class I Structures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .            15.6-1 15.7  Masonry Walls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          15.7-1 Appendix 15A Seismic Design for the Nuclear Steam Supply System and Miscellaneous Components. . . . . . . . . . . . . . . . . .                            15A-i 15A.1 General Seismic Design Criteria for the Nuclear Steam Supply System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .              15A-1 15A.2 Seismic Design Criteria for Piping, Vessels, Supports and Reactor Vessel Internals . . . . . . . . . . . . . . . . . . . . . . . . . . . .              15A-1 15A.3 General Analytical Procedure for Seismic Design . . . . . . . . . . .                              15A-4 15A.4 Movement of Reactor Coolant System Components. . . . . . . . . . 15A-22 15A.5 Tests to Demonstrate the Conservatism of the Limit Curves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-23 15A.6 Reactor Coolant Loop (RCL) PIPING REANALYSIS SUBSEQUENT TO LEAK BEFORE BREAK AND SNUBBER ELIMINATION15A-26 CHAPTER 16 TECHNICAL SPECIFICATIONS AND TECHNICAL REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . .                                    16.1-1 16.1  Technical Specifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .              16.1-1
 
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Section                                        Title                                                                Page 16.2  Technical Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .          16.2-1 CHAPTER 17 QUALITY ASSURANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .                    17-1 CHAPTER 18 PROGRAMS AND ACTIVITIES THAT MANAGE THE EFFECTS OF AGING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .            18-1 18.1  New Aging Management Activities . . . . . . . . . . . . . . . . . . . . . .                    18-1 18.2  Existing Aging Management Activities . . . . . . . . . . . . . . . . . . .                      18-5 18.3  Time-Limited Aging Analysis . . . . . . . . . . . . . . . . . . . . . . . . . .                18-23 18.4  TLAA Supporting Activities . . . . . . . . . . . . . . . . . . . . . . . . . . .              18-32 18.5  References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-34
 
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Revision 52Updated Online 09/30/20                        SPS UFSAR                              1 FOREWORD In the May 9, 1980, edition of the Federal Register (45 FR 30614), the NRC published a Final Rule requiring all licensed reactors to periodically update their Final Safety Analysis Reports. The purpose of the Rule was to establish baseline reference documents to be used in recurring safety analyses by licensees, the NRC, or other interested parties.
The Supplementary Information section of the Final Rule notice stated that submittal of an updated FSAR does not constitute a licensing action, but is only intended to provide information. The NRC Staff may review the material submitted, but does not intend to formally approve it. The NRC intends to use the updated FSAR in the future for appropriate applications such as reporting of deviations from conditions stated in the UFSAR.
The Rule became effective July 22, 1980, and established the following basic requirements for Vepcos nuclear power stations:
* A complete Updated FSAR (UFSAR) was required as the initial submittal
* The UFSAR was to reflect information and analyses submitted to the NRC by Vepco, or prepared by Vepco pursuant to NRC requirements, since submission of the original FSAR (or, as appropriate, the last UFSAR)
* NOTE: The Supplementary Information section of the Final Rule notice clarifies this requirement by stating that no analyses other than those already prepared or submitted pursuant to NRC requirements are required because of the Rule: however, FSAR analyses that are known to be nonconservative based on new analyses must be updated. Other new analyses not previously included in the FSAR may be incorporated in the UFSAR at the option of the licensee. Furthermore, specialized studies provided in the original FSAR (e.g., seismology, meteorology) should include the latest information developed in response to NRC requirements when these studies are transferred to the UFSAR, and program type material referenced by the UFSAR (e.g., security plan, emergency plan, QA Program) should be referenced accurately. In addition, the level of detail in the UFSAR should be at least the same as but not necessarily greater than that provided in the original FSAR. Information on design changes should not be included until the changes are approved for use and operable.
* The initial UFSAR was due no later than July 22, 1982
* The initial UFSAR was required to be up-to-date as of a maximum of six months prior to the date of filing (January 31, 1982, was chosen by Vepco as the cutoff date)
* Subsequent updates are required at least annually and must reflect changes made up to a maximum of six months prior to the date of filing
 
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* One original and 12 copies of the initial UFSAR and subsequent updates are required to be submitted to the NRC
* The updates are required to be certified by a duly authorized officer of Vepco
* The initial UFSAR should be a clean document without change bars and revision numbers. The subsequent annual revisions should include change indicators and page change identification In response to the foregoing FSAR update requirements, Vepco and NUS Corporation executed an Agreement for FSAR update services in April 1981, and NUS began work on the project immediately. The project was accomplished in four basic phases:
: 1. Document Retrieval
: 2. Change Package Development
: 3. FSAR Revision
: 4. Printing
* During the initial document retrieval phase in the Spring of 1981, NUS engineers researched the licensing correspondence files at Vepco offices in Richmond and the design change files at the plant sites. All documents potentially affecting the FSAR were copied and taken to the NUS home office.
Following the initial document review phase, NUS engineers periodically visited Richmond and the plant sites to acquire newly developed information. NUS was also placed on the distribution list for Vepco/NRC correspondence.
The document retrieval phase continued until early 1982, at which time sufficient information was available to document changes up to the January 31, 1982, cutoff date.
* The documentation retrieved during the first phase was reviewed in detail during the second phase to determine the particular two-digit section or sections of the FSAR that should be revised, i.e., 1.1, 1.2, 1.3, etc. Copies of the document (or of the particular pages of the document that were of interest) were placed in separate files corresponding to the two-digit sections. These files were defined as change packages. Development of the change packages continued in parallel with the document retrieval phase, with new information being reviewed and assigned to appropriate change packages. The final change packages became a work product delivered to Vepco on conclusion of the update effort and are available for tracing the sources of changes to the original FSARs
* After development of the initial change packages the material filed therein was used in the third phase of the project to make the actual FSAR revisions. The revision process continued in parallel with the continuing development of the change packages.
 
Revision 52Updated Online 09/30/20                      SPS UFSAR                              3 The revision phase for most FSAR chapters included two cycles of Vepco review and comment. These comments became part of the change packages and were used in the development of the final draft UFSAR.
* Vepco reviewed and approved the final draft chapters of the UFSARs for printing. The printer prepared approximately 125 sets of the UFSARs. NUS delivered one original and 12 copies of the UFSAR directly to the NRC on July 20, 1982, for Surry and July 22, 1982, for North Anna. The original UFSARs were transmitted under cover letter supplied to NUS by Vepco (see the attachment to this foreword). The remaining copies were shipped to Richmond and the plant sites.
The following work products were also delivered to Vepco by NUS and are available for use in producing subsequent annual updates:
* Printers copy of the UFSARs
* Annotated FSARs (2 copies)
* Final Change Packages (2 sets)
* Plant Drawing Indexes
* Key Word Indexes
* IBM Displaywriter Floppy Discs (2 sets each of the FSAR, Annotated FSAR, and Key Word Index)
* Update Procedures
* Introductory Volumes to the FSARs including this foreword, a list of effective pages, the key word indexes, the plant drawing indexes and a record of changes Further 10 CFR 50.71(e) rulemaking pertaining to UFSAR requirements for nuclear power stations was promulgated as recently as July 29, 1996 [61 FR 39278]. In particular, the annual revision requirement has been relaxed to six months after each refueling outage provided the interval between successive updates does not exceed 24 months.
The NRC issued a letter to licensees dated October 9, 1996, entitled Request for Information Pursuant to 10 CFR 50.54(f) Regarding Adequacy and Availability of Design Basis Information. The letter required submittal of information that will provide the NRC added confidence and assurance that Virginia Electric and Power Companys nuclear plants are operated and maintained within their design bases and that any deviations are reconciled in a timely manner. The Companys response (Serial No. 96-535) dated February 7, 1997, described previously conducted programmatic reviews of the Updated Final Safety Analysis Report (UFSAR). The 1996 UFSAR Project Team examined the existing administrative controls for maintaining UFSAR content and usability. Process enhancements to simplify administrative
 
Revision 52Updated Online 09/30/20                        SPS UFSAR                              4 controls, to increase accountability for technical content, and to improve UFSAR accessibility and usability are promoted by conversion to electronic media.
Under separate cover (Serial No. 97-108) dated May 23, 1997, Virginia Electric and Power Company notified the NRC about its project to address potential regulatory concerns involving the current design and licensing bases for the Surry and North Anna Power Stations. This project scope exceeds the level of scrutiny normally applied to the current licensing basis through routine surveillance and quality assurance activities. In order to facilitate thorough review, exhaustive validation, and a rigorous corrective action process, the recommended conversion to electronic media was implemented in Revision 28 of the Surry UFSAR. The entire text of the UFSAR was entered into electronic media. The conversion was accomplished by a process of augmenting recent UFSAR revision word processing packages with scanned-in optical character recognition documents for the balance of text, tables, and figures not previously stored electronically. A 100-percent word-for-word proofing was conducted by comparing a printed version of the entire electronic document with current controlled distribution copies. Thus, the electronic UFSAR was conveyed into service as the quality assurance document of record without introducing any substantive, technical, or non-editorial changes.
 
Revision 52Updated Online 09/30/20 SPS UFSAR 5 Revision 52Updated Online 09/30/20                SPS UFSAR 6 Intentionally Blank
 
Revision 52Updated Online 09/30/20              SPS UFSAR    LEP-1 LIST OF EFFECTIVE PAGES VOLUME I General Table of Contents (Repeated in each volume)
First Page    Last Page  Revision TOC-i        TOC-viii    Revision 52Updated Online 09/30/20 Foreword First Page    Last Page  Revision 1            6          Revision 52Updated Online 09/30/20 List of Effective Pages First Page    Last Page  Revision LEP-1        LEP-6      Revision 52Updated Online 09/30/20 Chapter 1 First Page    Last Page  Revision 1-i          1-vi        Revision 52Updated Online 09/30/20 1.1-1        1.1-4      Revision 52Updated Online 09/30/20 1.2-1        1.2-6      Revision 52Updated Online 09/30/20 1.3-1        1.3-10      Revision 52Updated Online 09/30/20 1.4-1        1.4-40      Revision 52Updated Online 09/30/20 1.5-1        1.5-2      Revision 52Updated Online 09/30/20 1.6-1        1.6-8      Revision 52Updated Online 09/30/20 Chapter 2 First Page    Last Page  Revision 2-i          2-x        Revision 52Updated Online 09/30/20 2.1-1        2.1-36      Revision 52Updated Online 09/30/20 2.2-1        2.2-40      Revision 52Updated Online 09/30/20 2.3-1        2.3-30      Revision 52Updated Online 09/30/20 2.4-1        2.4-66      Revision 52Updated Online 09/30/20 2.5-1        2.5-32      Revision 52Updated Online 09/30/20
 
Revision 52Updated Online 09/30/20              SPS UFSAR    LEP-2 LIST OF EFFECTIVE PAGES (CONTINUED)
Chapter 3 First Page  Last Page    Revision 3-i        3-vi          Revision 52Updated Online 09/30/20 3.1-1      3.1-2        Revision 52Updated Online 09/30/20 3.2-1      3.2-12        Revision 52Updated Online 09/30/20 3.3-1      3.3-26        Revision 52Updated Online 09/30/20 3.4-1      3.4-34        Revision 52Updated Online 09/30/20 3.5-1      3.5-58        Revision 52Updated Online 09/30/20 3.6-1      3.6-6        Revision 52Updated Online 09/30/20 Chapter 4 First Page  Last Page    Revision 4-i        4-vi          Revision 52Updated Online 09/30/20 4.1-1      4.1-40        Revision 52Updated Online 09/30/20 4.2-1      4.2-44        Revision 52Updated Online 09/30/20 4.3-1      4.3-22        Revision 52Updated Online 09/30/20 4.4-1      4.4-10        Revision 52Updated Online 09/30/20 VOLUME II Chapter 5 First Page  Last Page    Revision 5-i        5-iv          Revision 52Updated Online 09/30/20 5.1-1      5.1-2        Revision 52Updated Online 09/30/20 5.2-1      5.2-38        Revision 52Updated Online 09/30/20 5.3-1      5.3-20        Revision 52Updated Online 09/30/20 5.4-1      5.4-54        Revision 52Updated Online 09/30/20 5.5-1      5.5-6        Revision 52Updated Online 09/30/20 Chapter 6 First Page  Last Page    Revision 6-i        6-iv          Revision 52Updated Online 09/30/20 6.1-1      6.1-6        Revision 52Updated Online 09/30/20 6.2-1      6.2-58        Revision 52Updated Online 09/30/20 6.3-1      6.3-34        Revision 52Updated Online 09/30/20
 
Revision 52Updated Online 09/30/20              SPS UFSAR    LEP-3 LIST OF EFFECTIVE PAGES (CONTINUED)
Chapter 7 First Page  Last Page    Revision 7-i        7-vi          Revision 52Updated Online 09/30/20 7.1-1      7.1-4        Revision 52Updated Online 09/30/20 7.2-1      7.2-52        Revision 52Updated Online 09/30/20 7.3-1      7.3-16        Revision 52Updated Online 09/30/20 7.4-1      7.4-26        Revision 52Updated Online 09/30/20 7.5-1      7.5-34        Revision 52Updated Online 09/30/20 7.6-1      7.6-6        Revision 52Updated Online 09/30/20 7.7-1      7.7-10        Revision 52Updated Online 09/30/20 7.8-1      7.8-4        Revision 52Updated Online 09/30/20 7.9-1      7.9-4        Revision 52Updated Online 09/30/20 7.10-1      7.10-2        Revision 52Updated Online 09/30/20 7.11-1      7.11-2        Revision 52Updated Online 09/30/20 Chapter 8 First Page  Last Page    Revision 8-i        8-ii          Revision 52Updated Online 09/30/20 8.1-1      8.1-2        Revision 52Updated Online 09/30/20 8.2-1      8.2-4        Revision 52Updated Online 09/30/20 8.3-1      8.3-6        Revision 52Updated Online 09/30/20 8.4-1      8.4-10        Revision 52Updated Online 09/30/20 8.5-1      8.5-10        Revision 52Updated Online 09/30/20 8.6-1      8.6-2        Revision 52Updated Online 09/30/20 VOLUME III Chapter 9 First Page  Last Page    Revision 9-i        9-xii        Revision 52Updated Online 09/30/20 9.1-1      9.1-42        Revision 52Updated Online 09/30/20 9.2-1      9.2-20        Revision 52Updated Online 09/30/20 9.3-1      9.3-10        Revision 52Updated Online 09/30/20 9.4-1      9.4-30        Revision 52Updated Online 09/30/20 9.5-1      9.5-10        Revision 52Updated Online 09/30/20 9.6-1      9.6-16        Revision 52Updated Online 09/30/20 9.7-1      9.7-10        Revision 52Updated Online 09/30/20 9.8-1      9.8-8        Revision 52Updated Online 09/30/20
 
Revision 52Updated Online 09/30/20              SPS UFSAR    LEP-4 LIST OF EFFECTIVE PAGES (CONTINUED)
Chapter 9 (continued)
First Page  Last Page    Revision 9.9-1      9.9-16        Revision 52Updated Online 09/30/20 9.10-1      9.10-50      Revision 52Updated Online 09/30/20 9.11-1      9.11-6        Revision 52Updated Online 09/30/20 9.12-1      9.12-18      Revision 52Updated Online 09/30/20 9.13-1      9.13-18      Revision 52Updated Online 09/30/20 9.14-1      9.14-6        Revision 52Updated Online 09/30/20 9A-i        9A-ii        Revision 52Updated Online 09/30/20 9A-1        9A-22        Revision 52Updated Online 09/30/20 9B-i        9B-ii        Revision 52Updated Online 09/30/20 9B-1        9B-16        Revision 52Updated Online 09/30/20 9C-i        9C-ii        Revision 52Updated Online 09/30/20 9C-1        9C-6          Revision 52Updated Online 09/30/20 Chapter 10 First Page  Last Page    Revision 10-i        10-iv        Revision 52Updated Online 09/30/20 10.1-1      10.1-2        Revision 52Updated Online 09/30/20 10.2-1      10.2-6        Revision 52Updated Online 09/30/20 10.3-1      10.3-54      Revision 52Updated Online 09/30/20 Chapter 11 First Page  Last Page    Revision 11-i        11-vi        Revision 52Updated Online 09/30/20 11.1-1      11.1-2        Revision 52Updated Online 09/30/20 11.2-1      11.2-40      Revision 52Updated Online 09/30/20 11.3-1      11.3-36      Revision 52Updated Online 09/30/20 11A-i      11A-ii        Revision 52Updated Online 09/30/20 11A-1      11A-28        Revision 52Updated Online 09/30/20 Chapter 12 First Page  Last Page    Revision 12-i        12-ii        Revision 52Updated Online 09/30/20 12.1-1      12.1-2        Revision 52Updated Online 09/30/20 12.2-1      12.2-4        Revision 52Updated Online 09/30/20 12.3-1      12.3-2        Revision 52Updated Online 09/30/20
 
Revision 52Updated Online 09/30/20              SPS UFSAR    LEP-5 LIST OF EFFECTIVE PAGES (CONTINUED)
Chapter 12 (continued)
First Page  Last Page    Revision 12.4-1      12.4-2        Revision 52Updated Online 09/30/20 12.5-1      12.5-2        Revision 52Updated Online 09/30/20 12.6-1      12.6-2        Revision 52Updated Online 09/30/20 12.7-1      12.7-2        Revision 52Updated Online 09/30/20 12.8-1      12.8-2        Revision 52Updated Online 09/30/20 Chapter 13 First Page  Last Page    Revision 13-i        13-ii        Revision 52Updated Online 09/30/20 13.1-1      13.1-12      Revision 52Updated Online 09/30/20 13.2-1      13.2-4        Revision 52Updated Online 09/30/20 13.3-1      13.3-10      Revision 52Updated Online 09/30/20 13.4-1      13.4-4        Revision 52Updated Online 09/30/20 13.5-1      13.5-24      Revision 52Updated Online 09/30/20 VOLUME IV Chapter 14 First Page  Last Page    Revision 14-i        14-xx        Revision 52Updated Online 09/30/20 14.1-1      14.1-6        Revision 52Updated Online 09/30/20 14.2-1      14.2-134      Revision 52Updated Online 09/30/20 14.3-1      14.3-80      Revision 52Updated Online 09/30/20 14.4-1      14.4-20      Revision 52Updated Online 09/30/20 14.5-1      14.5-136      Revision 52Updated Online 09/30/20 14A-i      14A-ii        Revision 52Updated Online 09/30/20 14A-1      14A-4        Revision 52Updated Online 09/30/20 14B-i      14B-ii        Revision 52Updated Online 09/30/20 14B-1      14B-78        Revision 52Updated Online 09/30/20 Chapter 15 First Page  Last Page    Revision 15-i        15-viii      Revision 52Updated Online 09/30/20 15.1-1      15.1-4        Revision 52Updated Online 09/30/20 15.2-1      15.2-26      Revision 52Updated Online 09/30/20 15.3-1      15.3-2        Revision 52Updated Online 09/30/20
 
Revision 52Updated Online 09/30/20              SPS UFSAR    LEP-6 LIST OF EFFECTIVE PAGES (CONTINUED)
Chapter 15 (continued)
First Page  Last Page    Revision 15.4-1      15.4-6        Revision 52Updated Online 09/30/20 15.5-1      15.5-70      Revision 52Updated Online 09/30/20 15.6-1      15.6-20      Revision 52Updated Online 09/30/20 15.7-1      15.7-2        Revision 52Updated Online 09/30/20 15A-i      15A-ii        Revision 52Updated Online 09/30/20 15A-1      15A-50        Revision 52Updated Online 09/30/20 Chapter 16 First Page  Last Page    Revision 16-i        16-ii        Revision 52Updated Online 09/30/20 16.1-1      16.1-2        Revision 52Updated Online 09/30/20 16.2-1      16.2-2        Revision 52Updated Online 09/30/20 Chapter 17 First Page  Last Page    Revision 17-1        17-2          Revision 52Updated Online 09/30/20 Chapter 18 First Page  Last Page    Revision 18-i        18-vi        Revision 52Updated Online 09/30/20 18-1        18-40        Revision 52Updated Online 09/30/20}}

Revision as of 02:04, 9 September 2021

2 to Updated Final Safety Analysis Report, Frontmatter (EPID L-2020-LRO-0076) - Redacted
ML21210A127
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/30/2020
From:
Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Reactor Regulation
Thomas V
Shared Package
ML21208A006 List:
References
20-325, EPID L-2020-LRO-0076
Download: ML21210A127 (92)
v • d • e


Text

SURRY POWER STATION UPDATED FINAL SAFETY ANALYSIS REPORT Revision 52Updated Online 09/30/20

Intentionally Blank Revision 52Updated Online 09/30/20 SPS UFSAR 1 Click on Change Package Number Highlighted in Red to View Change Request.

REVISION

SUMMARY

Revision 52---Updated Online 09/30/20 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Section 7.4.2.5 Instrumentation equipment design

[SPS-UCR-2017-012] modification CA3041565, TSCR 450-3.7 Section 8.3, Figure 8.3-1 Hopewell 212 Transmission line Name

[SPS-UCR-2020-007] Change SU-20-00107 Sections 11.2.5.1, 15.2, 15.2.3, 15.6.1 and SPS Response to RIS 2015-06, "Tornado Table 15.2-1 Missile Protection" ETE-CCE-2018-0002

[SPS-UCR-2020-002]

Section 15.2.3, References 15.2, Table 15.2-1 Surry Tornado Missile Risk Evaluator

[SPS-UCR-2019-010] Implementation ETE-SU-2019-0065 Section 9.10.2.1 Unit 1 and Unit 2 Fire Protection Upgrades.

[SPS-UCR-2017-011] SU-17-00132 Section 9.3.2.2, Table 9.3-2 Correction to Table 9.3-2

[SPS-UCR-2020-003] CA7434130 Tables 4.1-14, 4.1-15, 4.3-3, 4.3-4 Update to Unit 1 and Unit 2 Reactor Pressure

[SPS-UCR-2015-019] Vessel Toughness Data (Unirradiated)

PA3007476 14.2, 14.3, 14.4, 14.5, 6.2, 6.3, 9.6, Tables Updated Alternate Source Term Analysis 14.2-2 through 14.2-4, 14.3-7 through LBDCR/TSCR 405, CR474351, CR1053122 14.3-16, 14.4-1 through 14.4-3, 14.4-5, 14.4-6, 14.5-7, 14.5-8, 14.5-10, 14.5-11, 6.2-6, 6.3-22

[SPS-UCR-2017-014]

15.2.5 SPS Units 1 and 2 UFSAR Updates for

[SPS-UCR-2018-010] Beyond Design Basis (BDB) Flooding Mods

- Roof Parapets SU-18-00114

Revision 52Updated Online 09/30/20 SPS UFSAR 2 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 5109/30/19 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

2.2.1.2, 7.7.1, 9.10.1, 9.10.2.2.5, 9.10.2.2.9, Consolidated Emergency Operations Facility 9.13.1, 9.13.3.10, 11.3.4.7, 12.3, Table 2.2-10, LAR 17-325 Table 11.3-7

[SPS-UCR-2017-010]

8.5 Open phase Condition Detection and

[SPS-UCR-2015-012] Protection Systems.

SU-15-01023 10.3.5.2 Auxiliary Feedwater MOV Hot Short

[SPS-UCR-2018-003] Resolution Unit 2.

SU-16-00108 4.1 Refs, Table, 4.1-12, Table 4.1-13 Surveillance Capsule Schedule

[SPS-UCR-2017-006] NRC letter 17-243 (draft),

ETE-CEP-2017-001; LA3062568 Figure 6.1-2 U2 Hot Short Resolution Charging Cross-tie

[SPS-UCR-2017-013] Relocation SU-17-00135 18.2.16, 18.5 Steam Generator Program reference update

[SPS-UCR-2018-005] PA3063167 8.3, Figure 8.3-1 500kV Switchyard Circuit Breaker CB58202

[SPS-UCR-2014-022] Tie-in bounding package.

SU-14-01148 7.7.1, 9.10.2.6 Update reflects modification to the trunked

[SPS-UCR-2016-002] radio communications system.

8.3 Modified to correct an approved change that

[SPS-UCR-2018-004] was not properly incorporated.

Revision 5009/27/18 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

18.3.2.4, 18.5 Refs Update reflects license renewal inspection

[SPS-UCR-2017-008] frequency of pressurizer surge lines.

Revision 52Updated Online 09/30/20 SPS UFSAR 3 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 5009/27/18 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

10.3.5.2 Update reflects auxiliary feedwater motor

[SPS-UCR-2017-002] operated valves fire-rated cables for Appendix R.

Figure 6.1-1 Update reflects Unit 1 Charging Cross-tie for

[SPS-UCR-2017-004] Appendix R.

2.3.1.2.2 Modified description of the exhaust dampers

[SPS-UCR-2018-002] to correct an error made during UFSAR conversion to electronic.

4.1.4, 7.2.1.2, 7.2.1.8.3, 7.2.2.3, 7.2.3.2.1, Update reflects automatic rod withdrawal 7.2.3.2.2, Table 7.2-3, Table 7.2-4, 7.3.1, capability being disabled.

7.3.2, 7.3.2.2.1, 7.3.2.2.3, 7.3.3.2, 7.3.3.3, Figure 7.3-1, 7.4.3.4, 7.4.3.6, 14.1, 14.2.4.1, 14.2.5.4, 14.2.7.2, 14.2.8.1

[SPS-UCR-2016-012]

9C.1.1 Update adds description of MER 5 flood dike

[SPS-UCR-2017-016] features.

3.3.3.2.1, 3.3 Refs, 3.5 Refs Update reflects Reload Nuclear Design and

[SPS-UCR-2017-015] CMS5 Methodologies Revision 4909/28/17 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 14.3-16 Modified table to correct orientation and

[SPS-UCR-2017-009] restore original isotopes and concentration values.

9.10.4.18 and 10.3.7.1 Update reflects Turbine Oil Conditioner

[SPS-FS-2006-013] System Replacement.

14.2.5, 14.2, and 9.1.3.5 Update reflects Boron Dilution Safety

[SPS-UCR-2017-003] Analysis Revision 10.3.1.4, 10.3.5, and Figure 10.3.8 Update reflects installation of Unit 1

[SPS-FS-2006-028] condensate air in-leakage subsystem.

Revision 52Updated Online 09/30/20 SPS UFSAR 4 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4909/28/17 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 11.3-5 and Table 11.3-6 Update reflects replacement of the Surry

[SPS-UCR-2016-009] Radwaste Facility ventilation particulate and noble gas monitors.

3.5.2.1 Modified to add description of use of

[SPS-UCR-2016-008] demonstration or lead fuel assemblies.

9.1.3.1, Table 9.1-2, Figure 9.1-1, 9.10.1, Updated to reflect isolation of reactor coolant 9.10.3.2 pump seal cooling and the charging

[SPS-UCR-2016-007] cross-connect during fire events.

14.5.1.4, 14.5.1.7, Table 14.5-1, Table 14.5-6 Updated peak cladding temperatures.

[SPS-UCR-2016-010]

14B.5.1.6.1 Modified high energy line inspection for

[SPS-UCR-2016-011] consistency with technical requirements manual.

Revision 4809/29/16 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.10.1, 9.10.2.1, 9.10.2.2.5, 9.10.2.2.8, Update reflects code evaluations completed to 9.10.2.2.9, 9.10.2.8 address code deficiencies are included in the

[SPS-UCR-2016-005] Appendix R report.

7.4.3.2 Corrected source range pre-amplifier self test

[SPS-UCR-2015-008] frequencies.

Figure 15.1-2 Added note to Figure that refers the reader to

[SPS-UCR-2016-006] the referenced drawing.

3.5.2.6.1 Update reflects ASME revised stress criterion

[SPS-UCR-2015-020] for optimized ZirloTM high performance fuel cladding 14.1, 14.2.7.2, 14.2.9.1.1, 14.4.1.2 Update reflects increased

[SPS-UCR-2016-003] statistical/deterministic Fdelta H limits Table 4.1-5, 9.1.2.1 Update reflects reactor coolant pump

[SPS-UCR-2015-001] abeyance seal upgrade

Revision 52Updated Online 09/30/20 SPS UFSAR 5 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4809/29/16 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.10.4.8 Update clarifies component cooling pump

[SPS-UCR-2015-009] classification.

Table 5.2-1, Table 5.2-2, 6.2.2.1.4, 6.3.1.3.4, Update reflects addition of FLEX mechanical 9.1.2.1, 10.3.5.2 connections to the AFW, CH, CS & SI

[SPS-UCR-2012-011] systems to mitigate effects of a Beyond Design Basis Event.

9.10.2.6, 7.7.1 Update reflects addition of communication

[SPS-UCR-2014-014] equipment for offsite communication to mitigate effects of a Beyond Design Basis Event.

7.7.2, 7.10.2, 8.4.3, 9.1.2.1, 10.3.1.2, 14.3.1.5 Update reflects addition of electrical and

[SPS-UCR-2015-010] mechanical connections to the remote monitoring panels, CH, and backup IA systems to mitigate effects of a Beyond Design Basis Event.

8.4.5 Reflects using LEDs for emergency lighting

[SPS-UCR-2015-017] systems.

8.4.6 Updated to reflect the TSC Alternate Power

[FS-2008-005] Source - Final Package 6.2.2.2.4, 9.3.2.2.3 Updated to reflect MOVs with the pressure

[SPS-UCR-2010-027] locking modification Table 14.5-6 Reflects the Westinghouse LBLOCA error

[SPS-UCR-2015-011]

10.3.3.1, 14b.5.1.6.1, 18.2.1 Update reflects Relocation of TS augmented

[SPS-UCR-2015-016] inspection requirements (except RCP flywheel) to the TRM 2.2.1.2, Table 2.2-8, Table 2.2-9, Table 11A-4, Revised the Primary Met Tower Instrument Table 11A-5, Table 11A-6, Table 11A-7 Height

[SPS-UCR-2015-018]

Revision 52Updated Online 09/30/20 SPS UFSAR 6 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4709/30/15 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

6.2.2.2.4 Reflects additional MOV pressure locking

[SPS-UCR-2011-001] valve modifications.

3.5.2.1, 3.5.2.1.2, Table 3.5-3, Figure 3.5-9 Reflects implementation of the Westinghouse

[SPS-UCR-2015-006] integral nozzle design 9.8.1, 9.8.2, Table 9,8-1, 9.10.1, 10.3.9.3, Reflects the Compressed Air System Upgrade Table 10.3-4, Figure 10.3-11

[SPS-UCR-2010-010]

9.10.1 Update to include the Beyond Design Basis

[SPS-UCR-2013-014] Storage Building 3.5.2.3 Reflects Re-Insertion of Secondary Source

[SPS-UCR-2014-001] Assemblies - Bounding Configuration 14.5.3.4.1, References 55, 56, 57, 58, 59, and Update to include Beyond Design Basis 60, Table 14.5-18, 15.6.2.1, 15.6.2.2.1 Offsite Communications

[SPS-UCR-2015-014]

3.6.1.1 Revised Direct Power Distribution

[SPS-UCR-2015-005] Measurements for Start-Up to be made at 50%

RTP rather than 30% RTP Figure 8.3-1 Update to include the 500kV Switchyard

[SPS-UCR-2015-013] Circuit Breaker CB58202 Tie-in Interim Package 8.3, Figure 8.3-1 Reflects Removal of the 1G/2G 34.5KV

[SPS-UCR-2014-003] Overhead Feeders 14.2 Refs, 14.3 Refs, 14B Refs Incorporates Topical Report VEP-FRD-41,

[SPS-UCR-2015-003] Rev. 02.

4.2.2.4, 9.1.2.6.9, 9.1.2.6.12, 9.1.2.6.13 Reflects removal of the RCP Floating Ring

[SPS-UCR-2015-004] Seal.

Table 5.4-17, Table 6.2-12, Figures 6.3-6 Update reflects the revised Surry through 6.3-13, 8.5 Recirculation Spray Pump NPSH.

[SPS-UCR-2015-002]

18.2.9 License Renewal - update clarifies the

[SPS-UCR-2014-024] responsibilities for General Condition Monitoring.

Revision 52Updated Online 09/30/20 SPS UFSAR 7 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4709/30/15 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.10.1, 9.10.4.14 Update reflects Beyond Design Basis

[SPS-UCR-2014-010] installation of spent fuel pool external make-up water source.

3.2.1, 3.5.2.6.2.1, 3.5 Refs Update reflects Westinghouse revised clad

[SPS-UCR-2014-019] corrosion model for ZIRLO and Optimized ZIRLO.

3.2.3.3, 3.2 Refs, Table 3.2-1, 3.3.2.3, 3.4.2.3, Update reflects discussion of the W-3 3.4.3.2, 3.4 Refs, 4.2.9, 14.1, 14.1 Refs, Alternate DNB correlations approved in 14.3.2.1, 14.3.2.3 Appendix D to DOM-NAF-2-P-A and

[SPS-UCR-2014-021] increase to technical specification minimum temperature for criticality.

9.5.1 Update reflects installation of wide range

[SPS-UCR-2013-007] spent fuel pool instrumentation.

18.2.19, Table 18-1 Update reflects that work control inspections

[SPS-UCR-2014-012] for license renewal are required to be performed by a VT qualified individual.

5.5.3, 5.5.4, 5.5.6, 5.5.7 Update replaces reference to Regulatory

[SPS-UCR-2014-017] Guide 1.163 with NEI 94-01, Revision 3-A.

Figure 9.12-1 Updated figure for Fuel Transfer System.

[SPS-UCR-2014-018]

18.2.16, 18.5 Refs Modify reflects program name change from

[SPS-UCR-2014-020] Secondary Piping and Component Inspection program to Flow Accelerated Corrosion program.

Revision 46Updated Online 09/30/14 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 9.10-1 Update corrects horsepower value for the

[SPS-UCR-2009-009] replacement diesel-driven fire pump.

9.10.2.2.2, Table 9.10-1 Update reflects replacement of the

[FS-2008-010] diesel-driven fire pump.

Revision 52Updated Online 09/30/20 SPS UFSAR 8 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 46Updated Online 09/30/14 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.10.2.6, 9.10.4.5, 9.10.4.6 Clarified description of the Appendix R

[SPS-UCR-2014-008] equipment located in Normal Switchgear and Cable Tray Rooms.

9.10.2.2.2, 9.10.4.24, Table 9.10-1 Update reflects replacement of the

[SPS-UCR-2014-011] diesel-driven fire pump fuel tank.

3.5.2.3, 9.1.2.3.1, 9.1.2.3.2.5 Update reflects the re-insertion of secondary

[SPS-UCR-2014-009] source assemblies for Unit 2.

11.2.3, 11.3.2.10, 11.3 Refs Radiation protection description updated to

[SPS-UCR-2014-006] include the Steam Generator Storage Facility.

Table 14.5-6 Table updated to reflect a post analysis of

[SPS-UCR-2014-007] record evaluation performed to assess the effect of an error in the HOTSPOT burst strain model on peak cladding temperature for the large break loss of coolant accident.

5.1, Table 5.4-11, Table 5.4-12, Table 5.4-13, Update implements revised LOCA Table 5.4-17, Figure 5.4-3, Figure 5.4-4, containment safety analysis.

Figure 5.4-5, Table 6.2-4, Table 6.2-13, Figure 6.3-6, Figure 6.3-10

[SPS-UCR-2014-004]

9.10.2.2.1 Updated the Fire Protection System

[SPS-UCR-2014-002] description to reflect backup water supply.

10.3.5.2 Updated the Condensate System description

[SPS-UCR-2014-005] to reflect use as backup water for the Fire Protection System in an emergency.

4.1.7.3, 4.1 Refs Update reflects the Westinghouse documents

[SPS-UCR-2013-017] related to MUR Uprate Fluence Evaluations.

Table 9.7-1 Update reflects replacement of the last (4 of 4)

[SPS-UCR-2012-003] containment sump pump.

Figure 8.3-1 Update reflects final configuration of 34.5 kV

[SPS-UCR-2013-013] switchyard modifications.

Revision 52Updated Online 09/30/20 SPS UFSAR 9 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 46Updated Online 09/30/14 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 14.5-6 Update reflects post analysis of record

[SPS-UCR-2013-011] evaluation performed to assess the effects of revised heat transfer coefficient multiplier distributions on peak cladding temperature for the large break loss of coolant accident.

9.10.2.1 Update reflects Fire Detection System

[FS-2007-007] replacement - final configuration.

14.5.1.6, 14.5.3.2, 14.5, 15A.3.3, 15.A.6, Update reflects the updated reactor vessel 15A, Table 15A-5, Table 15A-6, Table 15A-7, lower radial key stiffness value.

Table 15A-8, Table 15A-9

[SPS-UCR-2013-009]

3.5.2.1, 3.5.2.1.4, 3.5, Figure 3.5-10 Update reflects incorporation of the Robust

[SPS-UCR-2013-010] Protective Grid and modified Debris Filter Bottom Nozzle to the 15 x 15 upgrade fuel assemblies.

15.5.1.11.2 Modify corrected the tornado missile velocity

[SPS-UCR-2013-015] requirement.

Revision 4509/30/13 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

14.3.3.2.3.1, 14.3.3.2.3.2, 14.3.3.2.3.3, Reflects implementation of a revised rod 14.3.3.2.3.4, Table 14.3-6, Figure 14.3-25, ejection analysis (ETE-NAF-2013-0052, Figure 14.3-27 Rev. 0).

[SPS-UCR-2013-008]

9.10.4.12 Update reflects removal of the stator cooler

[SPS-UCR-2013-004] oil collection trays from the reactor coolant pump oil collection system.

Table 9.7-1 Update reflects replacement of 3 of 4

[SPS-UCR-2013-001] containment sump pumps.

9.8.1, 9.8.2, 9.8.3, Table 9.8-1, Figure 9.8-1, Update reflects interim configuration of the 9.10.1 compressed air system upgrade.

[SPS-UCR-2013-002]

Revision 52Updated Online 09/30/20 SPS UFSAR 10 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4509/30/13 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 4.1-5, 9.1.2.1 Update reflects all reactor coolant pumps now

[SPS-UCR-2011-026] using Flowserve N-9000 seal.

10.3.1.4, 10.3.5.2, Figure 10.3-8 Condensate System description updated to

[SPS-UCR-2013-005] reflect installation of Unit 2 air in-leakage subsystem.

11.3.3, 11.3.3.14 Updated description for new monitors on

[SPS-UCR-2011-009] main steam lines and turbine driven auxiliary feedwater pump.

7.2.2.1.1, 8.2 Station service transformers description

[SPS-UCR-2011-019] updated to reflect replacement cables.

18.2.7 License renewal section updated to correctly

[SPS-UCR-2011-020] identify damper housings inspection requirements.

18.2.9, 18.2.19 License renewal section updated to clarify

[SPS-UCR-2011-032] commitments associated with general condition monitoring and work control process.

18.1.2, Table 18-1 License renewal section updated to indicate

[SPS-UCR-2012-006] commitment 9 is now complete.

18.2.15, Table 18-1 License renewal section updated to indicate

[SPS-UCR-2012-007] commitment 14 is now complete.

Figure 9.9-1 Service Water System figure updated to

[SPS-UCR-2012-013] reflect Unit 1 flash evaporation demineralizer assembly demolition.

2.5.3.1, Table 2.5-2 Additional information clarifies earthquake

[SPS-UCR-2012-012] history is based on a specific timeframe.

Table 14.5-6 Table updated to reflect post analysis of

[SPS-UCR-2012-005] record evaluation performed to assess the effects of fuel thermal conductivity degradation on peak cladding temperature for the large break loss of coolant accident.

Figure 3.5-9 Figure modified to add fuel type descriptor

[SPS-UCR-2012-010] that was previously omitted.

Revision 52Updated Online 09/30/20 SPS UFSAR 11 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4409/27/12 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.10.2.1 Fire Detection System updated to reflect

[SPS-UCR-2012-008] replacement of some of the Robertshaw panels with SimplexGrinnell panels.

Table 9.5-3 Table updated to reflect alternate power

[SPS-UCR-2010-028] sources for the spent fuel pool pump motor.

10.3.1.2 Steam generator blowdown discussion

[SPS-UCR-2012-001] updated to reflect rerouting of piping.

Table 9.13-1 Main control room and emergency switchgear

[SPS-UCR-2011-029] and relay room ventilation data updated to reflect minimum air flow required to maintain design ambient conditions following a bounding event.

18.2.15 License Renewal commitment on reactor

[SPS-UCR-2011-031] vessel internals guide cards updated.

14.5.1.7, Table 14.5-5, Table 14.5-6 Best estimate large break loss of coolant

[SPS-UCR-2012-002] accident analysis description updated to reflect change to containment heat sink surface areas.

10.3.5.2, Figure 10.3-9 Update reflects installation of the

[SPS-UCR-2009-001] ultrasonic flowmeters in the feedwater lines.

9.1.2.6.5 Deborating demineralizer discussion updated

[SPS-UCR-2010-024] to reflect use of deborating vessel as cation demineralizer.

14.2.9.2.4.2, Table 14.2-2, Table 14.2-4, Updated design basis accident radiological 14.4.1.2.1, 14.4.1.2.2, 14.4.1.3.1, 14.4.1.3.2, analyses for the fuel handling accident and 14.4, Table 14.4-1, Table 14.4-2, Table 14.4-5 locked rotor analysis.

[SPS-UCR-2011-008]

11.1 Updated radiation protection description to

[SPS-UCR-2011-023] reflect an upgrade to the Stations self contained breathing apparatus.

10.3.5.2 Auxiliary feedwater discussion updated for

[SPS-UCR-2010-026] use of Carbohydrazide for startup of Unit 1.

Revision 52Updated Online 09/30/20 SPS UFSAR 12 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4409/27/12 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

10.3.5.2 Auxiliary feedwater discussion updated for

[SPS-UCR-2011-006] use of Carbohydrazide for startup.

18.1.3, Table 18-1 License Renewal commitment on tank

[SPS-UCR-2011-014] inspections updated.

18.1.4 License Renewal commitment on non-EQ

[SPS-UCR-2011-028] cable inspections updated.

18.2.19 License Renewal completion of work control

[SPS-UCR-2011-030] audit commitment updated.

1.2.7, Figure 10.2-3, Figure 10.2-4, 10.3.3.1, Updated descriptions and associated analyses 10.3 Refs, Figure 10.3-1, 14.2.13, 14.2.13.1, to reflect Unit 1 turbine retrofit.

14.2.13.2, 14.2.13.3, 14.2 Refs, Figure 14.2-72, Figure 14.2-73, Figure 14.2-74, Figure 14.2-75, Figure 14.2-76, Figure 14.2-77, Figure 14.2-78

[SPS-UCR-2009-017]

Revision 4309/29/11 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

4.1.7.1, 4.1 Refs, Table 4.1-14, Table 4.1-15, Update reflects increase to the cumulative 4.2.5, 4.3.3.2, 4.3.4, 4.3 Refs, Table 4.3-3, core burnup applicability limit (effective full Table 4.3-4 power years) for reactor coolant system

[SPS-UCR-2010-007] pressure/temperature limits, low temperature overpressure protection system setpoints and low temperature overpressure protection system enabling temperature, to 48 effective full power years.

Table 3.2-1 Modification reflects correction of departure

[SPS-UCR-2011-025] from nucleate boiling ratio limit type on DNBR Limits Table.

6.2.2.2.4 Update reflects current listing of motor

[SPS-UCR-2010-017] operated valves that incorporate a pressure locking modification.

Revision 52Updated Online 09/30/20 SPS UFSAR 13 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4309/29/11 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

18.1.2, 18.2.6, Table 18-1 License Renewal completion of concrete

[SPS-UCR-2011-010] aging commitment updated.

18.3.5.3, Table 18-1 License Renewal implementation of Alloy

[SPS-UCR-2011-011] Management Program commitment updated.

18.2.7, Table 18-1 License Renewal completion of fire protection

[SPS-UCR-2011-012] piping aging effects commitment updated.

18.2.19 License Renewal Work Control Process audits

[SPS-UCR-2011-016] commitment updated.

18.2.7, Table 18-1 License Renewal completion of fire protection

[SPS-UCR-2011-017] sprinkler commitment updated.

18.3.2.4 License Renewal added dates the inspection

[SPS-UCR-2011-021] of the pressurizer surge lines was completed.

Table 18-1 License Renewal completion of worker

[SPS-UCR-2011-022] qualification commitment updated.

6.2.2.2.3, 9.1.2.6.21 Globe valve description updated.

[SPS-UCR-2010-015]

9.10.4.12 Fire protection description updated to reflect

[SPS-UCR-2010-031] addition of an oil collection assembly on each reactor coolant pump stator cooler.

8.2, 10.3.3.2, Table 10.3-4, Figure 10.3-11 Update reflects upgrading the isolated phase

[SPS-UCR-2010-032] bus duct for both Units.

3.5.2.2 Updated section to reflect a replacement batch

[SPS-UCR-2010-014] of enhanced performance control rod assemblies will be placed in service for cycle 24 operation.

4.1.7.1, 4.1 Refs, Table 4.1-12, Table 4.1-13 Updated the reactor vessel surveillance

[SPS-UCR-2011-007] capsule withdrawal schedule for 60-year operation.

2.3.1.2.2 Updated emergency service water pump

[SPS-UCR-2010-008] house discussion to reflect addition of missile shield.

Revision 52Updated Online 09/30/20 SPS UFSAR 14 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4309/29/11 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9C.2 Appendix on flooding updated to reflect the

[SPS-UCR-2011-003] high level stop log roller removal.

14.2.9.2.4.3 Modified locked rotor accident discussion to

[SPS-UCR-2011-005] make it consistent with other sections.

1.1.5, 1.1.6, 3.2.2.1, 3.2.2.7, 3.2.3.3, 3.2 Refs, Updated descriptions and associated analyses Table 3.2-1, Table 3.2-2, Table 3.2-3, to reflect implementation of the Westinghouse 3.3.3.2.2, 3.4.1, 3.4.1.1.2, 3.4.1.1.4, 3.4.1.2, 15 x 15 upgrade fuel design.

3.4.1.3, 3.4.2, 3.4.2.1, 3.4.2.2, 3.4.2.3, 3.4.3.1, 3.4.3.2, 3.4.3.3, 3.4.3.4, 3.4.3.5, 3.4.3.6 (new),

3.4 Refs, Table 3.4-1, 3.5, 3.5.2.1, 3.5.2.1.2, 3.5.2.1.3, 3.5.2.1.4, 3.5.2.1.5, 3.5.2.6.1, 3.5 Refs, Table 3.5-3, Figure 3.5-9, Figure 3.5-17 (new), Table 4.3-1, Table 4.3-2, 9.1.2.3.2.1, 9.1.3.6, 9.1 Refs, 14.1, 14.1 Refs, 14.2.1.1, 14.2.1.2, 14.2.2.1, 14.2.2.2, 14.2.4.1, 14.2.7.2, 14.2.7.3.2, 14.2.7.4, 14.2.8.1, 14.2.9.1.1, 14.2.9.1.2, 14.2.9.1.7, 14.2.9.2.1, 14.2.9.2.2.2, 14.2.10.2, 14.2.10.3, 14.2 Refs, 14.3.2.1, 14.3.2.3, 14.3.3.2.1, 14.3 Refs, 14.4.1.1, 14.4 Refs, 14.5.1.5, 14.5.1.6, 14.5.1.7, 14.5.2.4.2, 14.5.2.5, 14.5.2.6, 14.5.3.4.1, 14.5.3.4.2, Table 14.5-1, Table 14.5-2, Table 14.5-3, Table 14.5-5, Table 14.5-6, Table 14.5-7, Table 14.5-13, Table 14.5-17, Table 14.5-18 (new),

Figure 14.5-1, Figure 14.5-2, Figure 14.5-3, Figure 14.5-4, Figure 14.5-5, Figure 14.5-6, Figure 14.5-7, Figure 14.5-8, Figure 14.5-9, Figure 14.5-10, Figure 14.5-11, Figure 14.5-12, Figure 14.5-13, Figure 14.5-14, Figure 14.5-76, 15A.5, 15A.5.2.5, 15A.6 (new), 15A Refs, Table 15A-8 (new), Table 15A-9 (new)

[SPS-UCR-2009-023]

Revision 52Updated Online 09/30/20 SPS UFSAR 15 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4309/29/11 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.2.7, Figure 10.2-1, 10.3.1.1, 10.3.3.1, Updated descriptions and associated analyses 10.3 Refs, Figure 10.3-1, 14.2.13.1 (new), to reflect Unit 1 turbine retrofit.

14.2.13.2, 14.2.13.3, 14.2 Refs, Figure 14.2-81, Figure 14.2-82, Figure 14.2-83 (new), Figure 14.2-84 (new),

Figure 14.2-85 (new), Figure 14.2-86 (new),

Figure 14.2-87 (new)

[SPS-UCR-2009-012]

1.1.6, 3.5 Refs Discussion corrected to state that mid-grids

[SPS-UCR-2011-004] are made of ZIRLO and NOT Optimized ZIRLO.

Table 9.7-1 Updated pump data for Unit 1 containment

[SPS-UCR-2009-024] sump pump replacements.

Table 4.1-5, 9.1.2.1 Revised description of reactor coolant pump

[SPS-UCR-2010-012] seal leakoff to reflect Flowserve N-9000 seals.

8.2, 10.3.3.2, Table 10.3-4, Figure 10.3-11 Revised discussion on isolated phase bus duct

[SPS-UCR-2010-013] coolers to reflect Unit 1 upgrade.

9.10.4.12 Updated discussion to reflect addition of

[SPS-UCR-2011-002] reactor coolant pump stator cooler outlet trough oil collection assemblies.

Table 18-1 Updated license renewal commitment related

[SPS-UCR-2010-018] to alloy 82/182 weld material.

18.2.15, 18.5 Refs Updated license renewal commitment to

[SPS-UCR-2010-022] perform enhanced inspections of reactor vessel internals in accordance with EPRI MRP-227.

3.5.2.2 Reflects replacement of enhanced

[SPS-UCR-2010-025] performance control rod assemblies for Unit 1 cycle 24 operation.

9.10.4.8, 9.10 Refs, 9.13.3.1 Removed requirement to use 1-VS-F-58B

[SPS-UCR-2010-033] after an Appendix R fire to ventilate the charging pump cubicles.

Revision 52Updated Online 09/30/20 SPS UFSAR 16 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4309/29/11 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.1, 1.1.2, 1.1 Refs, 3.2.1, 3.3.3.2.2, 3.4.1.3, Reflects the Measurement Uncertainty Table 3.4-1, 4.1.7.1, 4.1.7.3, 4.1.7.4, 4.1 Refs, Recapture Power Uprate.

Table 4.1-2, Table 4.1-4, Table 4.1-5, Table 4.1-8, Table 4.1-14, Table 4.1-15, 4.2.5, 4.3.3.2, 4.3.4, 4.3 Refs, 5.3.1.1, 5.4.1.2, 5.4.3.1, 5.4.3.2.2, Table 5.4-1, Table 5.4-17, 6.2.1.1, 7.2.2.5, 7.3.2.6.1, 8.1, 9.1.2.2, 9.1.2.3.2.6, Table 9.1-4, Table 9.1-5, Table 9.1-6, Table 9.1-7, 9.4, 9.5, 9.9, 9.13.3.6, Figures 10.2-1 thru Figure 10.2-4, 10.3.1, 10.3.1.1, 10.3.1.2, 10.3.2, 10.3.3, 10.3.4, 10.3.5,10.3.5.2, 10.3.5.3, 10.3.9, Table 10.3-4, 11.2.5.1, Table 11.2-2, Table 11.2-3, 11.3.2.2, Table 11.3-3, Table 11A-1, 14.1, 14.1 Refs, 14.2.1.1, 14.2.1.2, 14.2.2, 14.2.2.1, 14.2.2.3, 14.2.4.1, 14.2.4.2, 14.2.4.3, 14.2.7.1, 14.2.7.2, 14.2.7.3.1, 14.2.7.3.2, 14.2.8, 14.2.8.1, 14.2.8.2, 14.2.8.3, 14.2.9.1, 14.2.9.1.1, 14.2.9.1.2, 14.2.9.1.6, 14.2.9.2.2.1, 14.2.9.2.2.2, 14.2.9.2.4.1, 14.2.9.2.4.3, 14.2.10.2, 14.2.10.3, 14.2.10.4.2, 14.2.10.5, 14.2.11.1, 14.2 Refs, Table 14.2-1, Table 14.2-2, Table 14.2-3, Table 14.2-4, Figure 14.2-1, Figure 14.2-2, Figure 14.2-3, Figure 14.2-4a, Figures 14.2-5 thru Figure 14.2-14, Figure 14.2-16, Figure 14.2-21, Figure 14.2-23, Figures 14.2-27 thru Figure 14.2-42, Figure 14.2-45, Figure 14.2-49, Figure 14.2-50, Figure 14.2-51, Figure 14.2-55, Figure 14.2-56, Figure 14.2-62, Figure 14.2-67,

[SPS-UCR-2009-022]

Revision 52Updated Online 09/30/20 SPS UFSAR 17 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4309/29/11 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Figure 14.2-68, 14.3.1.2, 14.3.1.3, 14.3.1.4.3, (continued) 14.3.1.4.4, 14.3.2.1, 14.3.2.3, 14.3.2.4.2, 14.3.2.4.4, 14.3.2.5, 14.3.3.1.2, 14.3.3.2.2, 14.3.3.2.2.5, Tables 14.3-4 thru 14.3-11, Table 14.3-13, Table 14.3-15, Table 14.3-16, Figures 14.3-1 thru 14.3-9, Figure 14.3-14, Figure 14.3-19, Figure 14.3-24, Figure 14.3-26, 14.4.1.3.1, 14.4.2.1, Table 14.4-6, 14.5.2.3, 14.5.5, Table 14.5-1, Table 14.5-13, Appendix 14A, Table 14A-1, Table 14A-2

[SPS-UCR-2009-022]

14.3.1.4.4, 14.3.2.4.4 Removed discussion of 20 gpd primary to

[SPS-UCR-2010-030] secondary leakage limit for Unit 1 B steam generator.

Table 9.7-1 Updated pump data for Unit 2 containment

[SPS-UCR-2010-034] sump pump replacements.

10.3.5.2, Figure 10.3-9 Update reflects installation of the ultrasonic

[SPS-UCR-2009-014] flowmeters in the feedwater lines.

10.3.1.2 Description of the feedwater flow distribution

[SPS-UCR-2010-020] removed to reflect new J-nozzle design, which provides even distribution.

Revision 4209/30/10 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

14.2.9.1.6, Figure 14.2-49, Figure 14.2-50, Loss of Reactor Coolant Flow Analysis Figure 14.2-55, Figure 14.2-56 updated to reflect the DNB transient for the

[SPS-UCR-2010-019] underfrequency and undervoltage events in the LOFA reanalysis.

Table of Contents, List of Tables, List of Table of Contents modified to include the Figures for following chapters: 9, 11, 14, & 15 Appendices Table of Content.

[SPS-UCR-2010-021]

Revision 52Updated Online 09/30/20 SPS UFSAR 18 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4209/30/10 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.10.1, 9.10.2.2.5, 9.10.4.19 Fire Protection discussions updated to include

[SPS-UCR-2009-027] the addition of the Turbine Deck Security Office.

15A.3.2, 15A Refs Modified references to reflect procedures

[SPS-UCR-2010-009] updated.

9.9.2 Modified the total flow for each intake

[SPS-UCR-2010-011] structure to be consistent with the circulating water pump flow rate.

7.7.2, 11.3.6 Removed discussion of the Main Control

[SPS-UCR-2010-003] Room Bottled Air System.

11.2.3.2 Final configuration reflects portions of the

[FS-2003-045] blowdown water treatment subsystem that are no longer used at the station.

9.10.2.1 Interim configuration reflects portions of the

[SPS-UCR-2010-002] Surry Fire Detection System that have been replaced.

11.2.3.2 Corrects FS 2003-045 to reflect portions of the

[SPS-UCR-2010-005] blowdown water treatment subsystem that is no longer in use.

2.1.5.2, 2.1 Refs Adds a new reference to Chapter 2.

[SPS-UCR-2010-006]

6.2.2.2.13, 6.3.1.2.5 Description of the containment strainer

[SPS-UCR-2009-003] assembly seals was updated to reflect installation of the U2 seal closure frames.

7.2.1.1, Table 7.5-2, 7.7.2, 9.10.4.17, 9.13.2, Discussion of the Main Control Room Bottled 9.13.3.6, 9.13.4.1, 9.13.4.2, Table 9.13-1, Air System was removed.

14.2.9.2.4.3, 14.3.1.4.4, 14.3.2.4.4, 14.4.1.2.1, 14.4.1.3.1, 14.5.5.2

[SPS-UCR-2009-026]

10.3.5.2 A discussion was added describing the use of

[SPS-UCR-2009-028] Carbohydrazide for startup of Unit 2 using Auxiliary Feedwater.

9.1, 9.1.2.6.23, Figure 9.1-1 Reflects installation of Zinc Injection System

[FS 2007-014] for Unit 1.

9.1, 9.1.2.6.23, Figure 9.1-1 Reflects final configuration of Zinc Injection

[FS 2008-023] System.

Revision 52Updated Online 09/30/20 SPS UFSAR 19 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4209/30/10 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

4.1.7.1, 4.1.7.3, Table 4.1-13 Clarifies the capsule locations were original

[SPS-UCR-2009-021] locations. Annotates Table to reflect relocation of Surry Unit 2 surveillance capsule U.

Table 9.7-1 Corrected the containment sump pump data to

[SPS-UCR-2009-025] reflect the current pumps.

18.3.5.6 Updated discussion on reactor coolant pump

[SPS-UCR-2009-011] and ASME code case N-481.

4.2.2.4, Table 4.1-5, 9.1.2.1 Revised description of reactor coolant pump

[SPS-UCR-2009-019] seal arrangement to reflect the Flowserve N-9000 seal.

14.5.2.1, 14.5.2.3, 14.5.2.4.1, 14.5.2.4.2, Revised to incorporate the reanalysis of the 14.5.2.5, 14.2.5.6, 14.5 Refs, Table 14.5-13, Westinghouse small break loss of coolant Table 14.5-14, Table 14.5-15, Table 14.5-16, accident (SBLOCA).

Table 14.5-17, Figure 14.5-15 through Figure 14.5-76

[SPS-UCR-2009-008]

Revision 4109/30/09 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Figure 10.2-1 (sh 2), 10.3.3.2 Reflects the Unit 2 main generator change in

[FS 2008-011] hydrogen pressure.

10.3.5.2, 10.3.5.3 Clarified description of AFW system

[FS 2007-020] alignments to ensure minimum AFW flow requirements are met for design basis accident with the RCS above 350 degrees for both Units.

KWI Removed key word index.

[SPS-UCR-2009-020]

8.3, Figure 8.3-1 Reflects the redirection of the 531 transmission

[SPS-UCR-2009-010] line to Suffolk substation.

14.3.1.4.4, 14.3.2.4.4 Reflects a 20 gpd leakage limit for Unit 1 B

[SPS-UCR-2009-013] steam generator for operating cycle 23.

6.2.2.2.13, 6.3.1.2.5 Added a description of Unit 1 seal closure

[FS 2008-024] frames installed over the containment sump strainer flexible metal seals.

Revision 52Updated Online 09/30/20 SPS UFSAR 20 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4109/30/09 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.4.3.5 Raised the upper pH limit of the charging pump

[SPS-UCR-2009-005] component cooling water system.

8.3, Figure 8.3-1, 8.5 Incorporates addition of Bus 7 and breakers in

[FS 2005-026] switchyard.

6.2.2.2.6, 6.2.4, 6.2.4.1.5, 6.2 Refs Added new section, Gas Accumulation in

[SPS-UCR-2009-004] ECCS Piping in response to Generic Letter 2008-01.

14.5.1.7, Table 14.5-5, Table 14.5-6 Incorporates increase of carbon steel surface

[SPS-UCR-2009-006] area in containment and the impact on the best estimate large break loss of coolant accident analysis.

9B.1.1, 9B.2.1, 9B.1 Refs, Table 9B.2-1 Updated the discussion on heavy loads to

[FS 2008-021] include reliance on a RV head drop analysis and revised the weight of the U1 RV head and lifting device.

5.4.2.1.7, Table 5.4-12, Table 5.4-13, Implements changes to the Surry containment Table 5.4-17, 6.1, 6.2.3.11, 6.3.1.3.2 analysis using revised IRS/ORS pump

[SPS-UCR-2009-002] flowrates.

9.4.3.3 Removed description of Chilled Water

[FS 2007-028] circulating pump low suction pressure trip.

5.4.2.1.7, Table 5.4-12, Table 5.4-13, Incorporates increasing the SW inlet (river Table 5.4-17, Figure 5.4-3, Figure 5.4-4, water) temperature to 100 degrees in Figure 5.4-5, 6.3.1.4.3, 9.4.1.1, 9.4.3.3, 9.9.1 accordance with Technical Specification

[FS 2008-017] change request 397.

14.5.1.6, 14.5.1.7, Table 14.5-1, Table 14.5-2, Incorporated the results of a reanalysis of the Table 14.5-3, Table 14.5-4, Table 14.5-5, Westinghouse Best-Estimate Large Break Loss Table 14.5-6, Figure 14.5-1, Figure 14.5-2, of Coolant Accident (BE-LOCA) analysis Figure 14.5-3, Figure 14.5-4, Figure 14.5-5, using the Automated Statistical Treatment of Figure 14.5-6, Figure 14.5-7, Figure 14.5-8, Uncertainty Method (ASTRUM).

Figure 14.5-9, Figure 14.5-10, Figure 14.5-11, Figure 14.5-12, Figure 14.5-13, Figure 14.5-14

[FS 2008-022]

18.5 Refs Editorial - Updated UFSAR references to

[FS 2008-025] reflect current revisions for the steam generator management program.

Revision 52Updated Online 09/30/20 SPS UFSAR 21 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4109/30/09 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

6.2.2.1.3, 6.2.2.2.13, 6.2.3.11.1, 6.2.3.3, Updated various sections to reflect compliance 6.2.4.1.4, 6.2 Refs, Table 6.2-3, 6.3.1.2.5, with GSI-191 for the strainer assembly.

6.3.1.3.1, 6.3.1.3.2, 6.3.1.3.3, 6.3.1.3.4, 6.3.1.4.1, 6.3.1.4.3, 6.3.1.4.4, 6.3 Refs Table 6.3-3

[FS 2007-011]

Table 4.1-1 Revised Low-Pressure trip setpoint to be

[FS 2008-013] consistent with TSCR 318.

3.5 Refs, 14.4 Refs Updated reference placeholders with standard

[FS 2008-020] reference information.

18.2.11, Table 18-1 Updated to reflect license renewal

[FS 2008-018] commitments that have been completed.

12.3, 12.3 Refs, KWI Added NEI 99-01 as a reference.

[FS 2008-019]

Revision 4009/30/08 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

2.1.5.2, Table 2.1-4 Adds limitation on dimethylamine to chemical

[FS 2007-022] section.

9.10.2.2.7 Modifies description on the actuation of the

[FS 2008-008] Low Pressure CO2 Fire Protection System dampers.

9.10.4.8, 9.10 Refs Reflects that forced ventilation of the charging

[FS 2008-009] pump cubicles is not required after an Appendix R fire.

8.3, Figure 8.3-1, 8.5 Reflects changes associated with partial

[FS 2008-014] implementation of modification to 34.5 kV switchyard buses 5 and 7.

8.4.1 Incorporates the disconnect of the auto start

[FS 2007-019] circuitry for the high pressure heater drain pumps.

6.3.1.3 Reflects the installation of the entire sump

[FS 2008-006] strainer for Unit 2.

Revision 52Updated Online 09/30/20 SPS UFSAR 22 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4009/30/08 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

8.4.6 Incorporates changes associated with partial

[FS 2008-012] implementation of the modification of D transfer bus breaker to supply power to the TSC MCC and TSC UPS from the ACC diesel generator.

Table 9.4-1, Table 9.4-8 Corrected component cooling water pump

[FS 2008-007] design parameters.

5.4.1.2, 5.4.1.3.3, 5.4.1.3.5.4, 5.4.1.4, 5.4.2.1.6, Incorporates the containment response using 5.4.3, 5.4 Refs, Table 5.4-1, Table 5.4-2, new mass and energy data tables. Updates the Table 5.4-3, Table 5.4-4, Table 5.4-5, minimum NPSH valves.

Table 5.4-6, Table 5.4-7, Table 5.4-8, Table 5.4-9, Table 5.4-13, Table 5.4-14, Table 5.4-15, Figure 5.4-1, Figure 5.4-2, Table 6.2-12, Table 6.2-13

[FS 2008-003]

10.3.5.3 Updated the total accuracy value for the

[FS 2007-024] auxiliary feed flow loop.

10.3.5.2, 10.3.5.3 Incorporated changes associated with the

[FS 2008-001] modification of the operator selector switches for the AFW discharge MOVs.

9.10.4.23 Corrected the value of the concrete wall

[FS 2008-004] thickness separating the two fuel oil pump houses.

6.3.1.3, 11.3.2.1, Table 11.3-2, Figure 11.3-2 Modifies text associated with Incore Sump

[FS 2006-024] Room Drain Modifications.

3.5.2.6.1, 3.5 Refs, 14.4.1.1, 14.4 Refs Modifies lead rod average burnup limit for

[FS 2006-033] Surry fuel.

Figure 6.1-1, 6.2, 6.2.2.2.13, 6.2.3.11.3, Modifies text to reflect changes associated with Table 6.2-3,Table 6.2-13, 6.3, 6.3.1.2.5, 6.3.1.3, Containment Sump Strainer Design.

6.3.1.4, Table 6.3-1, Table 6.3-3, Figure 6.3-2, Figure 6.3-5

[FS 2007-025]

Revision 52Updated Online 09/30/20 SPS UFSAR 23 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4009/30/08 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.1.8, 1.4.49, 5.3.4.1, 5.3.4.3, 5.3 Refs, Performed containment analyses and LOCA Table 5.3-5, 5.4, 5.4.1.1, 5.4.1.3.1, 5.4.1.3.2, alternate source term analyses to support GSI 5.4.1.3.3, 5.4.1.3.4, 5.4.1.3.5.2, 5.4.1.3.5.3, 191 modifications Unit 1.

5.4.1.3.5.4, 5.4.1.3.5.5, 5.4.1.3.6, 5.4.1.4, 5.4.2, 5.4.2.1, 5.4.2.1.1, 5.4.2.1.2, 5.4.2.1.3, 5.4.2.1.4, 5.4.1.2.5, 5.4.2.1.6, 5.4.2.1.7, 5.4 Refs, Tables 5.4-6, 5.4-7, 5.4-8, 5.4-9, 5.4-10, 5.4-11, 5.4-12, 5.4-13, 5.4-14, 5.4-15, 5.4-16, 5.4-17, 5.4-18, 5.4-19, 5.4-20, 5.4-21, 5.4-22, 5.4-23, 5.4-24, & 5.4-25, Figures 5.4-1, 5.4-2, 5.4-3, 5.4-4, 5.4-5, 5.4-6, 5.4-7, 5.4-8, 5.4-9, 5.4-10, 5.4-11, 5.4-12, & 5.4-13, 6.2.2.1.4, 6.2.3.11.1, 6.2 Refs, Tables 6.2-11, 6.2-12, & 6.2-13, Figures 6.2-3, 6.2-4, 6.2-5, 6.2-6, & 6.2-7, 6.3.1.3, 6.3.1.4, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-11, 6.3-12, 6.3-13, 6.3-14, 6.3-15, 6.3-16, & 6.3-17, 14.5.4, 14.5.5, 14.5.5.2, 14.5.5.3, 14.5 Refs, Tables 14.5-7, 14.5-8,

& 14.5-11, 14B.2.3.3.1, 14B.2.3.3.2.1, 15.5.1.2

[FS 2005-027]

7.6.2.1 Removed information that specifies which flux

[FS 2006-035] thimble locations are plugged.

6.3.1.3, 7.5.1.3, Figure 7.5-2, Figure 7.5-3 Modified the refueling water storage tank

[FS 2007-002] engineered safety features actuation system to support GSI 191 containment sump modifications for Unit 1.

7.2, 7.2.1.8.6 Added replacement of the Westinghouse

[FS 2007-021] process modules with NUS Scientech modules.

1.1.8, 1.4.49, 14.5.4, 14.5.5, 14.5.5.2, 14.5.5.3, Editorial changes; clarifies final markups for Table 14.5-8, Table 14.5-9, Table 14.5-12, GSI-191 multiple packages.

15.5.1.2

[FS 2008-002]

5.4.2.1.6, 5.4 Refs Revised text to describe an alternate

[FS 2007-023] containment analysis method that can be used for the calculation of NPSHa for the recirculation spray pumps, and containment pressure and sump temperature response.

Revision 52Updated Online 09/30/20 SPS UFSAR 24 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 4009/30/08 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

14.5.1.1, 14.5.1.2, 14.5.1.3, 14.5.1.4, 14.5.1.5, Incorporated an analysis performed for 14.5.1.6, 14.5.1.7, 14.5.2.5, 14.5 Refs, LBLOCA using the Westinghouse Tables 14.5-1, 14.5-2, 14.5-3, 14.5-4, 14.5-5, Best-Estimate Large Break Loss of Coolant

& 14.5-6, Figures 14.5-1, 14.5-2, 14.5-3, Accident (BE-LBLOCA) analysis 14.5-4, 14.5-5, 14.5-6, 14.5-7, 14.5-8, 14.5-9, methodology using the Automated Statistical 14.5-10, 14.5-11, 14.5-12, 14.5-13, 14.5-14, Treatment of Uncertainty Method (ASTRUM).

14.5-15, 14.5-16, 14.5-17, 14.5-18, 14.5-19, Revised text for consistency and removed 14.5-20, 14.5-21, 14.5-22, 14.5-23, 14.5-24, unnecessary references.

14.5-25, 14.5-26, 14.5-27, 14.5-28, 14.5-29, 14.5-30, 14.5-31, 14.5-32, 14.5-33, 14.5-34, 14.5-35, 14.5-36, & 14.5-37

[FS 2006-021]

14.5.1.6, 14.5.1.7, 14.5.2.5, Table 14.5-6 Revised table to incorporate a penalty to PCT

[FS 2007-026] for the analysis performed for the LBLOCA analysis using the Westinghouse BE-LBLOCA analysis methodology using ASTRUM.

4.3.4.2 Clarified the description of the pressurizer

[FS 2007-013] PORV backup air supply.

14.5.2.5, 14.5.2.6, 14.5 Refs, Table 14.5-15 Updated peak cladding temperature for small

[FS 2007-009] break LOCA analysis for Westinghouse fuel.

14.5 Refs, Table 14.5-5 Updated peak cladding temperature for large

[FS 2007-010] break LOCA analysis for Westinghouse fuel.

9.1, 9.1.2.6.23, Figure 9.1-1 Installed the Unit 2 zinc injection system.

[FS 2007-018]

14.2.9.2.4.2, 14.2.9.2.4.3, 14.3.1.4.4, Revised the steam generator tube rupture and 14.3.2.4.2, 14.3.2.4.4, 14.3 Refs, Tables 14.3-9, main steam line break accident analyses to 14.3-10, & 14.3-15 reflect the change in the technical specification

[FS 2006-005 & FS 2006-020] allowable primary-to-secondary leakage rate.

[10 CFR 50.90 License Amendment]

18.2.11, 18.2.13, 18.2.15 Corrected the description of the Inservice

[FS 2007-017] Inspection Plan.

Revision 52Updated Online 09/30/20 SPS UFSAR 25 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3909/27/07 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 12.4 Reflected the audit and review functions

[FS 2007-016] contained in the Nuclear Facility Quality Assurance Program Description.

1.1.8, 1.4.49, 5.3.4.1, 5.3.4.3, 5.3 Refs, Performed containment analyses and LOCA Table 5.3-5, 5.4, 5.4.1.1, 5.4.1.3.1, 5.4.1.3.2, alternate source term analyses to support 5.4.1.3.3, 5.4.1.3.4, 5.4.1.3.5.2, 5.4.1.3.5.3, GSI 191 modifications Unit 2.

5.4.1.3.5.4, 5.4.1.3.5.5, 5.4.1.3.6, 5.4.1.4, 5.4.2, 5.4.2.1, 5.4.2.1.1, 5.4.2.1.2, 5.4.2.1.3, 5.4.2.1.4, 5.4.1.2.5, 5.4.2.1.6, 5.4.2.1.7, 5.4 Refs, Tables 5.4-6, 5.4-7, 5.4-8, 5.4-9, 5.4-10, 5.4-11, 5.4-12, 5.4-13, 5.4-14, 5.4-15, 5.4-16, 5.4-17, 5.4-18, 5.4-19, 5.4-20, 5.4-21, 5.4-22, 5.4-23, 5.4-24, & 5.4-25, Figures 5.4-1, 5.4-2, 5.4-3, 5.4-4, 5.4-5, 5.4-6, 5.4-7, 5.4-8, 5.4-9, 5.4-10, 5.4-11, 5.4-12, & 5.4-13, 6.2.2.1.4, 6.2.3.11.1, 6.2 Refs, Tables 6.2-11, 6.2-12, & 6.2-13, Figures 6.2-3, 6.2-4, 6.2-5, 6.2-6, & 6.2-7, 6.3.1.3, 6.3.1.4, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-11, 6.3-12, 6.3-13, 6.3-14, 6.3-15, 6.3-16, & 6.3-17, 14.5.4, 14.5.5, 14.5.5.2, 14.5.5.3, 14.5 Refs, Tables 14.5-7, 14.5-8,

& 14.5-11, 14B.2.3.3.1, 14B.2.3.3.2.1, 15.5.1.2

[FS 2007-027]

4.1.7.1, 4.1.7.3, 4.1.7.4, 4.1 Refs, Tables 4.1-14 Incorporated the revised RTPTS values

& 4.1-15, 4.2.5, 4.3.3.2, 4.3 Refs, Tables 4.3-3 provided for the Reactor Vessel Integrity

& 4.3-4 Program. [10 CFR 50.61]

[FS 2006-015]

4.3.4.2 Changed the description of the pressurizer

[FS 2006-022] PORV backup air supply.

Figure 6.1-2, 6.2.2.2.13, 6.2.3.11.3, Completed partial installation of Unit 2 Tables 6.2-3 & 6.2-12, 6.3.1.2.5, 6.3.1.3, containment sump strainers to support GSI 191 Tables 6.3-1 & 6.3-3, Figures 6.3-3 & 6.3-5 modifications.

[FS 2006-029]

6.3.1.3, 6.3.1.4, 11.3.2.1, Table 11.3-2, Added the Unit 2 incore sump room drain to Figure 11.3-3 support GSI 191 containment sump

[FS 2006-014] modifications.

Revision 52Updated Online 09/30/20 SPS UFSAR 26 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3909/27/07 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

6.3.1.3, Figure 6.3-17, 7.5.1.3, 7.5.2.1, Modified the Unit 2 refueling water storage Figures 7.5-2 & 7.5-3 tank engineered safety features actuation

[FS 2006-007] system to support GSI 191 containment sump modifications.

Figures 6.3-2 & 6.3-3 Modified the Unit 2 outside recirculation spray

[FS 2006-012] pumps test loops.

7.3.2.4 Revised the description of pressurizer pressure

[FS 2007-001] control.

7.7.1, 7.9.1, 7.9.3, 8.2, 8.4.4, Figure 8.4-1, Replaced the intake structure supervisory 9.10.2.1. system in the low level intake structure and in

[FS 2005-015] the main control room.

7.7.2, 7.11.2, 8.4.3 Updated the description of the power supply

[FS 2005-009] for the remote monitoring panels.

9.1.2.1, 9.1.3.5.3, 9.6.3.1, 9.6.3.2, 9.10.3.3, Replaced operable terminology with 9C.2, 10.3.1.5, 11.3.4.2, 11.3.4.3, 11.3.4.4 functional terminology in accordance with

[FS 2007-004] Regulatory Issue Summary 2005-20.

Table 9.7-1 Updated the description of the component

[FS 2006-034] cooling heat exchanger pit sump pump shaft material.

9.10.4.18 Provided additional fire hazard analysis

[FS 2007-005] discussion in order to address Mechanical Equipment Room No. 4.

9.12.9, 9.12.9.1, 9.12.9.2, 9.12.9.3, 19.2 Refs, Revised the description of handling ISFSI cask 9B.1.5 systems.

[FS 2007-003]

9.14.2, Table 9.14-1 Added the dry shielded canister drain and

[FS 2005-024] reflood pumps.

Table 9.14-1 Replaced the spent fuel storage cask vacuum

[FS 2004-017] pumps.

10.3.1.1, 14.2.13 Modified the turbine overspeed protection

[FS 2006-032] control permissive logic and circuitry.

10.3.5.2, 10.3.5.3 Defeated the auto-open function for auxiliary

[FS 2006-030] feedwater flow isolation motor-operated valves.

Figure 10.3-10 Replaced chemical feed system pumps.

[FS 2005-025]

Revision 52Updated Online 09/30/20 SPS UFSAR 27 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3909/27/07 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

11.2.6.2, 11.3.3, 11.3.3.1, 11.3.3.2, 11.3.3.13, Replaced ventilation system radiation 11.3.3.14, Tables 11.3-5, 11.3-6, & 11.3-8 monitors.

[FS 2005-012]

14.2.11.1, 14.2.11.1.1, 14.2.12, Revised the analysis description of auxiliary Figures 14.2-73, 14.2-74, 14.2-75, & 14.2-76 feedwater flow following loss of normal

[FS 2006-031] feedwater and loss of AC power events.

18.1.4, 18.2.6, 18.2.13, 18.2.19, Table 18-1 Reflected the completion of License Renewal

[FS 2006-025] Commitment Item Nos. 4, 12, 18, 26, and 27.

18.3.2.4, Table 18-1 Reflected the completion of License Renewal

[FS 2007-008] Commitment Item No. 24.

Revision 3809/29/06 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

2.1.2.1 Revised the Exclusion Area Boundary to be the

[FS 2006-023] site boundary. [10 CFR 50.90]

2.2.1.2 Clarified the description of the applicability of

[FS 2004-016] Regulatory Guide 1.23 to meteorological equipment.

3.1, 3.1 Refs, 3.3.1, 3.3.2.3, 3.3.2.13, 3.3.3.2.2, Incorporated the use of integral fuel burnable 3.5.2.1.5, 3.5.2.5, 3.5.2.6.3, 3.5.2.6.4, absorber (IFBA) rods.

Table 3.5-3, Figure 3.5-15, 3.6.3.13

[FS 2006-006]

Figures 6.3-2 & 6.3-3 Modified the Unit 1 outside recirculation spray

[FS 2006-004] pumps test loops.

7.6.2.1 Isolated the flux thimble tube at location

[FS 2006-017] 1-RC-TW-J3.

8.5 Modified the #1 and #3 emergency diesel

[FS 2004-023] generators auto start circuits.

8.5 Aligned the description of engineered

[FS 2006-009] safeguards equipment powered by each emergency bus with the list contained in Technical Specification 3.16 Basis.

9.8 Corrected the description of the containment

[FS 2006-016] instrument air compressors capacity.

Revision 52Updated Online 09/30/20 SPS UFSAR 28 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3809/29/06 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9C.1.2 Augmented the description of the water level

[FS 2005-013] monitoring system to include the Amertap pit monitors and a description of the system power supply.

10.3.1.1 Clarified the description of the turbine-driven

[FS 2005-008] auxiliary feedwater pump design and operating conditions.

10.3.3.2 Added the new Unit 1 generator and exciter

[FS 2005-022] ratings and revised the cooling water flow value for the Unit 1 generator hydrogen coolers.

10.3.5.4 Revised the description of auxiliary feedwater

[FS 2006-010] pump surveillance test and inspections.

[10 CFR 50.90]

11.2.3.1.7, 11.2.4.1.1, 11.2.4.1.5, 11.2.4.2.2 Corrected the description of Radwaste Facility

[FS 2005-016] reducing and processing functions.

14.3.3.2.1, 14.3.3.2.3.1, 14.3.3.2.3.2, Reanalyzed the control rod assembly ejection 14.3.3.2.3.3, 14.3.3.2.3.4, 14.3 Refs, accident in support of the transition to Integral Table 14.3-6, Figures 14.3-24, 14.3-25, Fuel Burnable Poison (IFBA) fuel.

14.3-26, and 14.3-27

[FS 2006-001]

14.5.1.6, 14.5.2.5, 14.5.2.6, 14.5 Refs, Incorporated the peak clad temperature Tables 14.5-5 & 14.5-15 penalties and benefits for the large break and

[FS 2006-003] small break LOCA associated with implementation of IFBA fuel. [10 CFR 50.46]

14.5 Refs, Table 14.5-5 Incorporated the peak clad temperature

[FS 2005-007] penalties and benefits for the large break LOCA. [10 CFR 50.46]

14.5 Refs, Table 14.5-5 Incorporated the peak clad temperature

[FS 2006-002] penalties and benefits for the large break LOCA. [10 CFR 50.46]

Revision 52Updated Online 09/30/20 SPS UFSAR 29 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3809/29/06 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Chapter 17 (all) Replaced Chapter 17 in its entirety with a brief

[QA 2004-002] description of and reference to the recently implemented Topical Report DOM-QA-1. The Dominion Nuclear Facility Quality Assurance Program Description is based on ANSI/ASME NQA-1-1994 and will be maintained as a separate, single document for Dominion facilities.

[10 CFR 50.54(a)]

18.2.12 Removed the ASME XI edition and addenda

[FS 2005-023] reference for containment inservice inspection to allow periodic update as required by regulation.

Revision 3709/30/05 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.1, 1.4.41, 2.1.3.5, 4.3.5, 5.1, 6.2.1.1, Corrected citations to regulation and regulatory 6.2.2.1.3, 7.2.1.8.3, 14.1, 15.2.1 guide dose limits for design basis accident

[FS 2004-031] analysis.

3.6.3.2 Indicated that ultrasonic or x-ray testing is no

[FS 2004-029] longer performed for burnable poison rods beginning with Cycle 20.

4.2.2.2, 4.2.6 Updated the estimated pressurizer heatup rate

[FS 2004-018] during startup for a reduced heater capacity of 1200 kW.

4.2.7.2, 7.5.2.2, 7.5.3.5, 7.6.2.2, 7.9.2 Replaced the emergency response facilities

[FS 2004-027] computer system.

4.3.3.1, 4.3 Refs Extended the inspection interval for reactor

[FS 2004-026] coolant pump flywheels from 10 to 20 years.

[10 CFR 50.90]

Tables 4.3-2 & 4.3-4 Revised the stress intensity value for the Unit 2

[FS 2004-028] reactor vessel flange.

4.4.1.7, 6.2.2.2.4, 6.2.2.2.10, 6.2.4, 6.3.1.5.1, Changed the ASME Code reference for 6.3.1.5.2, 9.3.4, 9.4.5 inservice testing activities from Section XI to a

[FS 2004-033] general reference to the ASME Code.

Revision 52Updated Online 09/30/20 SPS UFSAR 30 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3709/30/05 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Tables 5.2-1 & 5.2-2 Reflected the removal of valves 1-MS-118 and

[FS 2005-011] 2-MS-118 as part of the decay heat subsystem removal.

5.3.5, 5.3 Refs, 6.2.3.3, 6.2.3.12.1, 6.2 Refs, Reflected that the Hydrogen analyzers and Tables 6.2-14 & 6.2-15, Figures 6.2-3, 6.2-4, recombiners will continue to function and be 6.2-5, 6.2-6, 6.2-7, & 6.2-8 periodically tested, but are no longer part of the

[FS 2005-002] plant design basis or credited in accident analyses.

6.3.1.3, Figure 6.3-16 Changed the refueling water storage tank low

[FS 2004-021] level alarm setpoint from 16.0% to 20.0%.

7.2.2.1.1 Increased the design temperature limit for

[FS 2000-006] power cable from 85°C to 90°C and described randomly spaced power cable having less than 1/4 diameter spacing.

7.2.3.2.7, Figure 8.4-1, 10.3.5.3 Changed electrical power feeds associated with

[FS 2003-030] replacement of the plant computer and the emergency response facilities computer system.

8.2 Provided clarification of the operating

[FS 2003-060] conditions and analysis required for electrical equipment and cables.

8.3, Figure 8.3-1 Installed redundant, underground feeder cables

[FS 2004-006] to the low level intake structure buses.

8.5 Corrected the description of the loads served by

[FS 2003-037] the emergency diesel generators.

[10 CFR 50.90]

8.5 Clarified that three low head safety injection

[FS 2004-025] pump motors are analyzed to start at 72% of rated voltage.

8.5 Modified the #2 emergency diesel generator

[FS 2005-018] auto start circuit.

Table 9.4-2 Corrected the description of the capacity of the

[FS 2005-019] chilled water system chillers.

9.13.3.6, 9.13.4.2 Revised the description of the main control

[FS 2004-022] room and emergency switchgear and relay room ventilation system to rely on operating either one or two chillers.

Revision 52Updated Online 09/30/20 SPS UFSAR 31 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3709/30/05 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9B.2.3, 9B.2.4.7, 9B.2 Refs, Table 9B.2-1 Replaced the 6-ton Auxiliary Building hoist

[FS 2004-038] with a 5-ton hoist.

10.3.5.2, Figure 10.3-9 Replaced Unit 2 auxiliary feedwater system

[FS 2004-003] isolation valves with stop-check valves.

10.3.5.2, Figure 10.3-9 Replaced Unit 1 auxiliary feedwater system

[FS 2004-015] isolation valves with stop-check valves.

Table 10.3-4 Revised the cooling water flow value for the

[FS 2004-004] Unit 2 generator hydrogen coolers.

Figure 10.3-11 Corrected tie-in locations between Sheets 1 & 2

[FS 2004-036] describing the bearing cooling system.

Tables 11.3-5 & 11.3-7 Reflected consistent mark number format for

[FS 2005-017] the radiation monitoring system.

14.2 Refs, 14.3 Refs, 14B Refs Updated the references to the RETRAN

[FS 2004-030] Topical Report.

14.3.1.4.4, 14.3.2.4.2, Table 14.3-7, 14.3-8, Corrected and clarified the description of the 14.3-9, 14.3-10, 14.3-12, & 14.3-15 dose consequences of the main steam line

[FS 2005-010] break, locked rotor accident, and steam generator tube rupture based on the alternative source term methodology.

Table 14.3-8 Incorporated an editorial correction of the

[FS 2005-021] event time ranges.

14.5.1.6, 14.5 Refs, Table 14.5-5 Incorporated the peak clad temperature

[FS 2005-001] penalties and benefits for the large break LOCA. [10 CFR 50.46]

Figure 15.1-1 Provided the location of well-water supply

[FS 2004-032] system Well E and removed the incorrectly identified information center.

Figure 15.1-2 Added delay fencing in the Protected Area.

[FS 2004-010]

Figure 15.1-2 Added sally port fencing in the Protected Area.

[FS 2004-012]

15.6.2.1 Incorporated an editorial correction replacing

[FS 2005-004] stem generator with steam generator.

15.7, 15.7 Refs Clarified the scope of statistical information

[FS 2004-034] regarding the evaluation of masonry block walls in response to IE Bulletin 80-11.

Revision 52Updated Online 09/30/20 SPS UFSAR 32 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3709/30/05 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

18.1.1, 18.1.4, 18.2.1, 18.2.9, 18.2.19, Reflected the completion of License Renewal Table 18-1 Commitment Item Nos. 1, 2, 3, 7, 8, 19, and 29.

[FS 2004-037]

Revision 3609/30/04 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI Updated the Key Word Index to incorporate an

[FS 2004-002] editorial correction.

3.3.3.2.1, 3.3 Refs, 3.5 Refs Updated references to the topical report for

[FS 2003-035] reload design methodology. [10 CFR 50.90 License Amendment]

3.5.3.1, 3.5.3.1.6, 4.1.2.8, 4.1.6, 4.1 Refs, Replaced the Unit 2 reactor vessel closure Tables 4.1-2, 4.1-8, & 4.1-15, 4.2.2.1, head.

Table 4.2-1, 4.3.1.1, Tables 4.3-2, 4.3-4, 4.4-1,

& 9B.2-1, 14.3.3.1.1.1, 14.5.3, 14.5.3.3.4, 14.5 Refs, 15.2 Refs, Table 15.2-2

[FS 2003-040 & FS 2003-052]

Table 4.1-2 Identified the replacement reactor vessel heads

[FS 2003-051] dome insulation thickness.

4.2.2.1, 5.3.1.3.2, 9.12.5.2, 9.12.5.4, 9B.2.5, Upgraded the Unit 2 reactor head assembly.

Table 9B.2-1, Table 11.3-2, Figures 11.3-2

& 11.3-3, 14.3.3.1.1.4.2, 15.5.1.1, 15.5.1.8, 15.5.1.11.1, 15A.3.5.2, 15A.3.5.2.4, 15A Refs

[FS 2003-048]

4.2.7.2 Completed the installation of the Unit 2 N-16

[FS 2003-042] primary-to-secondary leakage detection system.

4.3.1.1, Table 4.3-1 & 4.3-2 Provided a text description of cumulative usage

[FS 2004-008] factors for reactor vessel components in lieu of a tabular format. Updated stresses for reactor vessel components.

Table 5.3-2, 9.4.1.3, 9.4.3.3, Table 9.4-2, Updated the description of the Unit 2 chilled Figure 9.9-1, Table 10.3-4, Figure 10.3-11 water system to reflect equipment replacement

[FS 99-065] and changing the systems source of cooling water.

Revision 52Updated Online 09/30/20 SPS UFSAR 33 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3609/30/04 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

5.5.3, 7.2.3.2.7, 7.3.2.3.2, 7.4.2.4, 7.4.3.2, Replaced the Unit 2 plant computer.

7.4.3.6, Tables 7.4-1, 7.4-2, & 7.4-3, 7.6.2.2, 7.7.2, Figure 7.7-1, 7.9.2, 7.9.2.2, 7.9.2.3, 7.9.2.5, 7.9.2.6, 7.9.3, 7.9.4, 9.10.4.1

[FS 2003-059]

6.2.2.2.4 Replaced the Unit 2 charging pump discharge

[FS 2003-053] alternate header isolation valve, 2-CH-MOV-2287C.

7.2.1.2, 7.3.2.3.2, 14.2.4 Replaced the Unit 2 benchboard individual rod

[FS 2003-023] position indicators and the rod bottom lights with redundant flat panel displays.

7.5.2.2, 7.5.3.5, 7.6.2.2, 7.7.2, Figure 7.7-1, Replaced the Unit 1 plant computer.

7.9.2, 7.9.2.2, 7.9.2.5, 7.9.3

[FS 2002-019]

7.6.2.1 Clarified the description of the Unit 2 incore

[FS 2003-049] instrumentation system.

8.5 Added provisions for inspection and repair of a

[FS 2001-037] buried fuel oil storage tank during plant operation. [10 CFR 50.90 License Amendment]

9.4.1.1 Added the vacuum priming system to the

[FS 2004-014] description of the component cooling heat exchangers.

9.4.1.3 Clarified the description of the chilled water

[FS 2003-064] used to cool the water in the refueling water storage tank.

9.4.1.3, Table 9.4-2 Updated the Unit 1 chilled water system

[FS 2003-050] capacity.

Table 9.6-1, 11.2.3.1.5, Table 11.2-1 Designated the waste disposal evaporator test

[FS 2003-058] tanks as installed but no longer used.

9.10.4.7 Removed the steam heating coils from the

[FS 2004-011] motor control center rooms ventilation units.

9.12.4.14, 9B.2.4.6, 9B.2.4.7, Table 9B.2-1 Uprated the Unit 2 polar crane capacity for

[FS 2003-011] each of the two hooks from 125 to 140 tons.

Figure 10.2-1, 10.3.3.2, Table 10.3-4 Replaced the Unit 2 main generator with an

[FS 2003-012] upgraded, refurbished generator.

Revision 52Updated Online 09/30/20 SPS UFSAR 34 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3609/30/04 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

10.3.1.2 Restored the automatic control mode for the

[FS 2003-039] Unit 2 steam header pressure controller.

10.3.3.2, Table 10.3-4 Replaced the Unit 2 main generator exciter.

[FS 2003-009]

10.3.5.1 Increased the Unit 2 feedwater recirculation

[FS 2003-041] flow from 2800 to 4300 gpm.

10.3.5.2, Figure 10.3-9 Modified the Unit 2 feedwater bypass

[FS 2003-038] regulating valve line to provide bypass flow indication during unit startup.

10.3.5.3 Incorporated editorial correction of punctuation

[FS 2003-054] errors.

11.2.4.1.6 Added the low-level waste storage facility and

[FS 2003-029] sea van storage pad to the description of the solid waste disposal system.

14.2.9.2.2.2, 14.2.9.2.3, 14.2.9.2.4.1, Reflected the reanalyzed dose consequences of 14.2.9.2.4.2, 14.2.9.2.4.3, 14.2.9.2.4.4, a locked rotor accident using alternate source 14.2 Refs, Tables 14.2-2, 14.2-4, & 14.3-14 term and methodologies described in

[FS 2003-044] Regulatory Guide 1.183.

14.2.10.3, 14.2.10.4.2, Figures 14.2-68, Updated the reanalyzed information and figures 14.2-69, 14.2-70, 14.2-71, & 14.2-72 for loss of external electrical load/turbine trip.

[FS 2004-007]

14.3.1.4, 14.3.1.4.1, 14.3.1.4.2, 14.3.1.4.3, Incorporated the reanalysis of the dose 14.3.1.4.4, 14.3.1.4.5, 14.3.2.4, 14.3.2.4.2, consequences of the steam generator tube 14.3.2.4.3, 14.3.2.4.4, 14.3.2.4.5, 14.3 Refs, rupture and main steam line break using the Tables 14.3-9, 14.3-10, 14.3-11, 14.3-12, alternative source term methodology.

14.3-14, & 14.3-16

[FS 2003-057]

14.4.1.2.1, 14.4.1.2.2, 14.4.1.3.1, 14.4.1.3.2, Incorporated the reanalysis of the dose 14.4 Refs, Table 14.4-5 consequences of a fuel handling accident using

[FS 2003-055] the alternative source term methodology.

14.5.2.4.2, 14.5.2.5 Made editorial corrections to correctly refer to

[FS 2004-024] Tables 14.5-15 & 14.5-16.

14.5.2.6, 14.5 Refs, Table 14.5-16 Incorporated a change to the summary of peak

[FS 2004-019] clad temperature penalties and benefits for the small break LOCA. [10 CFR 50.46]

Revision 52Updated Online 09/30/20 SPS UFSAR 35 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3609/30/04 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

14.5.5.2, 14.5.5.3, 14.5 Refs, Table 14.5-12 Revised the discussion of dose consequences of

[FS 2003-061] the loss of coolant accident using 500 cfm instead of 10 cfm for the control room in-leakage and out-leakage parameters.

15.5.2, 15.5.2.1, 15.5.2.3, 15 Refs Completed the restoration of construction

[FS 2003-031] opening in the containment structure for the Unit 2 reactor pressure vessel head replacement.

17.2.1.2.D.3.c, Figure 17.2.1-3 Deleted the Manager Nuclear Engineerings

[QA 2004-004] responsibility for development of Improved Technical Specifications. Updated the title of and line of reporting for Supervisor Nuclear Records. [10 CFR 50.54(a)(3)]

17.2.2.8 Updated terminology to the current naming

[QA 2004-005] convention for inservice inspection personnel.

[10 CFR 50.54(a)(3)]

17.2.10 Updated the description of qualification

[QA 2003-001] requirements for personnel performing non-destructive examinations.

[10 CFR 50.54(a)(3)]

18.2.3 Established acceptance criteria for borated

[FS 2004-001] water leakage.

18.2.6, 18.2.10, Table 18-1 Described completion of commitments

[FS 2004-005] regarding inspection of inaccessible areas, groundwater monitoring, and internal inspections of containment polar crane girders.

18.2.19, Table 18-1 Described completion of commitments

[FS 2004-009] regarding procedures to assure consistent inspection of components for aging effects during work activities.

18.3.2.4, 18.5 Refs, Table 18-1 Completed detailed engineering evaluation for

[FS 2003-062] the potential effect of environmentally-assisted fatigue in safety injection accumulator nozzles and charging line nozzles.

Revision 52Updated Online 09/30/20 SPS UFSAR 36 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3509/30/03 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.1, 1.6.2.3, 2.1.3.1, 3.1, 4.1, 4.1.4, 4.1.5, Reflected the increased operating life basis Tables 4.1-8, 4.1-12, & 4.1-13, 4.3.1.1, 4.3.1.2, from 40 to 60 years and added Chapter 18 Tables 4.3-3 & 4.3-4, 5.0, 6.1, 6.3.1.2.1, 7.1, [10 CFR 54.21] to describe the programs and 7.5.3.5, 8.0, 9.0, Table 9.1-3, 10.1, 11.1, activities that manage the effects of aging 11.3.2.9.1, 15.5.1.8, 18.0, 18.1, 18.1.1, 18.1.2, materials during the extended operation period 18.1.3, 18.1.4, 18.2, 18.2.1, 18.2.2, 18.2.3, associated with license renewal.

18.2.4, 18.2.5, 18.2.6, 18.2.7, 18.2.8, 18.2.9, 18.2.10, 18.2.11, 18.2.12, 18.2.13, 18.2.14, 18.2.15, 18.2.16, 18.2.17, 18.2.18, 18.2.19, 18.2.20, 18.3, 18.3.1, 18.3.1.1, 18.3.1.2, 18.3.1.3, 18.3.2, 18.3.2.1, 18.3.2.2, 18.3.2.3, 18.3.2.4, 18.3.3, 18.3.4, 18.3.5, 18.3.5.1, 18.3.5.2, 18.3.5.3, 18.3.5.4, 18.3.5.5, 18.3.5.6, 18.3.6, 18.4, 18.4.1, 18.4.2, 18.5, Table 18-1

[FS 2002-016]

Table 2.1-4, Figure 15.1-2 Installed a tank farm and feed system for

[FS 99-064] treating the circulating water system with sodium bromide and sodium hypochlorite.

2.2.1.2, 3.3.2.13, 6.2.2.1.2, 7.4.3.3.3, 7.4.3.5.2, Replaced paper strip chart recorders in the 7.4.3.7.2, 7.4.3.7.4, 7.4.3.7.5, 11.3.3, 11.3.4.1, control room with video display recorders.

11.3.4.5

[FS 2001-044]

3.5.2.6.1, 3.5 Refs Identified the references for the design

[FS 2002-034] requirements for fuel assembly structural components.

3.5.3.1, 4.1.2.8, 4.1.6, 4.1 Refs, Tables 4.1-2, Replaced the Unit 1 reactor vessel closure 4.1-9, & 4.1-14, 4.2.2.1, 4.2.5, 4.2 Refs, head.

Table 4.2-1, 4.3.1.1, Tables 4.3-1, 4.3-2, 4.3-3,

& 4.3-4, 4.4.1.3, Table 4.4-1, 15A.5.2, 15A.5.2.1, 15.A.5.2.2, 15A.5.2.3, 15A.5.2.4, 15A.5.2.5, 15A Refs

[FS 2003-018 & FS 2003-026]

4.1 Refs, Table 4.1-14 Reflected a new reference nil ductility

[FS 2003-001] transition temperature for the Unit 1 reactor vessel closure head dome.

[10 CFR 50.55a(a)(3)(ii) and 10 CFR 50.55a(g)(6)(i) Relief Requests]

Revision 52Updated Online 09/30/20 SPS UFSAR 37 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3509/30/03 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 4.1-1, 7.5.1.4.1, 7.5.1.4.2 Changed the reactor coolant system

[FS 2001-022] low-pressure alarm from 2205 to 2210 psig.

4.2.2.1, Figures 4.2-2 & 4.2-3, 9B.2.4.4, Modified the service structure, cooling air 9B.2 Refs, Table 9B.2-1 shroud and shroud support, radiation shield,

[FS 2003-019] insulation, and intermediate lift ring for the Unit 1 reactor vessel head replacement.

4.2.2.1, 4.3.1.1, Table 4.3-1 Enhanced the description of repairs performed

[FS 2002-031] on the Unit 1 reactor vessel head and control rod drive mechanism nozzles.

4.2.2.6 Clarified the description of flanges used in the

[FS 2002-029] reactor coolant system.

4.2.7.2 Installed the Unit 1 N-16 primary-to-secondary

[FS 2001-035] leakage detection system.

4.2.7.2 Installed the initial phase of the Unit 2 N-16

[FS 2003-043] primary-to-secondary leakage detection system.

4.2 Refs, Table 4.3-3 & 4.3-4 Corrected typographical errors.

[FS 2003-014]

4.3.3.2, 4.3 Refs, Table 4.3-4 Reflected the revised RTPTS values provided

[FS 2003-007] for the Unit 2 Reactor Vessel Integrity Program.

Table 6.2-5 Replaced charging pump 1-CH-P-1B.

[FS 2002-028]

6.3.1.5.1, 6.3.1.5.2 Revised the frequency of inspection for the

[FS 2002-002] containment spray and recirculation spray nozzles. [10 CFR 50.90 License Amendment]

Figure 6.3-1 Removed the vent caps from the refueling

[FS 2000-021] water storage tanks.

7.2.1.2, 7.3.2.3.2, 14.2.4 Replaced the Unit 1 benchboard individual rod

[FS 2003-005] position indicators and the rod bottom lights with redundant flat panel displays.

7.2.2.1.6 Removed the reactor protection system logic

[FS 99-062] channel testing event recorder.

7.2.2.5, Table 7.2-3, 7.8, 7.8.1, Figure 7.8-1 Removed the load frequency recorder and the

[FS 2002-022] automatic load control system.

Revision 52Updated Online 09/30/20 SPS UFSAR 38 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3509/30/03 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

7.2.3.2.7, 7.9.4, 8.4.4, 8.4.5, 8.4.6, Provided power feed changes in preparation for Figure 8.4-1, 9.10.2.7, 10.3.5.3 plant computer replacement, installed a portion

[FS 2002-017] of the new computer for parallel testing, and permitted use of engineering-approved cable.

7.6.2.1, 7.6.3 Clarified the description of the incore

[FS 2002-021] instrumentation system.

8.4.4 Installed an additional 125V dc switchboard

[FS 2003-003] crosstie circuit breaker.

8.5 Modified the #3 emergency diesel generator

[FS 2003-013] breaker closure circuit.

9.4.3.5 Restored the original configuration of the

[FS 2001-009] charging pump component cooling water system.

9.10.2.2.2 Changed the pressure of the firewater system.

[FS 2001-028]

9.12.4.14, 9B.2.4.6, 9B.2.4.7, 9B.2 Refs, Uprated the Unit 1 polar crane capacity for Table 9B.2-1 each of the two hooks from 125 to 140 tons.

[FS 2003-010]

9.12.5.3 Provided an alternate method for monitoring

[FS 2003-017] subcriticality during fuel onload.

9.13.3.6 Installed an alternate power feed to Mechanical

[FS 97-028] Equipment Room-5 for use in the event of a fire.

9.13.3.6, 9.13.4.1 Provided shutdown of fans serving areas

[FS 2000-019] adjacent to the main control room (MCR) due to a safety injection signal or manual actuation in the MCR.

10.3.1.2 Restored the automatic control mode for the

[FS 2003-028] Unit 1 steam header pressure controller.

10.3.1.2, 10.3.8, 11.2.3, 11.2.3.2, 11.2.3.2.1, Reflected partial implementation of 11.2.3.2.2, Tables 11.2-4, 11.2-5, 11.2-6, discontinued use of the steam generator

& 11.2-7, Figures 11.2-2 & 11.2-3, 11.3.2.6, blowdown treatment facility.

11A.4, Tables 11A-10 & 11A-12

[FS 2003-047]

10.3.4.1, 10.3.4.2 Increased the flow rate of the circulating water

[FS 98-045] pumps from 210,000 gpm to 220,000 gpm.

Revision 52Updated Online 09/30/20 SPS UFSAR 39 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3509/30/03 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

10.3.5.1 Increased the Unit 1 feedwater recirculation

[FS 2003-004] flow from 2800 to 4300 gpm.

10.3.5.2, Figure 10.3-9 Modified the Unit 1 feedwater bypass

[FS 2003-024] regulating valve line to provide bypass flow indication during unit startup.

10.3.9, 10.3.9.2, Figure 10.3-11 Added description of the bearing cooling

[FS 2001-003 & FS 2003-046] normal makeup water supply and treatment system.

Figure 10.3-7 Installed an additional cross-connect valve for

[FS 2001-030A] isolation of the Unit 1 auxiliary steam header.

Figure 10.3-11 Replaced turbine lube oil coolers temperature

[FS 2000-029] control valves with manual throttle valves.

Figure 10.3-11 Removed and capped dead-leg piping to the

[FS 2001-006] flash evaporators that are abandoned in place.

14.2.1.1, 14.2.1.2 Corrected the description of the reactor trip

[FS 2003-032] setpoint for the rod withdrawal from subcritical event.

14.4.1.2.1 Updated a cross-reference number.

[FS 2003-006]

14.5.3.2, 14.5 Refs Added text describing that it has been shown

[FS 2003-002] that the control rods will insert for cold leg breaks.

14.5 Refs, Table 14.5-5 Incorporated a change to the summary of peak

[FS 2003-027] clad temperature penalties and benefits for the large break LOCA. [10 CFR 50.46]

15.3.1, 15.3.2, 15.4, 15.4.1, 15.4.2, 15.4.3, Completed the restoration of construction 15.5.1.6, 15.5.1.8, 15.5.1.9, 15.5.1.9.1, opening in the containment structure for the 15.5.1.9.3, 15.5.1.9.4, 15.5.1.10, 15.5.2, Unit 1 reactor pressure vessel head 15.5.2.1, 15.5.2.2, 15.5.2.3, 15.5.2.4, 15.5.2.5, replacement.

15.5 Refs

[FS 2003-020 & FS 2003-025]

17.2.0.2, Table 17.2-0, 17.2.2.1, 17.2.2.5, Made editorial corrections to correctly refer to 17.2.2.6, 17.2.10, 17.2.17 Table 17.2-0.

[FS 2003-021]

Revision 52Updated Online 09/30/20 SPS UFSAR 40 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3509/30/03 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

17.2.1.1.A, 17.2.1.2.B, 17.2.1.2.B.1, Revised organizational titles of the Senior Vice 17.2.1.2.B.1.b.1.1, 17.2.1.2.C.1, 17.2.16.2.B.2, President Nuclear Operations, Shift Manager, 17.2.16.2.C, 17.2.1.16.2.D, Figures 17.2.1-1 and Unit Supervisor. [10 CFR 50.54(a)(3)]

& 17.2.1-2, Table 17.2-0, App C A.8.e, B.6.e, B.6.i, B.7.c, & B.8

[FS 2003-015]

17.2.1.2 Assigned responsibility for maintenance of

[FS 2003-008] plant equipment history to the Manager Nuclear Maintenance. [10 CFR 50.54(a)(3)]

17.2.1.2.A.2, Figure 17.2.1-1 Deleted the description of and reference to the

[FS 2002-006] Nuclear Oversight Board.

[10 CFR 50.54(a)(4)]

Table 17.2-0 Provided for the repair and testing of a

[FS 2002-033] temporary opening in the containment due to reactor vessel head replacement.

[10 CFR 50.54(a)(3)]

Revision 3409/03/02 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.1.8, 1.4.11, 1.4.47, 2.1.2.1, Figure 2.1-3, Incorporated the reanalysis of the LOCA and 5.3.1.2, 5.3.1.3.4, 5.3.1.4, 5.3.1.4.1, 5.3.1.4.2, Fuel Handling Accidents resulting from the 5.4, 6.1, Table 6.2-6, 6.3.1.1, 7.7.1, 9.12.6, implementation of alternative source term.

9.12.6.1, 9.13.1, 9.13.2, 9.13.3.1, 9.13.3.2, [10 CFR 50.67]

9.13.3.6, 9.13.3.7, 9.13.4.1, 11.3.1, 11.3.3.13, 11.3.4.2, 11.3.4.3, 11.3.4.4, 11.3.6, Table 11.3-1, 14.4.1.1, 14.4.1.2, 14.4.1.2.1, 14.4.1.2.2, 14.4.1.2.2.1, 14.4.1.2.2.2, 14.4.1.2.2.3, 14.4.1.2.2.4, 14.4.1.2.3, 14.4.1.3.1, 14.4.1.3.2, 14.4.1.3.3, 14.4.1.3.4, 14.4 Refs, Tables 14.4-1, 14.4-2, 14.4-3, 14.4-4, & 14.4-6, 14.5.4, 14.5.5, 14.5.5.1, 14.5.5.2, 14.5.5.3, 14.5.6, 14.5 Refs, Tables 14.5-7, 14.5-8, 14.5-10, 14.5-11,

& 14.5-12

[FS 2000-005A]

Revision 52Updated Online 09/30/20 SPS UFSAR 41 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3409/03/02 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

3.4.1.1, 3.4.1.1.4, 3.4.1.2, 3.4 Refs, 3.5.2.1, Reflected the physical description of Surry 2 3.5.2.6.1, 3.5 Refs, Table 3.5-3 Batch 20 and subsequent reload fuel batches

[FS 2002-003] for Units 1 and 2. Identified the fuel performance models for cycle-specific evaluations.

4.2.2.4 Replaced reactor coolant pump main flange

[FS 99-053] bolts with main flange fasteners.

4.3.1.1 Described the repairs performed on the Unit 1

[FS 2001-043] reactor vessel head and control rod drive mechanism nozzles.

4.3.1.1, Figure 4.3-2 Clarified the stress analysis boundary

[FS 2001-046] conditions at the vessel head penetration shrink fit for the control rod drive mechanism housings. Showed the vessel head penetration welds in their correct orientation.

5.4.1.3.5.4, 8.4.4 Updated a reference document number and

[FS 2002-024] corrected a typographical error.

6.2.3.12.1, 6.2 Refs, Tables 6.2-14 & 6.2-15, Re-evaluated the hydrogen concentration in Figures 6.2-3, 6.2-4, 6.2-5, 6.2-6, 6.2-7, containment following a LOCA.

& 6.2-8

[FS 2002-012]

Table 6.2-13, 6.3.1.3, Table 14B-3 Changed the bleed flow contribution to outside

[FS 2001-026] recirculation spray pump NPSHa, clarified the function of the recirculation spray suction cross-connect line, and deleted the component cooling heat exchangers from the list of postulated targets in the auxiliary building.

7.6.2.1 Installed a plug in the high pressure seal at

[FS 2001-042] Unit 1 core location J5 (1-RC-TW-J5).

7.6.2.1, 7.6.2.2, 7.6.2.3.1, Figures 7.6-1 & Provided the description of a second flux 7.6-2 thimble tube and seal table seals design.

[FS 2000-049] Described the process for converting to the new design.

7.6.2.1, Figure 7.6-1 Installed a plug in the high pressure seal at

[FS 2002-013] Unit 2 core location N8 (2-RC-TW-N8).

Revision 52Updated Online 09/30/20 SPS UFSAR 42 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3409/03/02 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

7.7.2, 9.10.3.5, 9.10.4.13, 10.3.1.2 Incorporated changes to reflect that the decay

[FS 99-034] heat release subsystem is no longer used and that decay heat release components have been removed on Unit 1.

Figure 8.3-1, 8.4.4 Installed an additional 125V dc switchboard

[FS 2002-004] crosstie circuit breaker.

8.5 Removed the diesel generator voltage and

[FS 2001-001] speed relay from the residual voltage time delay relay circuit and increased the time delay from 2.0 to 2.2 seconds.

8.5 Clarified the description of the analysis

[FS 2002-020] consideration of a loss of offsite power being sequenced with a loss of coolant accident.

8.5, Table 8.5-1 Updated the setting of the emergency bus

[FS 99-025] degraded voltage relays. [10 CFR 50.90 License Amendment]

9.1.2.1 Clarified auxiliary spray valve operation

[FS 2001-036] meeting the requirements of the Appendix R analysis.

9.4.3.1 Clarified component cooling system thermal

[FS 2002-008] relief requirements.

9.6.1.2, 9.6.2.2, 9.6.2.2.1, 9.6.2.2.3, 9.6.2.2.6, Clarified the status of the High Radiation 9.6.3.2, 9.6.4.2, 9.6 Refs, Tables 9.6-3 & 9.6-7 Sampling SystemPost-Accident Operation.

[FS 2002-011] [10 CFR 50.90 License Amendment]

9.6.2.1 Reflected the abandonment of recorders from

[FS 2001-024] the secondary sampling system on-line chemistry monitoring panels.

9.10.1 Identified fire protection systems that are not

[FS 2001-039] required to satisfy regulatory criterion.

[10 CFR 50.48]

9.10.1, 16.2, 17.2.1.2, 17.2.5 Removed terminology associated with the

[FS 2001-034] former 10 CFR 50.59 regulation and incorporated wording from the current rule.

9.13.1, 9.13.4.1 Clarified the description of auxiliary building

[FS 2002-009] ventilation fan performance.

Revision 52Updated Online 09/30/20 SPS UFSAR 43 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3409/03/02 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.13.3.3, 9.13.4.1 Enhanced the text description of the

[FS 2002-015] decontamination building ventilation system operation.

9B.2.4.4 Added the reactor vessel head stud racks to the

[FS 2001-002] description of special lifting devices.

9B.2.4.4, Table 9B.2-1 Removed the pneumatic reactor cavity seal ring

[FS 2001-017] and its lifting rig.

11.2.3, 11.2.3.1.7, 11.2.3.2, Tables 11.2-5 Updated the description of steam generator

& 11.2-6 blowdown to reflect system lineup and

[FS 98-001] chemistry guidelines.

11.2.4.1.2 Incorporated current methodology for handling

[FS 97-011] and storing spent radioactive filters.

11.3.3.8, Tables 11.3-6 & 11.3-7 Changed the Unit 1 condenser air ejector

[FS 2001-025] radiation monitor to a more sensitive detector.

11.3.3.8, Tables 11.3-6 & 11.3-7 Changed the Unit 2 condenser air ejector

[FS 2001-038A] radiation monitor to a more sensitive detector.

14.2.10.3, 14.2.10.4, 14.2.10.4.1, 14.2.10.4.2, Incorporated an improved analysis technique Figures 14.2-62, 14.2-63, 14.2-64, 14.2-65, concerning loss of external electrical load.

14.2-66, 14.2-67, 14.2-68, 14.2-69, 14.2-70, 14.2-71, & 14.2-62

[FS 2001-018]

Table 14.2-4 Cited the regulatory whole body dose limit.

[FS 2001-031] [10 CFR 100]

14.5 Refs, Table 14B-2, 15.5 Refs Corrected typographical errors.

[FS 2001-041]

14B.3.3, 14B.5.3.3 Provided discussion of the auxiliary building

[FS 2001-045] ambient temperature monitoring system for detection of a high energy line break and associated automatic/manual actions.

17.2.1.1, 17.2.1.2, 17.2.10, Figures 17.2.1-1, Modified organizational titles and realigned 17.2.1-2, & 17.2.1-3 certain reporting relationships within the

[FS 2002-005] Nuclear Business Unit. [10 CFR 50.54(a)(3)]

17.2.1.2, Figures 17.2.1-1 & 17.2.1-3 Relocated the Records Management Program

[FS 2001-040] organization from General Services to Nuclear Engineering. [10 CFR 50.54(a)(3)]

Revision 52Updated Online 09/30/20 SPS UFSAR 44 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3409/03/02 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

17.2.1.2, 17.2.3, 17.2.5, 17.2.6, 17.2.11, Relocated North Anna Power Station current 17.2.15, 17.2.16, 17.2.18, 17.2 Refs, technical specification requirements for the Table 17.2-0, Appendix C Management Safety Review Committee,

[FS 2001-023] Station Nuclear Safety and Operating Committee, and Station Nuclear Safety to the QA Topical Report. [10 CFR 50.90 License Amendment]

17.2.7 Updated the description of the organizational

[FS 2002-023] structure to reflect the responsibilities of the Vice President Nuclear Engineering and Vice President Nuclear Support Services with respect to procurement, vendor surveillance, and document reviews. [10 CFR 50.54(a)(3)]

Revision 3309/04/01 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.1.6, 1.2.3, 3.3.2.12, 3.5, 3.5.1.3, 3.5.2.1, Incorporated technical and editorial corrections 3.5.2.1.1, 3.5.2.1.2, 3.5.2.1.4, 3.5.2.1.5, 3.5.2.2, and clarifications resulting from the integration 3.5.2.3, 3.5.2.4, 3.5.2.5, 3.5.2.6.1, 3.5.2.6.3, review of mechanical reactor design.

3.5.2.6.4, 3.5.3.1, 3.5.3.1.1, 3.5.3.1.2, 3.5.3.2.1, 3.5.4, 3.5.4.1, 3.5 Refs, Tables 3.5-1 & 3.5-3, Figures 3.5-3, 3.5-4, 3.5-5, 3.5-7, 3.5-9, 3.5-11, 3.5-12, & 3.5-13

[FS 2000-027]

1.4.23, 7.5.1, 8.4.3 Provided clarification of the design and

[FS 2001-011] licensing basis for the power supplies to the vital bus systems.

2.4.1, Table 9.2-1, Table 15.2-1, 15.5.1.8 Corrected typographical, administrative, and

[FS 2000-051] format errors.

3.4.1.1.2, 3.4.1.1.3, 3.4.1.1.4, 3.4.1.1.5, 3.4.1.2, Incorporated technical and editorial corrections 3.4.1.3, 3.4.2, 3.4.2.1, 3.4.2.1.1, 3.4.2.1.2, and clarifications resulting from the integration 3.4.2.2, 3.4.2.2.1, 3.4.2.2.2, 3.4.2.2.3, 3.4.2.2.4, review of thermal/hydraulic reactor design.

3.4.2.3, 3.4.2.4, 3.4.2.5, 3.4.2.6, 3.4.3.1, 3.4.3.2, 3.4.3.2.1, 3.4.3.3, 3.4.3.5, 3.4.3.8, 3.4 Refs, Table 3.4-1, Figures 3.4-1, 3.4-4, 3.4-8, & 3.4-10, Table 4.2-1, 8.5, 10.3.5.3

[FS 2000-028]

Revision 52Updated Online 09/30/20 SPS UFSAR 45 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3309/04/01 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

4.2.2.8, 14.2.6.2.2, 14.2.6.2.3 Established additional reactivity controls and

[FS 99-042A] surveillance for the vacuum-assisted backfill method of returning an RCS loop to service.

[10 CFR 50.90 License Amendment]

Table 5.4-20 Revised the containment analysis results for

[FS 2001-013] depressurization time and subatmospheric peak pressure.

6.2.3.12.1, Table 6.2-14 Updated the description of the containment

[FS 2001-010] hydrogen generation analysis.

6.2.3.12.1, Table 6.2-14, 14.5.1.3, 14.5.1.4, Corrected typographical, administrative, and Table 14.5-3, 15A References format errors.

[FS 2001-027]

Figures 6.2-1 & 6.2-2 Incorporated modifications to the Unit 1 safety

[FS 99-063] injection system.

7.6.2.1, Figure 7.6-1 Installed a seal welded cap on the flux thimble

[FS 2000-046] tube at location 2-RC-TW-N8.

8.5 Added definition of loss of offsite power

[FS 2000-037] (LOOP) as a LOOP to both units to the introduction of the emergency power system.

8.5 Added a time delay relay to each filter exhaust

[FS 2000-045] fan start circuit to allow proper damper alignment.

9.4.4.3 Provided a description of the air lockup valve

[FS 2000-043] on the reactor coolant pump thermal barrier inside and outside containment component cooling trip valves.

9.6.1.2, 9.6.2.2.6, Table 9.6-7 Deleted time restraints for containment sump

[FS 2000-052] sampling or analysis with the high radiation sampling system.

9.8.1, Table 9.8-1 Deleted statement that the compressed air

[FS 2001-007] system air receivers are sized to provide ten minutes of breathing quality air and air to essential systems after shutdown of all compressors following a loss-of-power accident. Corrected compressed air system design data.

Revision 52Updated Online 09/30/20 SPS UFSAR 46 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3309/04/01 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.10.4.4 Included a description of the two-hour design

[FS 2000-048] basis discharge/recharge case for the station batteries.

9.10.4.4 Revised the description of hydrogen generation

[FS 99-043] and fire potential in the station battery rooms.

9.10.4.12 Incorporated modifications to the reactor

[FS 2000-041] coolant pump motor oil collection system.

9.10.6, 12.2.2.3, 17.2.1.1, 17.2.1.2, 17.2.2.1, Modified organizational titles and reporting 17.2.2.5, 17.2.3, 17.2.7, 17.2.10, 17.2.15, relationships associated with the entire Nuclear 17.2.16.2, 17.2.17, 17.2.18, Figures 17.2.1-1, Business Unit. [10 CFR 50.54(a)(3)]

17.2.1-2, & 17.2.1-3, Table 17.2-0

[FS 2001-019]

9.12.3.1, 9.12.5.2 Changed the design of the reactor cavity seal

[FS 2000-017] from pneumatic to mechanical.

9.12.5.2 Corrected the description of lifting the reactor

[FS 2000-044] vessel head with the reactor containment polar crane.

9.13.1, 9.13.4.1, 14.3.2 Updated the description of feedwater isolation

[FS 2000-024] for the rupture of a main steam pipe accident and of auxiliary building ventilation system capability.

9.13.2 Clarified the design and testing of the

[FS 99-046A] safety-related charcoal filters installed in the auxiliary ventilation exhaust system.

[10 CFR 50.90 License Amendment]

9.13.3.7, 9.13.4.1 Clarified auxiliary filtration requirements

[FS2000-053A] consistent with the Basis for Technical Specification 3.22.

9C.1.1, 9C.2 Deleted carbon steel from the description of

[FS 97-020] the flow restriction shields installed around circulating water system expansion joints.

10.3.1.2, 14.3.1.5 Added the description of the backup bottled air

[FS 99-057] system for the steam generator power operated relief valves.

Revision 52Updated Online 09/30/20 SPS UFSAR 47 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3309/04/01 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

11.2.3, 11.2.3.1.10, Table 11.2-1, Installed a cross-connect line between the Figures 11.2-2 & 11.2-5 Radwaste Facility building drain system and

[FS 2000-047] the laundry waste system. Installed a second laundry drain pre-filter.

Tables 11.2-2 & 11.2-3 Corrected typographical errors.

[FS 2001-014]

14.2.11.1, 14.2.12, Figures 14.2-73, 14.2-74, Described the reanalysis of the loss of normal 14.2-75, 14.2-76, 14.2-77, 14.2-78, 14.2-79, feedwater (LONF) and loss of ac power to the

& 14.2-80, 14B.5.1.7 station auxiliaries (LOAC) events with

[FS 2001-005] 500 gpm auxiliary feedwater flow during the transient.

14.3.1.4.2, 14.3.1.4.4, 14.3.1.4.5, 14.3.2.4.2, Reflected the reanalysis of the dose 14.3.2.4.4, 14.3.2.4.5, 14.3 Refs, Tables 14.3-9, consequences of the steam generator tube 14.3-10, 14.3-11, 14.3-12, & 14.3-16 rupture and main steam line break events.

[FS 2000-032]

14.5.1.1, 14.5.1.2, 14.5.1.3, 14.5.1.4, 14.5.1.5, Updated the analysis of the large break 14.5.1.7, 14.5.1.8, 14.5 Refs, Tables 14.5-2, loss-of-coolant accident.

14.5-3, 14.5-4, 14.5-5, 14.5-6, 14.5-7, 14.5-8,

& 14.5-9, Figures 14.5-2, 14.5-3, 14.5-4, 14.5-5, 14.5-6, 14.5-7, 14.5-8, 14.5-9, 14.5-10, 14.5-11, 14.5-12, 14.5-13, 14.5-14, 14.5-15, 14.5-16, 14.5-17, 14.5-18, 14.5-19, 14.5-20, 14.5-21, 14.5-22, 14.5-23, 14.5-24, 14.5-25, 14.5-26, 14.5-27, 14.5-28, 14.5-29, 14.5-30, 14.5-31, 14.5-32, 14.5-33, 14.5-34, 14.5-35, 14.5-36, 14.5-37

[FS 2001-008]

Table 15.2-1 Restored the seismic Category I designation for

[FS 2000-054] the yard hydrant piping system.

15.5.1.8, 15.5 Refs. Documented the evaluation of isolated

[FS 99-013] containment penetration piping for susceptibility to thermal over-pressurization following a DBA. [NRC Generic Letter 96-06]

15A.3.2, 15A Refs Incorporated generic implementation procedure

[FS 2001-004] criteria and methodology for seismic verification of equipment.

Revision 52Updated Online 09/30/20 SPS UFSAR 48 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3309/04/01 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

17.2.17, Table 17.2-0 Updated the Quality Assurance Topical Report

[FS 99-067] description of the retention of quality assurance records in electronic media.

[10 CFR 50.54(a)(4)]

Table 17.2-0 Clarified the provision for substitution of

[FS 2001-020] experience for a bachelors degree.

[10 CFR 50.54(a)(3)]

Tables 17.2-0, 17.2-2, & 17.2-3 Reduced records retention requirements

[FS 2000-003] consistent with ANSI N45.2.9 or applicable regulations. [10 CFR 50.54(a)(4)]

Revision 52Updated Online 09/30/20 SPS UFSAR 49 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3209/01/00 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 1.4.2, 1.4.5, Ch 2, 2.2.2.1, 2.3.1.2.2, Incorporated technical and editorial corrections Tbl 2.3-7, 2.4.7.2, 2.4.7.6, 2.4.9, Tbls 2.4-9, and clarifications resulting from the integration 2.4-10, & 2.4-12, Figs 2.4-5 & 2.4-6, 2.5.4.3, review of civil/structural/seismic topics.

4.3.1.2, 4.3 Refs, Tbl 4.3-3, Fig 4.3-3, 7.2.1, 7.5.1, 9.2.3.1, 9A.2, 9A.3.1.3.1, 15.1, 15.2.4, Tbl 15.2-1, 15.4.1, 15.4.4, 15.4.5, 15.4.6, 15.4.6.1, 16.4.6.2, 15.4.6.3, 15.4.6.4, 15.4.6.4.1, 15.4.6.4.2, 15.4.6.4.3, 15.4.6.4.4, 15.4.6.4.5, 15.4.6.4.6, 15.4.6.4.7, 15.4.6.4.8, 15.4.6.4.9, 15.4.6.4.10, 15.4.6.4.11, 15.4.6.4.12, 15.4.6.4.13, 15.4.6.4.14, 15.4.6.4.15, 15.4.6.4.16, 15.4.6.4.17, 15.4.6.4.18, 15.4.6.4.19, 15.4.6.5, 15.4.6.5.1, 15.4.6.5.2, 15.4.6.5.3, 15.4.6.5.4, 15.4.6.5.5, 15.4.6.5.6, 15.4.6.5.7, 15.4.6.5.8, 15.4.6.5.8.1, 15.4.6.5.8.2, 15.4.6.5.8.3, 15.4.6.5.8.4, 15.4.6.5.8.5, 15.4.6.5.9, 15.4.6.5.9.1, 15.4.6.5.9.2, 15.4.6.5.9.3, 15.4.6.5.10, 15.4.6.5.10.1, 15.4.6.5.10.2, 15.4.6.5.10.3, 15.4.6.5.11, 15.4.6.5.11.1, 15.4.6.5.11.2, 15.4.6.5.11.3, 15.4.6.5.11.4, 15.4.6.5.11.5, Figs 15.4-1 thru 15.4-3, 15.5.1.6, 15.5.1.8, 15.5.1.10, 15.5.1.12, 15.5.1.13.3, Figs 15.5-5

& 15.5-6, 15.6, 15.6.1, 15.7, 15.7 Refs, 15A, 15A.3.1, 15A.3.2, 15A.3.3, 15A.3.4, 15A.3.5, 15A.3.5.1, 15A.3.5.2, 15A.3.5.2.1, 15A.3.5.2.2, 15A.3.4.2.3, 15A.3.5.2.4, 15A.3.5.3, 15A.4, 15A Refs, Tbl 15A-5

[FS 99-050]

KWI, Table 4.1-9, 5.4.1.3.5.4, Table 9.1-7, Incorporated updates to the key word index and 9.4.4.7, Table 9.4-1, Figure 9.9-1, 14.2.5.2.1 corrected typographical, spelling, grammar and

[FS 99-044] administrative errors.

Revision 52Updated Online 09/30/20 SPS UFSAR 50 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3209/01/00 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 5.3.1.1, 5.3.1.3.1, 9.3.3.2, 9.4, 9.4.1.1, Incorporated technical and editorial corrections 9.4.1.2, 9.4.1.3, 9.4.1.4, 9.4.1.5, 9.4.3.1, and clarifications resulting from the integration 9.4.3.2, 9.4.3.3, 9.4.3.5, 9.4.4.1, 9.4.4.3, review of the component cooling water system.

9.4.4.5, 9.4.5, 9.4 Refs, 9.4 RefDwgs, Tables 9.4-7 through 9.4-10, Figures 9.4-1 through 9.4-5, 9.9, 9.9.1, 9.9.2.1, 9.9.3.2, Table 9.9-3

[FS 99-022]

1.1, 1.4.2, 1.4.28, 1.4.29, 1.4.31, 1.4.33, 1.6, Incorporated technical and editorial corrections 1.6.1.1, 1.6.2.8, 3.1, 3.2.1, 3.2.2.1, 3.2.3.1, and clarifications resulting from the integration 3.2.3.3, 3.2 Refs, 3.3.1, 3.3.2.1, 3.3.2.3, review of reactor design.

3.3.2.10, 3.3.2.12, 3.3.2.13, 3.3.3.2.2, Table 3.3-1, Figures 3.3-1, 3.3-2, 3.3-3, 3.3-7, 3.3-8, & 3.3-9, Table 3.4-1, 3.6.1.2, 3.6.2, 3.6.3.1, 4.3.1.1, 4.3 Refs, 9.1.1.2, 9.1.2.3.1, 9.1 Refs

[FS 2000-025]

1.2.5, 1.4.70, 7.2.1.1, 7.7.1, 9.1.2.1, 9.1.2.6.15, Incorporated technical and editorial corrections 9.2, 9.2.1, 9.2.2, 9.2.3, 9.2.4, Tables 9.2-1 and clarifications resulting from the integration

& 9.2-2, Figure 9.2-1, 9.7.2, 11.2.3, 11.2.3.1.1, review of the boron recovery and waste 11.2.3.1.2, 11.2.3.1.3, 11.2.3.1.11, 11.2.3.2, disposal systems.

11.2.3.2.1, 11.2.4.1.3, 11.2.4.1.5, 11.2.4.2, 11.2.4.2.1, 11.2.4.2.3, 11.2.4.2.5, 11.2.4.2.7, 11.2.4.2.11, 11.2 RefDwgs, Tables 11.2-1, 11.2-8 through 11.2-10, Figures 11.2-1

& 11.2-2, 11A.4.2

[FS 99-031]

1.2.8, 1.4.24, 1.4 RefDwgs, 4.3.6, 7.7.1, 8.1, Incorporated technical and editorial corrections Figure 8.1-1, 8.2, 8.3, 8.3 RefDwgs, and clarifications resulting from the integration Figure 8.3-2, 8.4.1, 8.4.2, 8.4.3, 8.4.4, 8.4.6, review of the vital bus and station service 8.5, 8.6, 9.1.3.1 systems.

[FS 99-051]

Revision 52Updated Online 09/30/20 SPS UFSAR 51 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3209/01/00 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.4.3, 7.2.2.1.1, 7.7.2, 9.1.2.1, 9.3.2.1, 9.4.3.1, Incorporated technical and editorial corrections 9.10.1, 9.10.2.1, 9.10.2.2.1, 9.10.2.2.3, and clarifications resulting from the integration 9.10.2.2.5, 9.10.2.2.7, 9.10.2.2.9, 9.10.2.3.2, review of the fire protection system.

9.10.2.3.3, 9.10.2.4, 9.10.2.6, 9.10.2.8, 9.10.2.9, 9.10.3.3, 9.10.3.4, 9.10.3.5, 9.10.4.1, 9.10.4.3, 9.10.4.4, 9.10.4.5, 9.10.4.7, 9.10.4.8, 9.10.4.9, 9.10.4.10, 9.10.4.11, 9.10.4.12, 9.10.4.14, 9.10.4.15, 9.10.4.16, 9.10.4.17, 9.10.4.18, 9.10.4.19, 9.10.4.20, 9.10.4.22, 9.10.4.23, 9.10.4.24, 9.10.4.25, 9.10.4.26, 9.10.4.27, 9.10.5, 9.10.6, Table 9.10-1, 9.11.1, Table 9.11-1, Figure 9.11-1, 9.13.4.1, 10.3.9.3, 11.1, 11.1 Refs

[FS 99-027]

1.4.5, 7.7.2, 9.1.2.2, Figure 10.3-2, 12.1.1.2.1, Corrected typographical, administrative, and 12.4, 12.5, 12.6, 13.1, 14.2.2, 14.2.2.1, format errors.

14.2.5.1, 14.2.5.2.2, 14.2.9.2.3, 14.2.9.2.4.1, Table 14.2-4, Figure 14.2-84, 14.3.2.1, 14.3.2.2.1, 14.3.3.2.2.2, 14.3.3.2.2.4, 14.4.1.2.2.1, 14.4.2.1, Table 14.4-6, 14.5.2.3, 14.5.2.4.2, 14.5.3.3.2, 14.5.3.4.1, 14.5.5.2, 14.5 Refs, Table 14.5-14, Figures 14.5-5

& 14.5-38, 15.4.6

[FS 2000-023]

1.4.11, 5.3.1.2, 5.3.1.3.2, 3.1.3.3, 5.3.1.3.4, Incorporated technical and editorial corrections 5.3.1.4, 5.3.1.4.1, 5.3.1.5, Table 5.3-1, 6.3.1.4, and clarifications resulting from the integration 7.7.2, 9.13.1, 9.13.3.2, 9.13.3.1, 9.13.3.2, review of the ventilation system.

9.13.3.3, 9.13.3.4, 9.13.3.5, 9.13.3.6, 9.13.3.7, 9.13.3.9, 9.13.4, 9.13.4.1, 9.13.4.2, 9.14.2, 9.14.3, 10.3.6.2, 10.3.8.2, 11.2.2, 11.2.5, Table 11.2-11, 11.3.3.14, 11.3.6

[FS 99-040]

1.4.18, 9.4.1.3, 9.4.3.3, Tables 9.4-2 through Incorporated technical and editorial corrections 9.4-5, 9.5.1, 9.5.3.4, 9.5 Refs, 9.5 RefDwgs, and clarifications resulting from the integration Figure 9.5-1, Table 10.3-4, Figure 10.3-11 review of spent fuel pool cooling, chilled water,

[FS 99-049] and bearing cooling systems.

Revision 52Updated Online 09/30/20 SPS UFSAR 52 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3209/01/00 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.4.24, 2.1.3.2, 2.4.3.3, 2.4.7.4, 2.4.8, Corrected typographical, administrative, and Tables 2.4-13 & 9.5-1, 9.10.6, Figure 9A-1, format errors.

11.1 Refs, 15.2.4, Table 15.2-1, 15.4.1

[FS 99-058]

1.4.46, 6.2.2.2.3, 6.2.2.2.4, Tables 6.2-5 Incorporated technical and editorial corrections

& 6.2-8 and clarifications resulting from the integration

[FS 98-042] review of the safety injection system.

1.4.49, 1.4.55, 1.4.57, 5.2.1, 5.2.2, Tables 5.2-1 Incorporated technical and editorial corrections

& 5.2-2, 5.3.4, 5.3.4.1, 5.3.4.2, 5.3.4.3, 5.3.4.4, and clarifications resulting from the integration Tables 5.3-4 & 5.3-5, Figure 5.3-2, 5.4.2, review of the containment systems.

5.4.2.1, 5.4 Refs, 5.5.1, 6.1, Table 6.2-7, 6.3.1.1, 6.3.2, 6.3.2.1, 6.3.2.2, 6.3.2.3, 6.3.2.4, Tables 6.3-4 & 6.3-5, Figure 6.3-6, 7.5.1.4.2, 15.5.1.2, 15.5.1.8

[FS 99-039]

1.5, 9.1, 9.1.1, 9.1.1.2, 9.1.1.3, 9.1.2, 9.1.2.1, Incorporated technical and editorial corrections 9.1.2.4, 9.1.2.4.1, 9.1.2.5, 9.1.2.6.1, 9.1.2.6.2, and clarifications resulting from the integration 9.1.2.6.7, 9.1.2.6.8, 9.1.2.6.9, 9.1.2.6.12, review of the chemical and volume control and 9.1.2.6.15, 9.1.2.6.16, 9.1.2.6.17, 9.1.2.6.18, residual heat removal systems.

9.1.2.6.19, 9.1.2.6.20, 9.1.3.1, 9.1.3.3, 9.1.3.5.2, 9.1.3.5.3, 9.1 Refs, Tables 9.1-1 through 9.1-3, 9.1-8, & 9.1-9, 9.3.1, 9.3.2.1, 9.3.2.2.2, 9.3.2.2.3, 9.3.3.1, 9.3.3.2, Tables 9.3-2 through 9.3-4, 9.4.1.1, 9.9.1.3

[FS 99-041]

Figures 2.4-6 & 2.4-7, 6.2.3.10, 7.9.2.5, Corrected typographical, administrative, and 7.10.2.1, 7.10.2.2, 12.1.1.2.1, 14.5 Refs format errors.

[FS 2000-018]

3.6.3.1, 9A.2, 14.5.2.3 Corrected typographical, administrative, and

[FS 2000-040] format errors.

4.1.7.4, 4.1 Refs, Tables 4.1-13 through 4.1-15 Incorporated the most recently acquired and

[FS 2000-035] currently applicable reactor vessel material properties data.

Revision 52Updated Online 09/30/20 SPS UFSAR 53 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3209/01/00 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 4.1-2, 9.10.3.3, 9.10.4.2, 9.10.4.3, Incorporated technical and editorial corrections 9.10.4.13, 10.3.1.2, 10.3.1.5, 10.3.3.1, and clarifications resulting from the integration 11.3.3.14, 14.3.1.2, 14.3.1.3, 14B.2.3.2.3, review of the high energy line break.

14B.4.2, 14B.4.3, 14B.5.1.1, 14B.5.1.4, 14B.5.1.5, 14B.5.1.6, 14B.5.1.6.1, 14B.5.1.6.2, 14B.5.1.6.3, 14B.5.1.6.4, 14B.5.1.6.4.2, 14B.5.1.6.4.3, 14B.5.1.6.4.5, 14B.5.2.1, 14B.5.2.5, 14B.5.3.3, 14B.5.4.2, 14B Refs, Tables 14B-2, 14B-3, & 14B-9, Figures 14B-1

& 14B-10

[FS 2000-007]

Table 4.1-4, 10.3.1.2, 10.3.4.2, 10.3.5.2, Incorporated technical and editorial corrections 10.3.6.2, Figure 10.3-2 and clarifications resulting from the integration

[FS 99-038] review of the feedwater, condensate, steam generator blowdown, and condensate polishing systems.

4.2.11, 4.2 Refs, 9.3.1, 9.6.2.1, 9.6.2.2.6, Incorporated technical and editorial corrections 9.6.3.2, Tables 9.6-7 & 9.7-1, Figure 9.7-1, and clarifications resulting from the integration 10.3.8.1 review of the sampling and primary vents and

[FS 99-047] drains systems.

5.2.2, 5.2 Refs Updated the discussion of acceptable closure

[FS 2000-031] time of a normally closed manual isolation valve.

Table 5.2-1 Reflected the addition of a new inside

[FS 99-054] containment isolation valve.

Tables 5.2-1 & 5.2-2 Updated Table 5.2-1 to reflect changes to

[FS 99-045] valves subject to Type C testing as defined in 10 CFR 50, Appendix J. [10 CFR 50, Appendix J]

Revision 52Updated Online 09/30/20 SPS UFSAR 54 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3209/01/00 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

5.4.1.3.4, 6.2.2.1.4, 14.1, 14.1 Refs, 14.2.1, Incorporated technical and editorial corrections 14.2.2.2, 14.2.2.3, 14.2.4.2, 14.2.7.2, and clarifications resulting from the integration 14.2.7.3.1, 14.2.7.3.3, 14.2.7.4, 14.2.9.2.1, review of the plant safety analyses.

14.2.9.2.2.2, 14.2.9.2.4.1, 14.2.9.2.4.3, 14.2.10.4.2, 14.2.13, 14.2 Refs, Figures 14.2-16 through 14.2-21, & 14.2-27, 14.3.1.1, 14.3.1.4.3, 14.3.1.4.4, 14.3.2.1, 14.3.2.2.1, 14.3.2.5, 14.3.3.1.1.2, 14.3.3.2.1, 14.3.3.2.1.2, 14.3 Refs, Tables 14.3-8, 14.3-11,

& 14.3-12, 14.4.1.1, 14.4.1.2, 14.4.1.2.1, 14.4.1.2.2.2, 14.4.1.3.1, 14.4.2.1, 14.4.2.2.1, 14.5.1.2, 14.5.1.3, 14.5.1.8, 14.5.2.3, 14.5.2.4.2, 14.5.6, 14.5 Refs, Tables 14.5-2, 14.5-11, & 14.5-12, Figures 14.5-30 & 14.5-31

[FS 2000-016]

Table 6.2-6, Table 6.3-2, 14.5.5.3, 14.5 Refs Updated the allowable leakage from the safety

[FS 2000-008] injection and charging systems.

7.2.2.2.10, 7.3.2.2.3, 7.4.3.4, 7.4.3.6, 7.4.3.8, Incorporated technical and editorial corrections 7.4.4.1, 7.4.4.3, 7.4.4.4.2, 7.4.4.4.3, and clarifications resulting from the integration Table 7.4-3, Figure 7.4-2, 7.6.1, 7.6.2.1, review of the nuclear instrumentation system.

7.6.2.3.1, Figure 7.6-1, 7.11.1

[FS 99-035]

7.3.1, 7.3.2.1, 7.3.2.2.1, 7.3.2.2.2, 7.3.2.3.1, Incorporated technical and editorial corrections 7.3.2.3.2, 7.3.3.2, 7.3.3.5, 7.3 RefDwgs, 7.7.2, and clarifications resulting from the integration 7.8.1, 7.8.2, 7.8.3, Figure 7.8-1 review of the nuclear control system.

[FS 99-059]

7.7.2, 9.10.3.5, 9.10.4.13, 10.3.1.2 Incorporated changes to reflect that the decay

[FS 99-033] heat release subsystem is no longer used and that decay heat release components have been removed on Unit 2.

7.12.1.1, 10.3.5.3 Incorporated technical and editorial corrections

[FS 2000-022] and clarifications resulting from the integration review of the electrical instrumentation and plant computer system.

9.4.4.3, 9.8.1, 9.8.2, 9.8.3, 9.8.4, Table 9.8-1, Incorporated technical and editorial corrections Figure 9.8-1, 10.3.9.3, Table 15.2-1 and clarifications resulting from the integration

[FS 2000-011] review of the instrumentation air system.

Revision 52Updated Online 09/30/20 SPS UFSAR 55 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3209/01/00 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 9.4-1 Updated the design data for the component

[FS 96-032] cooling water heat exchangers to describe the replacement heat exchangers.

9.7.2, 11.2.2, 11.2.5, 11.2.5.1, 11.2.5.2.3, Incorporated technical and editorial corrections 11.2.6.1, Tables 11.2-2 & 11.2-3 and clarifications resulting from the integration

[FS 99-028] review of the gaseous waste disposal system.

9.7.3 Incorporated a modification to the level

[FS 99-023] detector and controls for the auxiliary building sump pumps.

9.9.1.2 Updated the description of emergency service

[FS 99-007] water pump capacity associated with a design change to improve pump reliability.

9.9.1.3 Provided additional information concerning the

[FS 2000-034] response required for hurricane conditions that are less severe than those produced by the probable maximum hurricane.

9.10.2.2.9, 9.10 Refs Added a description of the design basis for the

[FS 99-021] halon system in the emergency switchgear rooms.

9.10.3.3, 10.3.1.2 Added a description of the local operation of

[FS 99-019] the atmospheric steam dump valves.

9.10.4.8 Incorporated terminology from new EPA

[FS 2000-010] regulation, 40 CFR 279.22(c)(1).

9.12.4.4, 9.12.4.5, 9.12.4.6, 9.12.4.9, 9.12.4.13, Incorporated technical and editorial corrections 9.12.4.14, 9.12.5.2, 9.12.5.4, 9.12.6.2, 9.12.8, and clarifications resulting from the integration 9.14.2, 9A.2 review of fuel handling and storage.

[FS 2000-014]

9.13.2, 14B.5.2.1 Incorporated the environmental impact of a

[FS 2000-004] turbine building high energy line break on the control room envelope, mechanical equipment room no. 5, and the emergency diesel generator room.

10.3.5.3, 14.2.11, 14.2.11.1, 14.2.11.1.1, Incorporated the description of the reanalysis 14.2.11.1.2, 14.2.11.1.3, 14.2.11.1.4, 14.2.11.2, of the loss of normal feedwater event and the 14.2.12, 14.2 Refs, Figures 14.2-79 loss of ac power to the station auxiliaries event.

through 14.2-89

[FS 2000-015]

Revision 52Updated Online 09/30/20 SPS UFSAR 56 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3209/01/00 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

11A.4.1, 11A.4.2, Table 11A-1 Added descriptions of the application of the

[FS 96-065] Offsite Dose Calculation Manual.

12.4 Corrected the reference to the personnel

[FS 2000-026] qualification requirements for SNSOC and station supervisory personnel. [10 CFR 50.90 License Amendment]

14.2.13 Specified that the governor and main stop

[FS 98-050] valves are exercised on a periodic basis in order to eliminate part of the transient experienced during turbine inlet valve freedom testing.

14.5.1.6, 14.5.1.7, 14.5.2.6, 14.5.2.7, 14.5 Refs, Incorporated descriptions of the peak clad Tables 14.5-5 & 14.5-18 temperature penalties and benefits in the large

[FS 99-060] and small break LOCA analyses.

16.2 Revised the description of the administrative

[FS 99-052] controls that apply to the Technical Requirements Manual.

17.2.1.2, 17.2.2.1, 17.2.17, Figure 17.2.1-1 Modified organizational titles and reporting

[FS 2000-033] relationships associated with information technology.

17.2.1.2, 17.2.2.6, Figure 17.2.2-1 Updated organizational description to reflect

[FS 2000-009] Supply Chain Management (Generation) titles.

17.2.1.2, Figure 17.2.1-2 Modified organizational titles and reporting

[FS 2000-020] relationships associated with records management.

17.2.1.2, Figure 17.2.1-2 Modified organizational titles and reporting

[FS 2000-036] relationships associated with the radwaste facility.

Revision 52Updated Online 09/30/20 SPS UFSAR 57 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 1.4.9, 1.4.16, 4.1.3.1, 4.1.4, 4.1.7.1, Incorporated technical and editorial corrections 4.1.7.2, 4.1.7.4, 4.1 Refs, Tables 4.1-1, 4.1-5, and clarifications resulting from the integration 4.1-8, 4.1-10, & 4.1-11, 4.2.1, 4.2.2.1, 4.2.2.3, review of the reactor coolant system.

4.2.2.3.1, 4.2.2.3.2, 4.2.2.3.3, 4.2.2.4, 4.2.2.7, 4.2.2.8, 4.2.3, 4.2.5, 4.2.6, 4.2.7.2, 4.2.9, 4.2.9.1, 4.2.9.2, 4.2.9.3, 4.2.9.4, 4.2.9.5, 4.2.9.6, 4.2.9.7, 4.2.10, 4.2.10.1, 4.2.10.2, 4.2 RefDwgs, Tables 4.2-3 & 4.2-4, Figures 4.2-8 & 4.2-11, 4.3.1.3, 4.3.2, 4.3.3.1, 4.3.3.2, 4.3.4.2, 4.3.6, 4.3 Refs, Tables 4.3-4

& 4.3-5, 4.4.1.4, 7.2.3.2.3, 7.3.2.4, 7.10.1, 7.10.2.3, Table 7.10-1, 9.10.3.2

[FS 99-001]

KWI, 4.2.2.2, 6.2.3.3, 6.3.2.1, Tables 6.3-1 Provided grammatical and editorial corrections.

& 3, 7.6.2.1, 7.6.3, 7.10 References, 8.4.1, 8.4.4, Tables 11.2-8 & 9, 11.3.3.10, 14.2.6, 14.5.1.1, 14.5.1.4, 14.5.2.3, Table 14.5-14

[FS 98-052]

KWI, Tables 5.2-1 & 5.2-2, 7.5 References, Revised key word references, corrected 9.1.2.3, Table 9.5-1, App 9B, 10.3.5.2, formatting, typing, and capitalization errors, 10.3.5.3, 11.2.2, 11.2.3, 11.2.4, Tables 11.2-1 & updated reference lists and references in text, 11.2-11, Figures 11.2-4 through 11.2-6, added a list of tables to App 9B, and replaced a 11.3.3.1, 14.2.11, 14B.5.1.7, 16.2.2.1 non-standard drawing symbol.

[FS 99-004]

KWI, 15.3.2 Added references to the key word index and

[FS 95-045] expanded the description of the containment reinforcing steel.

Ref Dwgs: 1.2, 1.4, 2.1, 2.3, 4.2, 5.3, 6.2, 7.2, Corrected reference drawing descriptions, 7.3, 7.7, 8.3, 8.4, 9.1, 9.2, 9.3, 9.4, 9.5, 9.6, 9.7, eliminated duplicate entries, and added 9.8, 9.9, 9.10, 9.11, 9.12, 9.13, 9.14, 10.2, 10.3, companion Unit 2 drawings, where 11.2, 11.3, 15.1, 15.5; Section 9.9 appropriate, in the reference drawing list and

[FS 99-006] revised drawing reference numbers in the text.

1.4.16, 1.4.17, 4.2.7.1, 7.7.2, 9.13.1, 9.13.4.1, Incorporated technical and editorial corrections 11.3.3, 11.3.3.1, 11.3.3.3, 11.3.3.7, 11.3.3.8, and clarifications resulting from the integration 11.3.3.10, 11.3.3.13, 11.3.3.14, 11.3.4.1, review of the radiation monitoring system.

11.3.4.2, 11.3.4.3, 11.3.4.4, 11.3.4.7, 11.3.6, 11.3 RefDwgs, Tables 11.3-6 through 11.3-9

[FS 99-002]

Revision 52Updated Online 09/30/20 SPS UFSAR 58 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.4.17, 6.3.1.2, Table 9.4-7, 9.9, Incorporated technical and editorial corrections Tables 9.9-1&2, Figure 9.9-1, 9.10.4.17 & 18 and clarifications related to the Service Water

[FS 98-014] (SW) System: deleted singular SW flow rate through recirculation spray heat exchangers, corrected the description of the emergency service water pumps, and enhanced the description of the high-level intake canal.

1.4.39, 8.5, Table 8.5-1, 9.10.2.4, & 9.10.4.19 Incorporated technical and editorial corrections

[FS 98-022] and clarifications related to the Emergency Diesel Generator (EDG) System: improved the description of testing, enhanced the description of the auto tap changer configuration, corrected the EDG day tank capacity, rewrote the description of the undervoltage setpoint scheme, and improved the description of load sequencing.

1.4.59, Table 5.4-20, 6.1, Figures 6.1-1 & 2, Incorporated technical and editorial corrections 6.2.3.3, 6.3.1.3, 6.3.1.5.1, 6.3.1.5.2, and clarifications related to the Containment 6.3 References, Tables 6.3-1 & 3, Figure 6.3-1, Spray (CS) System: improved the description 13.1, Table 13.1-1, 13.5, 13.5.1, 13.5.1.1, of testing; designated historical information; 13.5.1.2, 13.5.1.3, 13.5.1.3.1, 13.5.1.3.2, corrected a cross-reference; corrected the figure 13.5.1.3.3, 13.5.1.3.4, 13.5.1.3.5, 13.5.2, depiction of the RWST, CS pumps, and spray 13.5 References, Tables 13.5-1 & 13.5-2 headers; reflected the analyzed amount of time

[FS 98-027] of system operation; enhanced the description of electrical cables; reworded RWST welding requirements; changed the RWST material description; clarified the capacity, heat tracing, and insulation of the chemical addition tank (CAT); resolved discrepancy regarding the manifold drain line; clarified description of electrical equipment testing; corrected rated pump flow; corrected pump motor insulation class; corrected nominal RWST operating temperature; clarified CAT pump horsepower rating; clarified pump operating temperature and test pressure description; clarified the description of check valves; and changed the depressurization time and subatmospheric peak pressure.

Revision 52Updated Online 09/30/20 SPS UFSAR 59 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.4.68, 1.4.69, 9.1.2.2, 11.2.2, 11.2.3, 11.3.2.1, Incorporated technical and editorial corrections 11.3.2.2, 11.3.2.6, 11.3.2.9, 11.3.5.8, and clarifications resulting from the integration Tables 11.3-3 & 11.3-4, 11A, Table 11A-1 review of the radiation protection system.

[FS 99-016]

1.5, 4.3.1.2, 6.2.2.2.7, 10.2 RefDwgs, Incorporated technical and editorial corrections Figure 10.2-1, 10.3.1, 10.3.1.1, 10.3.1.2, and clarifications resulting from the integration 10.3.1.3, 10.3.3, 10.3 RefDwgs, 14.3.2 review of the main steam system.

[FS 99-012]

Table 2.1-4, 10.3.1.4, 10.3.5.2 Added ethanolamine to the list of chemicals

[FS 96-063] used for pH control.

2.2.1.1, 2.2.1.2, 2.3.1.2.2, Table 9.4-9, 9.12.9.2, Updated text, table, and figure cross references; 11.3.4.5, Table 11A-1 corrected typographical errors; revised

[FS 99-024] non-standard number and unit formats; and sorted a table in alpha-numeric order.

2.3.1.1, 2.3.1.2.1, 2.3.2, 2.3 Refs, Tables 2.3-1 Updated the mean monthly discharge and flood through 2.3-4 discharge rates, added new references, and

[FS 95-038] revised the descriptions of on-site and off-site wells.

3.2.1 Removed the description of boron injection via

[FS 96-054] the safety injection system.

3.5.2.3 Revised the description of secondary neutron

[FS 97-008] sources to reflect that they are optional in reload cores.

4.1.2.6, 4.2.7.1 Removed references to monitoring containment

[FS 96-059] leakage by monitoring containment humidity.

4.1.7.4, 4.1 Refs, Tables 4.1-14 & 4.1-15 Updated reactor pressure vessel toughness data

[FS 99-018] associated with Technical Specification Basis change.

Table 4.2-2, 9.1.2.6.8 Revised the reactor coolant dissolved hydrogen

[FS 97-005] guidelines to include startup, shutdown, and off-normal conditions.

4.3.3.1 Modified the description of inservice

[FS 98-006] inspection requirements on the reactor coolant pump flywheel. [10 CFR 50.90 License Amendment]

4.3.4.2 Clarified the function of the PORV backup-air

[FS 96-053] spare bottles.

Revision 52Updated Online 09/30/20 SPS UFSAR 60 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 5.2-1, 5.3.1.3.1, 9.4.1.1, 9.4.4.7, 9.12.9.3, Updated text cross references, corrected 9.13.4.2, 11.2.3.1.7 typographical errors, and improved

[FS 99-037] grammatical usage.

Table 5.2-2 Added the description of a new valve to

[FS 96-021] containment penetration No. 24.

Table 5.3-2, 9.4.1.2, 9.4.3.2, Tables 9.4-2, Updated the description of the Unit 1 chilled 9.4-5, & 9.9-2, Figure 9.9-1, Table 10.3-4, water system to reflect equipment replacement Figure 10.3-11 and changing the systems source of cooling

[FS 98-030] water.

5.4.1.2 Incorporated a description of the revised

[FS 97-009] method of calculating core stored energy.

6.2.2.2.4 Incorporated modifications to the safety

[FS 99-029] injection system.

6.2.3.12, 6.2.3.13 Added a description of the portable passive

[FS 99-020] autocatalytic recombiner and its use.

Table 6.2-6, Table 6.3-2, & 14.5.5.2 Improved consistency with the Technical

[FS 96-030] Specifications description of safety injection and recirculation spray loop leakage limits.

Figures 6.2-1 & 6.2-2 Incorporated modifications to the Unit 2 safety

[FS 99-005] injection system.

6.3.1.3 Corrected typographical omission of a passage

[FS 98-043] of recirculation spray pumps cylindrical suction screens.

6.3.1.5.2 Clarified the description of the initial testing of

[FS 98-026] the recirculation spray system.

7.1, 7.1.1, 7.1.2, 7.2 Refs, 7.2.2.1.1, 7.2.2.1.4, Incorporated technical and editorial corrections 7.2.2.1.6, 7.2.2.4, 7.2.3.3, 7.2 RefDwgs, and clarifications resulting from the integration Tables 7.2-1 & 7.2-3, Figures 7.2-6, & 7.2-8 review of the reactor protection system.

through 7.2-11, 7.5.1, 7.5.1.2, 7.5.1.3, 7.5.1.4.1, 7.5.1.4.2, 7.5.2.2, 7.5.2.3.2, 7.5.3.5, Tables 7.5-1 & 7.5-2, Figures 7.5-1, 7.5-2, 7.5-4, & 7.7-1, 10.3.5.3, Table 13.1-1

[FS 98-048]

Revision 52Updated Online 09/30/20 SPS UFSAR 61 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

7.3.2.6, 8.1, 9.2, 9.4, 9.4.4.5, 9.5, 9.9, Incorporated editorial changes and corrections 9A.3.2.2.1, 9C.1, 9C.1.1, 10.3.1, 10.3.1.2, to typographical errors.

10.3.2, 10.3.4, 10.3.5, 10.3.5.3, 10.3.9, 11.2.3.2, & Table 11.2-11

[FS 99-015]

7.4.3.2 Added new type of cable to the description of

[FS 97-030] the source range nuclear instrument channels.

8.4, 8.5 Incorporated technical and editorial corrections

[FS 99-010] and clarifications resulting from the integration review of the emergency power system.

8.4.4, 8.4.5 Added descriptions of concurrent power

[FS 98-029] supplies to the new Unit 1 main control room Hathaway annunciator.

8.4.4, 8.4.5 Adds a description of the concurrent electrical

[FS 99-009] supplies to the main control room Hathaway annunciators.

8.5 Clarified the EDG start/load acceptance time

[FS 98-031] and power rating.

9.1.2.4, 9.1.2.4.1, 9.1.2.4.2, 9.1.2.4.3 Clarified the description of operation of the

[FS 96-050] reactor makeup control.

9.1.2.6.22 Correct the description of chemical and volume

[FS 97-003] control system piping operation an inspection.

Table 9.1-6 & 14.4.2.1 Revised the description of the volume control

[FS 98-046] tank rupture accident analysis.

9.2 & 10.3 Identified equipment described in the UFSAR

[FS 93-22] that is installed but no longer used.

9.3.3.1 Removed non-combustible from the

[FS 98-017] description of the radiant energy shield between the RHR pump motors.

9.4.1.1, 9.4.3.1, 9.4.3.2, 9.4.4.1, 9.4.4.3, Incorporate changes to the description and 9.4.4.5, 9.4.5, Table 9.4-2 operation of the component cooling system.

[FS 97-006]

9.4.3.1 Revises the component cooling water

[FS 98-002] chemistry chromate concentration and pH limits.

Revision 52Updated Online 09/30/20 SPS UFSAR 62 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.4.3.2 Incorporated a revised description of the

[FS 96-008] modified chiller alarms.

9.4.3.4 Added a description of the charging pump seal

[FS 97-018] cooling system modification to a once-through cooling system.

9.4.4.1 Removed the description of automatic closure

[FS 96-025] of the primary drain cooler component cooling return line.

Table 9.4-8 Deleted the table description of the condensate

[FS 97-023] makeup line check valve.

9.5.1, 9.12.5.5, 9.12.9.1, 9.12.9.2, 9.12.9.3, Updated the description of spent fuel handling Table 9.12-1 and the requirements for cask handling in and

[FS 96-012] around the spent fuel pool.

9.5.3.4 Deleted the reference to an assumed value for

[FS 97-016] fuel assembly offload rate.

Table 9.5-3 Added description that power to the spent fuel

[FS 97-029] pool cooling pumps is supplied from emergency buses.

9.9 & 9.10.4.17 Provided grammatical and editorial corrections.

[FS 98-041]

9.9.1.3, 9.10.4.13, 10.3.1.5, 10.3.5.1, 10.3.5.2, Incorporated technical and editorial corrections 10.3.5.3, 10.3.5.4, Table 13.5-2, 14B.5.1.7, and clarifications resulting from the integration Figure 14B-20 review of the Auxiliary Feedwater System.

[FS 98-037]

9.9.2 Added the description of a temporary service

[FS 98-018] water supply path to the component cooling heat exchangers. [10 CFR 50.90 License Amendment]

9.12.3.4, 11.3.4.1, 11.3 References Incorporated the exemption form criticality

[FS 97-042] monitoring in the fuel storage and handling areas. [10 CFR 70.14 Exemption]

9.12.4 & App. 9B.1 Enhanced the description of heavy loads and

[FS 97-002] their handling.

9.12.5.4 Revised the refueling reassembly sequence to

[FS 97-022] reflect current practice.

Revision 52Updated Online 09/30/20 SPS UFSAR 63 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.12.5.4 Improved the refueling procedure reassembly

[FS 98-040] sequence.

9.12.9, 9.12.9.2, 9.12.9.3 Incorporated technical and editorial corrections

[FS 99-030] and clarifications resulting from the integration review of the Surry ISFSI.

9A.1, 9A.2, 9A.3.1.2, 9A.3.1.3.2, 9A.3.1.4, Revised the fuel assembly drop discussions 9A.3.1.5, 14.4.1.3.2, 14.4.1.3.2.1, 14.4.1.3.2.2, using a 42 inch drop in lieu of a 24 inch drop 14.4.1.3.2.3, Table 14.4-3 and corrected typographical errors.

[FS 97-017]

9B.2.4.4 Added the SFP transfer canal gate lift rig to the

[FS 97-001] list of special lifting devices.

9C.1, 10.3.4.2, 10.3.4.3 Incorporated technical and editorial corrections

[FS 99-014] and clarifications resulting from the integration review of the circulating water system.

10.3.1.2 Added a description of the new condensate

[FS 94-040] return divert line to the steam generator blowdown heat exchangers.

10.3.1.4 Updated the description of the secondary plant

[FS 98-036] chemistry monitoring and control.

10.3.5.1 Removed extraneous detail from the

[FS 95-017] description of the steam generator feedwater pumps.

10.3.7.3, 10.3.7.4 Corrected the description of the function and

[FS 96-058] testing of the dc motor-driven oil pump.

10.3.12 Clarified the description of the main steam trip

[FS 97-021] valve Appendix R solenoid operated valves.

11.2.3, 11.2.3.1.8, Figure 11.2-4 Revised the description of the RF liquid waste

[FS 97-041] reverse osmosis system.

11.2.3.1.7, 11.2.4.1.4, Table 11.2-1 Added a description of the new RF liquid waste

[FS 96-039] reverse osmosis system and revised liquid waste handling descriptions.

11.2.3.1.8, Figure 11.2-4 Clarified the operation of the liquid waste

[FS 99-017] reverse osmosis and demineralizer system.

11.2.5.3.4 Incorporated a revised description of the

[FS 95-036] modified waste gas decay tank oxygen analyzer.

Revision 52Updated Online 09/30/20 SPS UFSAR 64 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

11.3.4.3 Corrected the nominal counting rates for

[FS 96-007] limiting isotopes of the containment gas monitors.

11.3.5.1, 11.3.5.3, 11.3.5.5, 11.3.5.6, 11.3.5.7, Incorporated changes to the Radiological 11.3.5.9 Environmental Monitoring Program

[FS 96-033]

12.2.2.3, 12.2 References Revised reactor operator training program

[FS 97-045] references.

12.7 Incorporated revised security plan references.

[FS 97-014]

14.2.6, 14.2.6.1, 14.2.6.1.1, 14.2.6.1.2, Revised the startup on an inactive loop accident 14.2.6.2, 14.2.6.2.1, 14.2.6.2.2, 14.2.6.2.3, analysis description.

14.2.6.2.4, 14.2.6.2.5, & 14.2.6.3

[FS 95-041]

14.2.11, 14.3.2, 14B.4.2, 14B.6, 14B.6.1, Augmented the description of effects of piping 14B.6.2, 14B Refs system breaks outside containment with a

[FS 99-032] transient analysis of a high-energy line break in the main steam valve house.

14.3.2 Revised wording to clarify the main steam pipe

[FS 96-044] break description.

14.5.5.3, 14.5 Refs Incorporated the results of a sensitivity analysis

[FS 99-036] performed to evaluate acceptable quantities of emergency core cooling system in conjunction with potentially unfiltered exhaust from the Auxiliary Building.

15.5.1.8 Revised the description of containment

[FS 96-051] electrical penetrations to address variations between manufacturers.

16, 16.1, 16.2, 16.2.1, 16.2.1.1, 16.2.1.2, Relocated requirements for plant operation and 16.2.2, 16.2.2.1, 16.2.2.2, 16.2.2.3, surveillance of systems to the Technical Tables 16.2-1, 16.2-2, & 16.2-3 Requirements Manual (TRM). Explicitly

[FS 99-008] incorporated the TRM into the UFSAR.

17.2.2.5 Updated the qualification requirements for

[FS 98-049] Oversight personnel.

17.2.16.2 Incorporated a title change.

[FS 98-051]

Revision 52Updated Online 09/30/20 SPS UFSAR 65 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3109/01/99 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 17.2-0 Revised the description to indicate the both

[FS 98-038] Innsbrook record vaults meet ANSI requirements.

Revision 3009/01/98 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

1.4, 6.1, 6.2, 6.3.1.5, 7.5.3.5, Tables 5.2-1&2, Incorporated technical and editorial corrections Tables 5.4-18, 19, & 20, Tables 6.2-2, 3, 4, 5, 6, and clarifications related to the Safety Injection 10, 11, 12, &13, Figs. 6.1-1 & 6.2-2 System.

[FS 98-015]

1.4.59, 5.3.3, 6.2.3, 6.3.1, 7.5.2.2, 11.3.3.10, Incorporated technical and editorial corrections Tables 6.3-1 & 3, Figs. 6.3-2, 3, & 5 and clarifications related to the Recirculation

[FS 98-019] Spray System.

2.2.1.1, Table 2.2-7, 2.5.3.2, 6.1, 6.2.2.1.2, Corrected references, typographical errors, and Table 6.2-1, 6.2.3.12.1, 6.2.4.1.4, 6.2 verb tense; clarified an abbreviated term and References, 7.4.3.6, Figure 7.5-1, 8.3, 9.6, 9.8, illegible text; and corrected format of numbers, 9.10, 9B.2.1, 9B.2.4.1, 9B.2.4.4, 9B.2.4.7, 9C, upper/lower case usage, and text lists.

11.2, Tables 11A-6, 7,9 & 10, Table 14.3-15, Table 14.5-11, 15.5.1.8 & Table 16.2-2

[FS 98-032]

3.3.3.2.2, 3.5, App. 9A & Tables 3.3-1 & Increased the maximum fuel enrichment from 9.12-1 4.1 to 4.3 weight percent U-235.

[FS 97-043] [10 CFR 50.90 License Amendment]

4.2.2.3.2 Added a description of the removal of the

[FS 98-024] steam generator channel head drain lines.

5.3.1 & 9.13 Revised description of auxiliary ventilation and

[FS 96-061] containment ventilation systems to reflect changes in these systems design and operation.

5.4 & Tables 5.4-17, 5.4-18, 5.4-19, 5.4-20, Removed Containment concrete floor plugs 6.2-11, 6.2-12 & 6.2-13 and the Pressurizer cubicle roof plug.

[FS 97-040]

6.2.2.1.1 & Table 6.2-2 Updated the description of the Safety Injection

[FS 96-047] control board indication.

6.2.2.1.3 Changed to state that pressure-relieving devices

[FS 96-027] discharge to the liquid waste disposal system.

Revision 52Updated Online 09/30/20 SPS UFSAR 66 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3009/01/98 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

6.2.2.2.1 Clarified the tanks to which the accumulators

[FS 97-039] may be drained.

6.2.2.2.4 & 6.2 References Revised description of safety injection valves

[FS 96-040] MOV-1890A/B and MOV-2890A/B to reflect addition of pressure equalization line. Added Reference to NRC Generic Letter 95-07.

6.2.3.3 Changed containment spray and minimum

[FS 98-007] recirculation spray pH ranges.

6.2.3.10, 6.2.4.1.4, 6.3.1.4, 15.5.1.3, 15.5.1.12 Revised the description of the Containment

& Figure 15.5-1 ground water control equipment, ground water

[FS 97-007] protection methods, and liquid level alarms.

6.2.3.12 Changed post-LOCA containment hydrogen

[FS 98-009] concentration for new initial conditions.

6.2.3.12.1 Revised valve stroke time for isolation of the

[FS 96-052] volume control tank.

6.2.4.1.3, 6.2.4.1.4 Changed to describe SI system testing as a

[FS 96-046] series of tests during refueling, and to state that accumulator discharge check valves are tested during refueling.

6.3.1.2.1 Removed the statement that sodium hydroxide

[FS 97-004] solution was only present in the containment spray system during system operation.

6.3.1.4, Tables 6.2-12 & 13 Revised description of NPSH to the

[FS 98-021] recirculation spray pumps to include impact several minor phenomena with impact on post-LOCA sump level.

7.2.3.2.7 Clarified the description of the AMSAC C-20

[FS 98-010] setpoint.

8.6 Clarified preventive maintenance program

[FS 93-33] requirements by deleting the statement which implies that insulation testing is performed on all electrical equipment.

9.9.1.2 & 9.9.3 Updated the description of Emergency Service

[FS 96-011] Water Pump, 1-SW-P-1A, to indicate the removal of the electric motor drive.

Revision 52Updated Online 09/30/20 SPS UFSAR 67 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3009/01/98 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.9.1.3 & 9.10.4.18 Clarified the description of actions taken prior

[FS 96-055] to the arrival of a hurricane onsite and corrected the classification of the circulating water valves as safety related.

9.9.2 & Table 2.1-4 Updated the description of service water

[FS 96-036] chemical treatment and updated the list of onsite chemicals.

9.10.4.16 Updated the description of Emergency Service

[FS 98-025] Water Pump, 1-SW-P-1A, to indicate the removal of the electric motor drive.

10.3.1.2 Removed the statement that the Main Steam

[FS 98-013] Safety Valves temperature flow probes are required for compliance with Regulatory Guide 1.97.

10.3.5.3, 14.2.11.1.3 Relocated the stated numerical value of

[FS 96-041] auxiliary feedwater (AFW) flowrate from the section describing the AFW system to the section where event analysis is described.

11.2.2, 11.2.5, & Tbl. 11.2-11 Modified descriptions of process vent system

[FS 97-035] to remove implied wind speed limitations for system operation.

12.1.1.2.1, 17.2, & KWI Updated Station Manager title to Site Vice

[FS 98-003] President and Assistant Station Managers titles to Manager-Station O&M and Manager-Station S&L. [10 CFR 50.90 License Amendment]

14.2.7 Updated the description of the feedwater

[FS 98-11] temperature reduction event.

14.3.1 Revised the steam generator tube rupture

[FS 97-034] accident analysis to reflect the evaluation of the effect of steam generator tube bundle uncovery on radioiodine release.

17.2.1.2.B.1 Identified the Site Vice President as the station

[FS 98-028] position fulfilling the Plant Manager position identified in the ISFSI Technical Specifications.

Revision 52Updated Online 09/30/20 SPS UFSAR 68 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 3009/01/98 (continued)

Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

17.2.3 Revised to reflect replacement of A/E

[FS 98-016] Instruction Manual with an Engineering Standard.

Revision 293/1998 Section Changes 17.2, 17.2.1.2, 17.2.2.1, 17.2.3, 17.2.4, 17.2.5, Deleted reference to Nuclear Operations Figure 17.2.1-1, and Table 17.2-0 Department Standards and replaced with

[FS 97-026] Nuclear Business Unit Standard. Added position of Project Manager (Configuration Management).

17.2.1.1 and 17.2.1.2 Clarified organizational position descriptions

[FS 98-004] by noting responsibilities for the ISFSI as they already exist.

17.2.1.2, Figure 17.2.1-2, and Figure 17.2.1-3 Deleted the position of Supervisor

[FS 98-005] Administrative Services in the Nuclear Management organization and assigned duties and responsibilities to other positions.

17.2.2.6 and 17.2.2.8 Clarified Quality Inspection Coordinator

[FS 97-038] qualifications.

17.2.17, Tables 17.2-2 and 17.2-3 Added Generic Letter 88-18 commitment

[FS 97-048] regarding storage of quality assurance records on optical disk media.

Table 17.2.0 Added provision for storage of quality

[FS 96-049] assurance records in an approved offsite facility.

Table 17.2-0 Provided an additional alternative to

[FS 97-044] ANSI/ANS 3.1.

Tables 17.2-2 and 17.2-3 Clarified the description of onsite and offsite

[FS 98-012] nuclear safety review committees.

Revision 52Updated Online 09/30/20 SPS UFSAR 69 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 2802/11/98 Section Changes Foreword Updated to reflect recent NRC initiatives regarding UFSAR submittal requirements, and adequacy and consistency of design basis information; and to note Virginia Powers adoption of electronic methods to enhance UFSAR maintenance, and UFSAR distribution in both hardcopy and electronic media.

5.5 Modified leak rate testing discussion to include

[FS 95-039] 10 CFR 50, Appendix J, Option B performance-based leak rate testing rulemaking.

7.5.1.1 Changed low-low pressurizer SI manual block

[FS 96-045] setpoint from 2000 psia to 2000 psig.

9.6

  • Added introduction and revised subsection

[FS 95-043] headings

  • Clarified the 3-hour requirement for PASS samples
  • Deleted references to sampling abandoned flash evaporators
  • Noted that condenser tube leakage monitoring may be by means other than chlorides monitoring
  • Deleted superfluous HRSS equipment brand names
  • Clarified operation of the HRSS waste tank
  • Clarified remote indication of HRSS parameters
  • Clarified SS valve isolation on an SI signal
  • Clarified environmental qualification of HRSS containment sump pump 9.10 & 17.2 Deleted references to the Training Center

[FS 96-042] records vault and associated features.

9.12 Updated to reflect current refueling practices.

[FS96-022 R1]

14.5.2 Updated to reflect reanalysis of small break

[FS 96-057] loss of coolant accident (SBLOCA), including Tables 14.5-14 thru 16, and Figures 14.5-36, and 38 thru 68.

Revision 52Updated Online 09/30/20 SPS UFSAR 70 Click on Change Package Number Highlighted in Red to View Change Request.

Revision 2802/11/98 (continued)

Section Changes Table 17.2-3 Corrected typos.

[FS 97-037]

All (no change bars)

  • Consolidated 7 volumes to 4 volumes

[FS 97-012] [FS 97-013]

  • Referenced Station Drawings previously included in UFSAR; inserted simplified diagrams
  • Removed notations associated with previously deleted material and renumbered sequentially
  • Renumbered previously inserted items that had suffixes (e.g., 4A, 4B)
  • Applied consistent typeface and page layouts
  • Improved consistency of measurement notation (e.g., time, mass, velocity),

including abbreviations

Volume I Assignment Sheet General Table of Contents Revision 52Updated Online 09/30/20 SPS UFSAR TOC-i Surry Power Station Updated Final Safety Analysis Report Table of Contents Section Title Page

..................................................................... 1-1 VOLUME I Assignment Sheet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . TOC-i General Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . TOC-i Foreword . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 List of Effective Pages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . LEP-1 CHAPTER 1 INTRODUCTION AND

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.2 Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.2-1 1.3 Comparison with other Stations . . . . . . . . . . . . . . . . . . . . . . . . . 1.3-1 1.4 Compliance with Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.4-1 1.5 Common Facilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.5-1 1.6 Research and Development Requirements. . . . . . . . . . . . . . . . . 1.6-1 CHAPTER 2 SITE CHARACTERISTICS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-1 2.1 Geography, Demography and Potential External Hazards. . . . . 2.1-1 2.2 Meteorology and Climatology . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2-1 2.3 Hydrology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1 2.4 Geology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.5 Seismology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 CHAPTER 3 REACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1 3.1 General . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1 3.2 Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-1 3.3 Nuclear Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-1 3.4 Thermal/Hydraulic Design and Evaluation . . . . . . . . . . . . . . . . 3.4-1 3.5 Mechanical Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-1 3.6 Tests and Inspections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-1

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Section Title Page CHAPTER 4 REACTOR COOLANT SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1 4.1 Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1 4.2 System Design and Operation . . . . . . . . . . . . . . . . . . . . . . . . . . 4.2-1 4.3 System Design Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-1 4.4 Tests and Inspections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.4-1 VOLUME II CHAPTER 5 CONTAINMENT SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1-1 5.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1-1 5.2 Containment Isolation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.2-1 5.3 Containment Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.3-1 5.4 Containment Design Evaluation. . . . . . . . . . . . . . . . . . . . . . . . . 5.4-1 5.5 Containment Tests and Inspections . . . . . . . . . . . . . . . . . . . . . . 5.5-1 CHAPTER 6 ENGINEERED SAFEGUARDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1-1 6.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1-1 6.2 Safety Injection System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.2-1 6.3 Consequence-Limiting Safeguards. . . . . . . . . . . . . . . . . . . . . . . 6.3-1 CHAPTER 7 INSTRUMENTATION AND CONTROL . . . . . . . . . . . . . . . . . . . . . 7.1-1 7.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.1-1 7.2 Reactor Protection System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.2-1 7.3 Reactor Control System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.3-1 7.4 Nuclear Instrumentation System . . . . . . . . . . . . . . . . . . . . . . . . 7.4-1 7.5 Engineered Safeguards . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.5-1 7.6 Incore Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.6-1 7.7 Operating Control Stations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.7-1 7.8 Computer System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.8-1 7.9 Inadequate Core Cooling (ICC) System. . . . . . . . . . . . . . . . . . . 7.9-1

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Section Title Page 7.10 Ex-Core Neutron Flux Monitor System . . . . . . . . . . . . . . . . . . . 7.10-1 7.11 Level Instrumentation to Prevent Loss of Shutdown Cooling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.11-1 CHAPTER 8 ELECTRICAL SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.1-1 8.1 General Description and Summary . . . . . . . . . . . . . . . . . . . . . . 8.1-1 8.2 Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.2-1 8.3 System Interconnections. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.3-1 8.4 Station Service Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.4-1 8.5 Emergency Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.5-1 8.6 Tests and Inspections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.6-1 VOLUME III CHAPTER 9 AUXILIARY AND EMERGENCY SYSTEMS . . . . . . . . . . . . . . . . 9.1-1 9.1 Chemical and Volume Control System . . . . . . . . . . . . . . . . . . . 9.1-1 9.2 Boron Recovery System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.2-1 9.3 Residual Heat Removal System . . . . . . . . . . . . . . . . . . . . . . . . . 9.3-1 9.4 Component Cooling Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.4-1 9.5 Fuel Pool Cooling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.5-1 9.6 Sampling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.6-1 9.7 Vent and Drain System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.7-1 9.8 Compressed Air System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.8-1 9.9 Service Water System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.9-1 9.10 Fire Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.10-1 9.11 Water Supply and Treatment Systems . . . . . . . . . . . . . . . . . . . . 9.11-1 9.12 Fuel Handling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.12-1 9.13 Auxiliary Ventilation Systems . . . . . . . . . . . . . . . . . . . . . . . . . . 9.13-1 9.14 Decontamination Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.14-1

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Section Title Page Appendix 9A High-Density Spent-Fuel Storage Rack Design. . . . . . 9A-i 9A.1 Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-1 9A.2 Storage Rack Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-1 9A.3 Storage Rack Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-3 Appendix 9B Movement of Heavy Loads . . . . . . . . . . . . . . . . . . . . . 9B-i 9B.1 Heavy Loads Over Spent Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-1 9B.2 Heavy Loads Over Safe-Shutdown Equipment . . . . . . . . . . . . . . 9B-4 Appendix 9C Flood Control System . . . . . . . . . . . . . . . . . . . . . . . . . 9C-i 9C.1 Design Basis Flooding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9C-1 9C.2 Individual Plant Examination Internal Flooding . . . . . . . . . . . . . 9C-4 CHAPTER 10 STEAM AND POWER CONVERSION . . . . . . . . . . . . . . . . . . . . . . 10.1-1 10.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.1-1 10.2 Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.2-1 10.3 System Design and Operation . . . . . . . . . . . . . . . . . . . . . . . . . . 10.3-1 CHAPTER 11 RADIOACTIVE WASTES AND RADIATION PROTECTION . . 11.1-1 11.1 General Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.1-1 11.2 Radioactive Waste Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.2-1 11.3 Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.3-1 Appendix 11A Radiation Exposure Evaluation for Expected Radioactive Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-i 11A.1 Analytical Basis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-1 11A.2 Input Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-1 11A.3 Plant and Animal Census . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-3 11A.4 Dose Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-3 CHAPTER 12 CONDUCT OF OPERATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.1-1 12.1 Organizational Structure of Virginia Electric and Power Company 12.1-1 12.2 Training Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.2-1

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Section Title Page 12.3 Emergency Planning. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.3-1 12.4 Review and Audit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.4-1 12.5 Plant Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.5-1 12.6 Plant Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.6-1 12.7 Industrial Security . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.7-1 12.8 Shift Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.8-1 CHAPTER 13 INITIAL TESTS AND OPERATION . . . . . . . . . . . . . . . . . . . . . . . . 13.1-1 13.1 Tests Prior to Initial Reactor Fueling . . . . . . . . . . . . . . . . . . . . . 13.1-1 13.2 Final Station Preparation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.2-1 13.3 Initial Testing in the Operating Reactor . . . . . . . . . . . . . . . . . . . 13.3-1 13.4 Operating Restrictions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.4-1 13.5 Steam Generator Postrepair Start-Up Test Program . . . . . . . . . 13.5-1 VOLUME IV CHAPTER 14 SAFETY ANALYSIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.1-1 14.1 General . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.1-1 14.2 Core and Coolant Boundary Protection Analysis. . . . . . . . . . . . 14.2-1 14.3 Standby Safeguards Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.3-1 14.4 General Station Accident Analysis. . . . . . . . . . . . . . . . . . . . . . . 14.4-1 14.5 Loss-of-Coolant Accident . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.5-1 Appendix 14A Radiation Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14A-i 14A.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14A-1 14A.2 Total Activity in the Core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14A-1 14A.3 Activity in the Fuel Rod Gap. . . . . . . . . . . . . . . . . . . . . . . . . . . . 14A-1 Appendix 14B Effects of Piping System Breaks Outside Containment 14B-i 14B.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-1 14B.2 Criteria for Pipe Breaks and Methods for Analysis . . . . . . . . . . . 14B-2

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Section Title Page 14B.3 High-Energy Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-12 14B.4 Plant Shutdown and Safety-Related Equipment . . . . . . . . . . . . . 14B-13 14B.5 Effects of Pipe Breaks and Cracks. . . . . . . . . . . . . . . . . . . . . . . . 14B-14 14B.6 Transient Analysis of a High-Energy Line Break in the Main Steam Valve House . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-29 14B.7 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-30 CHAPTER 15 STRUCTURES AND CONSTRUCTION . . . . . . . . . . . . . . . . . . . . . 15.1-1 15.1 Structures and Machinery Arrangement. . . . . . . . . . . . . . . . . . . 15.1-1 15.2 Structural Design Criteria. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.2-1 15.3 Material. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.3-1 15.4 Construction Procedures and Practices . . . . . . . . . . . . . . . . . . . 15.4-1 15.5 Specific Containment Structural Designs. . . . . . . . . . . . . . . . . . 15.5-1 15.6 Other Class I Structures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.6-1 15.7 Masonry Walls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.7-1 Appendix 15A Seismic Design for the Nuclear Steam Supply System and Miscellaneous Components. . . . . . . . . . . . . . . . . . 15A-i 15A.1 General Seismic Design Criteria for the Nuclear Steam Supply System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-1 15A.2 Seismic Design Criteria for Piping, Vessels, Supports and Reactor Vessel Internals . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-1 15A.3 General Analytical Procedure for Seismic Design . . . . . . . . . . . 15A-4 15A.4 Movement of Reactor Coolant System Components. . . . . . . . . . 15A-22 15A.5 Tests to Demonstrate the Conservatism of the Limit Curves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-23 15A.6 Reactor Coolant Loop (RCL) PIPING REANALYSIS SUBSEQUENT TO LEAK BEFORE BREAK AND SNUBBER ELIMINATION15A-26 CHAPTER 16 TECHNICAL SPECIFICATIONS AND TECHNICAL REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . 16.1-1 16.1 Technical Specifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16.1-1

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Section Title Page 16.2 Technical Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16.2-1 CHAPTER 17 QUALITY ASSURANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17-1 CHAPTER 18 PROGRAMS AND ACTIVITIES THAT MANAGE THE EFFECTS OF AGING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-1 18.1 New Aging Management Activities . . . . . . . . . . . . . . . . . . . . . . 18-1 18.2 Existing Aging Management Activities . . . . . . . . . . . . . . . . . . . 18-5 18.3 Time-Limited Aging Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . 18-23 18.4 TLAA Supporting Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-32 18.5 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-34

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Revision 52Updated Online 09/30/20 SPS UFSAR 1 FOREWORD In the May 9, 1980, edition of the Federal Register (45 FR 30614), the NRC published a Final Rule requiring all licensed reactors to periodically update their Final Safety Analysis Reports. The purpose of the Rule was to establish baseline reference documents to be used in recurring safety analyses by licensees, the NRC, or other interested parties.

The Supplementary Information section of the Final Rule notice stated that submittal of an updated FSAR does not constitute a licensing action, but is only intended to provide information. The NRC Staff may review the material submitted, but does not intend to formally approve it. The NRC intends to use the updated FSAR in the future for appropriate applications such as reporting of deviations from conditions stated in the UFSAR.

The Rule became effective July 22, 1980, and established the following basic requirements for Vepcos nuclear power stations:

  • A complete Updated FSAR (UFSAR) was required as the initial submittal
  • The UFSAR was to reflect information and analyses submitted to the NRC by Vepco, or prepared by Vepco pursuant to NRC requirements, since submission of the original FSAR (or, as appropriate, the last UFSAR)
  • NOTE: The Supplementary Information section of the Final Rule notice clarifies this requirement by stating that no analyses other than those already prepared or submitted pursuant to NRC requirements are required because of the Rule: however, FSAR analyses that are known to be nonconservative based on new analyses must be updated. Other new analyses not previously included in the FSAR may be incorporated in the UFSAR at the option of the licensee. Furthermore, specialized studies provided in the original FSAR (e.g., seismology, meteorology) should include the latest information developed in response to NRC requirements when these studies are transferred to the UFSAR, and program type material referenced by the UFSAR (e.g., security plan, emergency plan, QA Program) should be referenced accurately. In addition, the level of detail in the UFSAR should be at least the same as but not necessarily greater than that provided in the original FSAR. Information on design changes should not be included until the changes are approved for use and operable.
  • The initial UFSAR was due no later than July 22, 1982
  • The initial UFSAR was required to be up-to-date as of a maximum of six months prior to the date of filing (January 31, 1982, was chosen by Vepco as the cutoff date)
  • Subsequent updates are required at least annually and must reflect changes made up to a maximum of six months prior to the date of filing

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  • One original and 12 copies of the initial UFSAR and subsequent updates are required to be submitted to the NRC
  • The updates are required to be certified by a duly authorized officer of Vepco
  • The initial UFSAR should be a clean document without change bars and revision numbers. The subsequent annual revisions should include change indicators and page change identification In response to the foregoing FSAR update requirements, Vepco and NUS Corporation executed an Agreement for FSAR update services in April 1981, and NUS began work on the project immediately. The project was accomplished in four basic phases:
1. Document Retrieval
2. Change Package Development
3. FSAR Revision
4. Printing
  • During the initial document retrieval phase in the Spring of 1981, NUS engineers researched the licensing correspondence files at Vepco offices in Richmond and the design change files at the plant sites. All documents potentially affecting the FSAR were copied and taken to the NUS home office.

Following the initial document review phase, NUS engineers periodically visited Richmond and the plant sites to acquire newly developed information. NUS was also placed on the distribution list for Vepco/NRC correspondence.

The document retrieval phase continued until early 1982, at which time sufficient information was available to document changes up to the January 31, 1982, cutoff date.

  • The documentation retrieved during the first phase was reviewed in detail during the second phase to determine the particular two-digit section or sections of the FSAR that should be revised, i.e., 1.1, 1.2, 1.3, etc. Copies of the document (or of the particular pages of the document that were of interest) were placed in separate files corresponding to the two-digit sections. These files were defined as change packages. Development of the change packages continued in parallel with the document retrieval phase, with new information being reviewed and assigned to appropriate change packages. The final change packages became a work product delivered to Vepco on conclusion of the update effort and are available for tracing the sources of changes to the original FSARs
  • After development of the initial change packages the material filed therein was used in the third phase of the project to make the actual FSAR revisions. The revision process continued in parallel with the continuing development of the change packages.

Revision 52Updated Online 09/30/20 SPS UFSAR 3 The revision phase for most FSAR chapters included two cycles of Vepco review and comment. These comments became part of the change packages and were used in the development of the final draft UFSAR.

  • Vepco reviewed and approved the final draft chapters of the UFSARs for printing. The printer prepared approximately 125 sets of the UFSARs. NUS delivered one original and 12 copies of the UFSAR directly to the NRC on July 20, 1982, for Surry and July 22, 1982, for North Anna. The original UFSARs were transmitted under cover letter supplied to NUS by Vepco (see the attachment to this foreword). The remaining copies were shipped to Richmond and the plant sites.

The following work products were also delivered to Vepco by NUS and are available for use in producing subsequent annual updates:

  • Annotated FSARs (2 copies)
  • Final Change Packages (2 sets)
  • Plant Drawing Indexes
  • Key Word Indexes
  • IBM Displaywriter Floppy Discs (2 sets each of the FSAR, Annotated FSAR, and Key Word Index)
  • Update Procedures
  • Introductory Volumes to the FSARs including this foreword, a list of effective pages, the key word indexes, the plant drawing indexes and a record of changes Further 10 CFR 50.71(e) rulemaking pertaining to UFSAR requirements for nuclear power stations was promulgated as recently as July 29, 1996 [61 FR 39278]. In particular, the annual revision requirement has been relaxed to six months after each refueling outage provided the interval between successive updates does not exceed 24 months.

The NRC issued a letter to licensees dated October 9, 1996, entitled Request for Information Pursuant to 10 CFR 50.54(f) Regarding Adequacy and Availability of Design Basis Information. The letter required submittal of information that will provide the NRC added confidence and assurance that Virginia Electric and Power Companys nuclear plants are operated and maintained within their design bases and that any deviations are reconciled in a timely manner. The Companys response (Serial No.96-535) dated February 7, 1997, described previously conducted programmatic reviews of the Updated Final Safety Analysis Report (UFSAR). The 1996 UFSAR Project Team examined the existing administrative controls for maintaining UFSAR content and usability. Process enhancements to simplify administrative

Revision 52Updated Online 09/30/20 SPS UFSAR 4 controls, to increase accountability for technical content, and to improve UFSAR accessibility and usability are promoted by conversion to electronic media.

Under separate cover (Serial No.97-108) dated May 23, 1997, Virginia Electric and Power Company notified the NRC about its project to address potential regulatory concerns involving the current design and licensing bases for the Surry and North Anna Power Stations. This project scope exceeds the level of scrutiny normally applied to the current licensing basis through routine surveillance and quality assurance activities. In order to facilitate thorough review, exhaustive validation, and a rigorous corrective action process, the recommended conversion to electronic media was implemented in Revision 28 of the Surry UFSAR. The entire text of the UFSAR was entered into electronic media. The conversion was accomplished by a process of augmenting recent UFSAR revision word processing packages with scanned-in optical character recognition documents for the balance of text, tables, and figures not previously stored electronically. A 100-percent word-for-word proofing was conducted by comparing a printed version of the entire electronic document with current controlled distribution copies. Thus, the electronic UFSAR was conveyed into service as the quality assurance document of record without introducing any substantive, technical, or non-editorial changes.

Revision 52Updated Online 09/30/20 SPS UFSAR 5 Revision 52Updated Online 09/30/20 SPS UFSAR 6 Intentionally Blank

Revision 52Updated Online 09/30/20 SPS UFSAR LEP-1 LIST OF EFFECTIVE PAGES VOLUME I General Table of Contents (Repeated in each volume)

First Page Last Page Revision TOC-i TOC-viii Revision 52Updated Online 09/30/20 Foreword First Page Last Page Revision 1 6 Revision 52Updated Online 09/30/20 List of Effective Pages First Page Last Page Revision LEP-1 LEP-6 Revision 52Updated Online 09/30/20 Chapter 1 First Page Last Page Revision 1-i 1-vi Revision 52Updated Online 09/30/20 1.1-1 1.1-4 Revision 52Updated Online 09/30/20 1.2-1 1.2-6 Revision 52Updated Online 09/30/20 1.3-1 1.3-10 Revision 52Updated Online 09/30/20 1.4-1 1.4-40 Revision 52Updated Online 09/30/20 1.5-1 1.5-2 Revision 52Updated Online 09/30/20 1.6-1 1.6-8 Revision 52Updated Online 09/30/20 Chapter 2 First Page Last Page Revision 2-i 2-x Revision 52Updated Online 09/30/20 2.1-1 2.1-36 Revision 52Updated Online 09/30/20 2.2-1 2.2-40 Revision 52Updated Online 09/30/20 2.3-1 2.3-30 Revision 52Updated Online 09/30/20 2.4-1 2.4-66 Revision 52Updated Online 09/30/20 2.5-1 2.5-32 Revision 52Updated Online 09/30/20

Revision 52Updated Online 09/30/20 SPS UFSAR LEP-2 LIST OF EFFECTIVE PAGES (CONTINUED)

Chapter 3 First Page Last Page Revision 3-i 3-vi Revision 52Updated Online 09/30/20 3.1-1 3.1-2 Revision 52Updated Online 09/30/20 3.2-1 3.2-12 Revision 52Updated Online 09/30/20 3.3-1 3.3-26 Revision 52Updated Online 09/30/20 3.4-1 3.4-34 Revision 52Updated Online 09/30/20 3.5-1 3.5-58 Revision 52Updated Online 09/30/20 3.6-1 3.6-6 Revision 52Updated Online 09/30/20 Chapter 4 First Page Last Page Revision 4-i 4-vi Revision 52Updated Online 09/30/20 4.1-1 4.1-40 Revision 52Updated Online 09/30/20 4.2-1 4.2-44 Revision 52Updated Online 09/30/20 4.3-1 4.3-22 Revision 52Updated Online 09/30/20 4.4-1 4.4-10 Revision 52Updated Online 09/30/20 VOLUME II Chapter 5 First Page Last Page Revision 5-i 5-iv Revision 52Updated Online 09/30/20 5.1-1 5.1-2 Revision 52Updated Online 09/30/20 5.2-1 5.2-38 Revision 52Updated Online 09/30/20 5.3-1 5.3-20 Revision 52Updated Online 09/30/20 5.4-1 5.4-54 Revision 52Updated Online 09/30/20 5.5-1 5.5-6 Revision 52Updated Online 09/30/20 Chapter 6 First Page Last Page Revision 6-i 6-iv Revision 52Updated Online 09/30/20 6.1-1 6.1-6 Revision 52Updated Online 09/30/20 6.2-1 6.2-58 Revision 52Updated Online 09/30/20 6.3-1 6.3-34 Revision 52Updated Online 09/30/20

Revision 52Updated Online 09/30/20 SPS UFSAR LEP-3 LIST OF EFFECTIVE PAGES (CONTINUED)

Chapter 7 First Page Last Page Revision 7-i 7-vi Revision 52Updated Online 09/30/20 7.1-1 7.1-4 Revision 52Updated Online 09/30/20 7.2-1 7.2-52 Revision 52Updated Online 09/30/20 7.3-1 7.3-16 Revision 52Updated Online 09/30/20 7.4-1 7.4-26 Revision 52Updated Online 09/30/20 7.5-1 7.5-34 Revision 52Updated Online 09/30/20 7.6-1 7.6-6 Revision 52Updated Online 09/30/20 7.7-1 7.7-10 Revision 52Updated Online 09/30/20 7.8-1 7.8-4 Revision 52Updated Online 09/30/20 7.9-1 7.9-4 Revision 52Updated Online 09/30/20 7.10-1 7.10-2 Revision 52Updated Online 09/30/20 7.11-1 7.11-2 Revision 52Updated Online 09/30/20 Chapter 8 First Page Last Page Revision 8-i 8-ii Revision 52Updated Online 09/30/20 8.1-1 8.1-2 Revision 52Updated Online 09/30/20 8.2-1 8.2-4 Revision 52Updated Online 09/30/20 8.3-1 8.3-6 Revision 52Updated Online 09/30/20 8.4-1 8.4-10 Revision 52Updated Online 09/30/20 8.5-1 8.5-10 Revision 52Updated Online 09/30/20 8.6-1 8.6-2 Revision 52Updated Online 09/30/20 VOLUME III Chapter 9 First Page Last Page Revision 9-i 9-xii Revision 52Updated Online 09/30/20 9.1-1 9.1-42 Revision 52Updated Online 09/30/20 9.2-1 9.2-20 Revision 52Updated Online 09/30/20 9.3-1 9.3-10 Revision 52Updated Online 09/30/20 9.4-1 9.4-30 Revision 52Updated Online 09/30/20 9.5-1 9.5-10 Revision 52Updated Online 09/30/20 9.6-1 9.6-16 Revision 52Updated Online 09/30/20 9.7-1 9.7-10 Revision 52Updated Online 09/30/20 9.8-1 9.8-8 Revision 52Updated Online 09/30/20

Revision 52Updated Online 09/30/20 SPS UFSAR LEP-4 LIST OF EFFECTIVE PAGES (CONTINUED)

Chapter 9 (continued)

First Page Last Page Revision 9.9-1 9.9-16 Revision 52Updated Online 09/30/20 9.10-1 9.10-50 Revision 52Updated Online 09/30/20 9.11-1 9.11-6 Revision 52Updated Online 09/30/20 9.12-1 9.12-18 Revision 52Updated Online 09/30/20 9.13-1 9.13-18 Revision 52Updated Online 09/30/20 9.14-1 9.14-6 Revision 52Updated Online 09/30/20 9A-i 9A-ii Revision 52Updated Online 09/30/20 9A-1 9A-22 Revision 52Updated Online 09/30/20 9B-i 9B-ii Revision 52Updated Online 09/30/20 9B-1 9B-16 Revision 52Updated Online 09/30/20 9C-i 9C-ii Revision 52Updated Online 09/30/20 9C-1 9C-6 Revision 52Updated Online 09/30/20 Chapter 10 First Page Last Page Revision 10-i 10-iv Revision 52Updated Online 09/30/20 10.1-1 10.1-2 Revision 52Updated Online 09/30/20 10.2-1 10.2-6 Revision 52Updated Online 09/30/20 10.3-1 10.3-54 Revision 52Updated Online 09/30/20 Chapter 11 First Page Last Page Revision 11-i 11-vi Revision 52Updated Online 09/30/20 11.1-1 11.1-2 Revision 52Updated Online 09/30/20 11.2-1 11.2-40 Revision 52Updated Online 09/30/20 11.3-1 11.3-36 Revision 52Updated Online 09/30/20 11A-i 11A-ii Revision 52Updated Online 09/30/20 11A-1 11A-28 Revision 52Updated Online 09/30/20 Chapter 12 First Page Last Page Revision 12-i 12-ii Revision 52Updated Online 09/30/20 12.1-1 12.1-2 Revision 52Updated Online 09/30/20 12.2-1 12.2-4 Revision 52Updated Online 09/30/20 12.3-1 12.3-2 Revision 52Updated Online 09/30/20

Revision 52Updated Online 09/30/20 SPS UFSAR LEP-5 LIST OF EFFECTIVE PAGES (CONTINUED)

Chapter 12 (continued)

First Page Last Page Revision 12.4-1 12.4-2 Revision 52Updated Online 09/30/20 12.5-1 12.5-2 Revision 52Updated Online 09/30/20 12.6-1 12.6-2 Revision 52Updated Online 09/30/20 12.7-1 12.7-2 Revision 52Updated Online 09/30/20 12.8-1 12.8-2 Revision 52Updated Online 09/30/20 Chapter 13 First Page Last Page Revision 13-i 13-ii Revision 52Updated Online 09/30/20 13.1-1 13.1-12 Revision 52Updated Online 09/30/20 13.2-1 13.2-4 Revision 52Updated Online 09/30/20 13.3-1 13.3-10 Revision 52Updated Online 09/30/20 13.4-1 13.4-4 Revision 52Updated Online 09/30/20 13.5-1 13.5-24 Revision 52Updated Online 09/30/20 VOLUME IV Chapter 14 First Page Last Page Revision 14-i 14-xx Revision 52Updated Online 09/30/20 14.1-1 14.1-6 Revision 52Updated Online 09/30/20 14.2-1 14.2-134 Revision 52Updated Online 09/30/20 14.3-1 14.3-80 Revision 52Updated Online 09/30/20 14.4-1 14.4-20 Revision 52Updated Online 09/30/20 14.5-1 14.5-136 Revision 52Updated Online 09/30/20 14A-i 14A-ii Revision 52Updated Online 09/30/20 14A-1 14A-4 Revision 52Updated Online 09/30/20 14B-i 14B-ii Revision 52Updated Online 09/30/20 14B-1 14B-78 Revision 52Updated Online 09/30/20 Chapter 15 First Page Last Page Revision 15-i 15-viii Revision 52Updated Online 09/30/20 15.1-1 15.1-4 Revision 52Updated Online 09/30/20 15.2-1 15.2-26 Revision 52Updated Online 09/30/20 15.3-1 15.3-2 Revision 52Updated Online 09/30/20

Revision 52Updated Online 09/30/20 SPS UFSAR LEP-6 LIST OF EFFECTIVE PAGES (CONTINUED)

Chapter 15 (continued)

First Page Last Page Revision 15.4-1 15.4-6 Revision 52Updated Online 09/30/20 15.5-1 15.5-70 Revision 52Updated Online 09/30/20 15.6-1 15.6-20 Revision 52Updated Online 09/30/20 15.7-1 15.7-2 Revision 52Updated Online 09/30/20 15A-i 15A-ii Revision 52Updated Online 09/30/20 15A-1 15A-50 Revision 52Updated Online 09/30/20 Chapter 16 First Page Last Page Revision 16-i 16-ii Revision 52Updated Online 09/30/20 16.1-1 16.1-2 Revision 52Updated Online 09/30/20 16.2-1 16.2-2 Revision 52Updated Online 09/30/20 Chapter 17 First Page Last Page Revision 17-1 17-2 Revision 52Updated Online 09/30/20 Chapter 18 First Page Last Page Revision 18-i 18-vi Revision 52Updated Online 09/30/20 18-1 18-40 Revision 52Updated Online 09/30/20

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