ML17033B480
| ML17033B480 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/29/2016 |
| From: | V Sreenivas Plant Licensing Branch II |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| Sreenivas V, NRR/DORL/LPL2-1, 415-2597 | |
| Shared Package | |
| ML17033B477 | List: |
| References | |
| Download: ML17033B480 (114) | |
Text
NORTH ANNA POWER STATIONUPDATED FINAL SAFETY ANALYSIS REPORT Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR 1REVISION
SUMMARY
Revision 52-09/29/16 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.Table 6.4-1[FN-2008-025]Updated Table reflects addition of chemicals for Bearing Cooling System.Table 7.2-2, 7.3.1.2, Table 7.5-3[NAPS-UCR-2016-012]
Updated the uncertainty value for pressurizer pressure protectionTable 6.4-1[NAPS-UCR-2016-016]Updated Table to remove zinc chloride which
is no longer stored on site.Table 15.3-1[NAPS-UCR-2016-017]Modified to replace refe rence to appropriate tables for reactor vessel upflow conversion.
6.3.2.1.1
[NAPS-UCR-2016-018]
Modified to referenc e common figure for accumulator injection following a large break loss of coolant accident.9.5.1.1, Table 9.5-7
[NAPS-UCR-2016-013]
Update reflects engi neering evaluations completed to address fi re code deficiencies for main transformer fire spray system.
5.1.3.1, 5.3, 5.5.1.2, 5.5.1.3.1, 5.5.1.3.5, 5.5.1.3.11, Table 5.2-3, Table 5.5-1, Table 9.3-4, Figure 5.5-1
[NAPS-UCR-2013-010]
Update reflects reactor coolant pump seal
replacement - Unit 2 final configuration.
9.5.1.3.1.8
[NAPS-UCR-2014-029]
Modified to clarify the fire protection system use of coating versus wrap.6.3.3.13, 6.3 References, Table 6.3-8, 15.1.8.1, 15.1.8.4, 15.1 References, 15.3.1, 15.3.1.4, 15.3.1.8 to 15.3.1.14, 15.3.4.2.1, 15.3.3 References, 15.4.1, 15.4.1.6, 15.4.1.1 1 to 15.4.1.20, 15.4.3 References, Table 15.1-2, Tables 15.3-9 to 15.3-29, Table 15.4-22 to 15.4-32, Figures 15.3-97 to 15.3-215, Figures 15.4-54 to 15.4-76
[NAPS-UCR-2016-003]
Update reflects reactor vessel upflow conversion Unit 2.
5.1.3.1, 5.3, 5.5.1.2, 5.5.1.3.1, 5.5.1.3.5, 5.5.1.3.11, Table 5.2-3, Table 5.5-1, Table 9.3-4, Figure 5.5-1, Figure 5.5-2
[NAPS-UCR-2016-010]
Update reflects reactor coolant pump seal replacement - Unit 2 Interim 1A configuration.
Revision 52-09/29/2016 NAPS UFSAR 2 8.1.1, 8.2.1, Figure 8.2-1, Figure 8.2-2
[NAPS-UCR-2015-019]Modified to clarify transmission line number , 573 name changed to Spotsylvania.
Figure 8.2-1, 8.3.1.1.1, 8.3.1.1.2.3
[NAPS-UCR-2013-027]
Update reflects station service bus to emer gency bus cross tie installation.Table 9.3-3
[NAPS-UCR-2014-027]
Update reflects the repl acement of the reactor containment sump pumps.
Figure 10.4-9 (Sheet 1 of 4), (Sheet 3 of 4)
[NAPS-UCR-2015-010]
Update reflects beari ng cooling recirculation modification - Unit 2.4.2.2.2, 4.4.3.1.1, 4.5.2.1.3.2.4, 6.3.3.12, Figure 6.3-15, Figure 6.3-16, Figure 6.3-17, Figure 6.3-18, 15.3.1.1, 15.4.1.1, 15.4.1.2, 15.4.1.3, 15.4.1.4, 15.4.1.15, 15.4.1.6, Table 15.4-1, Table 15.4-2, Table 15.4-3, Table 15.4-4, Table 15.4-5 thru Table 15.4-8, Table 15.4-10, Figure 15.4-1 thru Table 15.4-26
[NAPS-UCR-2015-015]
Update reflects reactor vessel upflow conversion Unit 2.18.1.4, 18.2.19, Table 18-1
[NAPS-UCR-2015-022]
Update reflects closure of commitments 19 (non-EQ cable inspection) and 26 (addresses
fuse holders). Revised to clarify qualification of inspectors as Visual Test (VT).
Figure 9.3-2 (Sheet 10 of 12)
[NAPS-UCR-2015-009]Update reflects Unit 2 Steam Generator
Blowdown Sodium Analyzer Upgrade.
15.2.4.3
[NAPS-UCR-2015-017]
Update adds diverse i ndications available to the operator for identification and correction of low flow boron dilution events.11.5.3.4[NAPS-UCR-2013-025]
Update reflects administra tive controls related to use of filter transport casks.
9.5.1.2.2.1, 9.5.1.2.3, 9.5.1.3.4, 9.5.1.3.7, 9.5.4.1, Figure 9.5-2[NAPS-UCR-2015-012]
Update reflects the replacement of the Fuel
Oil Pump House fire detection and extinguishing system.
7.8[NAPS-UCR-2015-021]Incorporated editorial ch anges to the list of emer gency procedures.9.2.3.1, Table 9.2-10[FN-2006-016]
Update to reflect ab andoned domestic water components.
Revision 52-09/29/16 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 3Table 7.5-3[NAPS-UCR-2015-014]Changed the Aux Feedwater Flow "Available Indicated Accuracy" value on Table 7.5-3 from +/- 15 gpm to -21 to +17 gpm.Revision 51-09/30/15 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.4.1, 4.2.1.2.2, Table 4.2-2, Figure 4.2-4[NAPS-UCR-2015-004]Reflects implementation of the Westinghouse
integral nozzle design.9.4.2.2, 9.4.3.2, 9.4.5.2, Table 9.4-3, Figure 9.4-2 (Sh.
1), Figure 9.4-4[FN-2006-026]
Update reflects modifi cation of ventilation system "roll" filters to "box" filters.
12.2.5[NAPS-UCR-2015-003]Update reflects change to the SCBA Air quality requirements.
9.3.4.2.1, 9.3.4.2.4.14[NAPS-UCR-2015-011]
Update reflects change s to the Fleet Primary Resin Strategies.Table 9.5-1[NAPS-UCR-2014-007]
Reflects the 17-ton CO2 tank replacement.2.3.3.2.1, 2.3.3.2.2, 2.3.3.2.3, Table 2.3-15[NAPS-UCR-2014-042]Reflects replacement of Obsolete Met Tower Equipment.
18.2.3, 18.2.13, 18.3.2.4, 18.5 Refs, Table 18-1[NAPS-UCR-2015-007]Updates Chapter 18 to reflect closure of various licensing commitments in Table 18-1 (Items 12, 24, 30) and refl ects changes to Boric Acid Corrosion Surveillance and the Augmented Inspection Program.
9.3.2.1.1, Figure 9.3-2 (Sh. 10 of 12)
[NAPS-UCR-2014-036]
Reflects Unit 1 Steam Generator Blowdown Sodium Analyzer Upgrade.11.4.3, 11.4.3.2[NAPS-UCR-2011-010]Reflect replacement of Main Steam Radiation
Monitors.5.1.3.1, Table 5.2-3, 5.3, 5.5.1.2, 5.5.1.3.1, 5.5.1.3.5, 5.5.1.3.11, Table 5.5-1, Figure 5.5-1, Figure 5.5-2[NAPS-UCR-2015-008]
Reflect Reactor C oolant Pump Seal Replacement - Unit 1 In terim 1B configuration.
4.2.1.2, 4.2.3.1.3, 4.2.3.2, 4.2.3.2.1, Figure 4.2-25, 11A.1, 11A.1.3, 11A.3
[NAPS-UCR-2014-010]
Reflects the re-insertion of Secondary Source
Assemblies.
Revision 52-09/29/16 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 4 Figure 10.4-3 (Sheet 2 of 4)[NAPS-UCR-2014-023]
Removed the restricting orifice (RO) on the condensate recirculation line to the condenser
.Figure 10.4-4[NAPS-UCR-2014-024]
Removed the restricting orifice (RO) on the condensate recirculation line to the condenser
.15.1 References, 15.2 References, 15.3.4.2.1, 15.3 References, 15.4 References
[NAPS-UCR-2015-005]
Implements topical report VP-FRD-41, Rev 0.2.9.2.1.2.4
[NAPS-UCR-2013-015]
Update reflects removal of internals and
actuators for service water traveling screens spray wash system air operated control valves.
9.5.1.1
[NAPS-UCR-2013-023]
Update adds the Beyond Design Basis Clean
Agent System to the list of buildings with fire suppression systems that are not required for
compliance with regulatory criterion.18.2.15, 18.3.5.3, Table 18-1[NAPS-UCR-2014-039]
Updated to indicate clos ure of license renewal commitments 14 (follow industry activities related to reactor vessel internals issues) and 20 (follow industry activiti es related to Alloy 82/182 weld material).Table 15.4-19, Figure 15.4-50, Figure 15.4-51, Figure 5.4-52, Figure 15.4-53[NAPS-UCR-2014-040]
Update reflects the implementation of the
Control Rod Ejection analysis.
15.4.3.4.5
[NAPS-UCR-2015-001]Modified reference to i ndicate the correct table.
9.5.1.2.1
[NAPS-UCR-2014-017]
Update reflects the add ition of fire protection for the security enclosure on Unit 1 turbine
deck.8.3.1.1.2.3
[NAPS-UCR-2014-026]
Update reflects Beyond Design Basis installation of elect rical connections.TOC, 18.2.16, 18.5 References
[NAPS-UCR-2014-041]Modified to reflect program name change to
Flow Accelerated Corrosion Program 8.2.1, 8.2.2, Figure 8.2-2 (Sheet 3 of 6)[NAPS-UCR-2014-005]
Update reflects replacement of 500/230 kV
transformer #5.
4.2.1.1.1, 4.2.1.2, 4.2.1.3.1, 4.2 References
[NAPS-UCR-2014-019]Update reflects new Westinghouse Cladding Corrosion Model.
6.2.2.2, 6.3.2.2.1, 10.4.3.2
[NAPS-UCR-2014-020]
Update reflects Beyond Design Basis mechanical connections.
Revision 51-09/30/15 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 55.1.3.1, Table 5.2-3, 5.3, 5.5.1.2, 5.5.1.3.1, 5.5.1.3.5, 5.5.1.3.11, Table 5.5-1, Figure 5.5-1, Figure 5.5-2[NAPS-UCR-2014-038]
Update reflects reactor coolant pump seal replacement interim configuration for Unit 2.
9.5.5.3, Figure 9.5-6[NAPS-UCR-2012-017]
Update reflects EDG coolant expansion tank
vent valve installation.5.1.1.8, 5.5.7.2, Table 5.5-15[NAPS-UCR-2012-021]Update reflects repair of 2-RC-MOV-2593.11.4.3, 11.4.3.2
[NAPS-UCR-2012-022]Modified to reflect Unit 2 main steam radiation monitor replacement.Table 3.9-1[NAPS-UCR-2012-031]Update reflects replacement of AOV valves with manual valves for Unit 2 component cooling water supply to reactor coolant pumps.3.11.3, Table 9.2-10, 9.5.1.1, 9.5.1.2.1
[NAPS-UCR-2013-004]
Update reflects modificati ons to Fire Protection and Domestic Water Systems to accommodate Unit 3 excavation area.
9.1.3.5[NAPS-UCR-2013-011]
Update reflects Beyond Design Basis
installation of spent fu el pool instrumentation.
Figure 10.4-3 (Sheet 2 of 4)[NAPS-UCR-2014-002]
Update reflects Unit 2 condensate pump
recirculation flow cont rol valve replacement.
Figure 10.4-4[NAPS-UCR-2014-003]
Update reflects Unit 2C feedwater pump recirculation flow cont rol valve replacement.
6.2.1.1.1.3, 6.2.2.2, 6.2.2.6.2.1, 6.2.2.6.2.2, Table 6.2-2, Table 6.2-4, Table 6.2-11, Table 6.2-12, Table 6.2-13, Table 6.2-14, Table 6.2-15, Table 6.2-64, Figure 6.2-60, Figure 6.2-61, Figure 6.2-62, Figure 6.2-63, Figure 6.2-64, Figure 6.2-65, Figure 6.2-66, Figure 6.2-67, Figure 6.2-68, Figure 6.2-69, Figure 6.2-70, Figure 6.2-71, Figure 6.2-72, 6.3.2.2.6, Figure 6.3-6, Figure 6.3-7, Figure 6.3-8, Figure 6.3-9[NAPS-UCR-2014-012]
Update reflects revised NAPS Containment
Safety Analysis.
8.3.1.1.2.3
[NAPS-UCR-2014-013]
Update reflects Beyond Design Basis installation of power cables.
Revision 51-09/30/15 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 6 4.4.1.1, 4.4.2.3.2.4 (new), 4.4 Refs, Table 4.4-5, 4.5 Refs, 15.0, 15 Refs, 15.2.1.2.1, 15.2.2.2.1, 15.2.7.2.1, 15.2.10.2, 15.2.1 1.2.1, 15.2.12.2.1, 15.2 Refs, 15.3.4.2.1, 15.3 Refs, 15.4.4.2.2, 15.4 Refs[NAPS-UCR-2014-021]
Update reflects discussi on of the W-3 Alternate DNB correlations approved in Appendix D to
DOM-NAF-2-P-A.
4.2.1.2, 4.2.3.1.3, 4.2.3.2, 4.2.3.2.1, Figure 4.2-25, 11A.1, 11A.1.3 (new), 11A.3
[NAPS-UCR-2014-025]
Update reflects the re-insertion of secondary
source assemblies in Unit 2.
3A.45
[NAPS-UCR-2014-028]
Updated reference to Regulatory Guide 1.108
with Regulatory Guide 1.9 9.3.4.2.4.22
[NAPS-UCR-2014-031]Update reflects replacement of flanges for
2-CH-FT-2113.9.3.4.1[NAPS-UCR-2014-032]
Update reflects Beyond Design Basis
installation of RCS injection alternate connection.
8.3.1.1.1, 8.3.1.2.1
[NAPS-UCR-2014-033]
Update reflects Beyond Design Basis
installation of elect rical connections.
Figure 4.4-21[NAPS-UCR-2014-035]
Update reflects abandonment of Unit 2 core
exit thermocouples.
Revision 50-09/30/14 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
9.3.3.2
[NAPS-UCR-2014-030]
Reference correction.Table 15.4-9, Table 15.4-10[NAPS-UCR-2014-004]Update incorporates the latest assessments
allocated to the peak cladding temperature for
the Westinghouse Automated Statistical Treatment of Uncertainty Method Best-Estimate Large Break Loss-of-Coolant
Accident Evaluation Model analysis.
7.3.2.1.5.1, 7.3.2.1.5.12
[NAPS-UCR-2014-018]Sections updated to reflect that various testing frequency is determined by Surveillance Frequency Control Program.
Revision 51-09/30/15 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 7 9.5.1.2.1, 9.5 Refs[NAPS-UCR-2014-008]
Description updated to reflect beyond design
basis connection to Fire Protection System, which can supply emer gency make-up water to the spent fuel pool.
9.5.3
[NAPS-UCR-2013-022]
Included the use of light-emitting diodes (LED) units for emer gency lighti ng in the main control room.9.3.4.1, 9.3.4.2.4.24, Table 9.3-5, Table 9.3-6, Figure 9.3-5[NAPS-UCR-2012-024]
Update reflects the addition of a Unit 2 zinc injection skid.
5.2.3.2, 9.3.4.2.4.24
[NAPS-UCR-2012-039]
Update reflects that Unit 2 allows zinc in jection.3.8.2.7.6.1.1
[NAPS-UCR-2013-026]
Update removes discu ssion of temporary concrete floor repairs to the Unit 1 recirculation spray sump area.
3.3.2, 3.5.4
[NAPS-UCR-2014-011]
Modified to clarify th at various concrete thicknesses are allowed that provide missile protection.
6.2.2.2, 6.2.2.8.3, 6.2.4.2, Figure 6.2-48, 7.3.2.12 (new)
[NAPS-UCR-2014-001]
Update reflects revised low-low level setpoint
for the Casing Cooling tank to prevent vortex
in ception.2.4.2.2
[NAPS-UCR-2013-017]Update adds a description of the new Storm
Water Sump Pump System.
Figure 1.2-1[NAPS-UCR-2010-013]
Update adds changes to the site plan associated with the alternate ISFSI haul route.
Figure 8.2-1, Figure 8.2-2 (Sheet 1 of 6)[NAPS-UCR-2010-028]
Update reflects 34.5kV Power Distribution and Switchyard Modifications.
9.5.2.1.1[NAPS-UCR-2009-027]
Clarified the power source for the public address system outside the protected area
where there is no plant operating equipment.
4.3.2.4, 4.3.2.4.9 (deleted)
[NAPS-UCR-2013-018]Updated description of shutdown margin (SDM) uncertainty.
Figure 9.3-2 (Sheet 9 of 12)[NAPS-UCR-2013-019]
Updated to reflect the removal of both Unit 1 and Unit 2 'A' Main Steam Sodium Analyzers.
4.5.3.2.4.9 (deleted)
[NAPS-UCR-2013-028]Fuel analytical section modified to remove an outdated reference.
Revision 50-09/30/14 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 8Table 8.3-8[NAPS-UCR-2012-030]
Update added panels to table, which lists enclosures with more than one field run
color-coded cable.
9.2.3.2.1
[NAPS-UCR-2012-001]
Reverse Osmosis System updated to reflect
replacement of Revers e Osmosis Water Supply Pump.Sections 3.1, 3.1.11, 3.1.16, 3.1.17, 3.1.20, 5.2.2.1, 7.1.3, 7.2.1.1.5, 7.2.1.8, 7.2.2.2.1, 7.2.2.2.1.5, 7.2.2.3.5, 7.7.2.1, 10.4.3.3, 15.2.8.1, 15.4.2.2.1; Tables 7.2-1, 7.2-2, 7.2-4, 7.2-5, 7.5-1, 7.5-2, 7.5-3; and Figures 7.2-2, 7.2-7, 7.7-8, 7.7-11
[NAPS-UCR-2010-005]
Update includes removal of reactor trip on steam generator water-low coincident with steam flow/feedwater flow mismatch and addition of median signal selection circuitry to the feedwater control system.Sections 5.1.1.8, 5.5.7.2; and Table 5.5-15[NAPS-UCR-2012-034]
Update reflects the reinstallation of the valve
internals on 1-RC-MOV-1595.Sections 5.1.3.1, 5.3, 5.5.1.2, 5.5.1.3.1, 5.5.1.3.5, 5.5.1.3.11; Tables 5.2-3, 5.5-1, 9.3-4; and Figure 5.5-1[NAPS-UCR-2013-009]
Update reflects installation of Flowserve N-9000 seals on 1-RC-P-1A.Table 6.2-9[NAPS-UCR-2013-020]
Modified to correct expon ential term associated with the tabular mass flow rate data.Tables 15.4-9, 15.4-10, 15.4-32
[NAPS-UCR-2013-021]Update incorporates the latest assessments
allocated to the peak cladding temperature
Analyses of Record fo r the AREVA realistic large break loss-of-coolant accident analyses and the Westinghouse large break loss-of-coolant accident analyses.
Revision 49-09/30/13 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
8.2.1, 8.2.2, Figure 8.2.2 (Sh. 4), Figure 8.2.2 (Sh. 6)[NAPS-UCR-2012-037]
Update reflects the repl acement of a switchyard transformer.Table 9.3-1[NAPS-UCR-2013-006]Table updated to reflec t replacement of the service air compressor aftercooler
.Revision 50-09/30/14 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 9Table 15.4-19, Figure 15.4-50, Figure 15.4-51, Figure 15.4-52, Figure 15.4-53[NAPS-UCR-2013-014]
Update reflects revised control rod ejection event analysis.9.3.4.1, 9.3.4.2.4.24 (new), Table 9.3-5, Table 9.3-6, Figure 9.3-5 (Sheet 2)[NAPS-UCR-2012-023]
Update reflects the addition of a Unit 1 zinc
injection skid.
5.2.3.2, 9.3.4.2.4.24
[NAPS-UCR-2012-038]
Update reflects that Unit 1 allows zinc
in jection.3.11.3, 9.5.1.1, Figure 9.5-1[NAPS-UCR-2013-007]
Update reflects changes associated with the underground fire protectio n piping replacement project.3.1, 3.1.11.2, 3.1.16.2, 3.1.17.2, 3.1.20.2, 5.2.2.1, 7.1.3.2.3, 7.1.3.3.3, 7.2.1.1.5, 7.2.1.8, 7.2.2.2.1, 7.2.2.2.1.5, 7.2.2.3.5, Table 7.2-1, Table 7.2-2, Table 7.2-4, Table 7.2-5, Figure 7.2-2, Figure 7.2-2a (new), Figure 7.2-7, Figure 7.2-7a (new), Table 7.5-1, Table 7.5-2, Table 7.5-3, 7.7.2.1, Figure 7.7-8, Figure 7.7-8a (new), Figure 7.7-11, Figure 7.7-11a (new), 10.4.3.3, 15.2.8.1, 15.4.2.2.1
[NAPS-UCR-2010-006]
Update reflects removal of the Unit 2 reactor
trip on steam generator water low coincident with steam flow/feedwater flow mismatch.Table 15.1-2, 15.4.3.1, 15.4.3.2.3, 15.4.3.4, 15.4.3.4.3, 15.4.3.4.4, 15.4.3.4.5, Table 15.4-34, Table 15.4-36, Table 15.4-37, Table 15.4-41, Figure 15.4-42[NAPS-UCR-2012-028]
Update reflects reanalyzed steam generator tube rupture event.Table 8.3-8[NAPS-UCR-2013-008]Table reflects addition of electrical panel for electrical distribution system cable replacement.
Figure 9.5-6[NAPS-UCR-2009-028]
Figure updated to reflect replacement of the
emer gency diesel generator jacket coolant expansion tank, gauge, and alarm switch.Table 8.3-8[NAPS-UCR-2012-008]
[NAPS-UCR-2012-012]Table updated to reflect alternate power supply to the spent fuel pool cooling pumps.11.3.3.2[NAPS-UCR-2012-035]
Discussion updated to re flect replacement of the hydrogen analyzer with an oxygen analyzer
.Revision 49-09/30/13 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 10 3.7.8 (new section), 3.7 Refs
[NAPS-UCR-2013-005]
Section added for A ugust 201 1 earthquake discussion on the evaluation and results of
analyses that were performed.LEP, Appendix 3D cover, Table 4.3-6, Appendix 5A cover, 10.2.1.1
[NAPS-UCR-2013-002]Effective pages modified to be consistent with
the relocation of Appendi ces Table of Contents, corrected FQ value and corrected reference number.Table 1.3-12, Table 3C-3, 9.2.2.1.2, 9.2.2.2.2, 9.2.2.3.2, 9.5.10.2, 9.5.10.3, 1 1.3.2, Table 11.3-1[NAPS-UCR-2010-015]
Updated to reflect the re moval of the Catalytic Recombiner from the plant.
6.3.2.1.2.1, 6.3.3.1, 6.3.4.2, Figure 6.3-4[NAPS-UCR-2012-033]
Removed the original LHSI pump performance
curve and added descript ions to reflect the current LHSI pump performance curve has been developed based on installed pump test data, reduced to account for pump degradation and instrument uncertainty.
3.7.4.3, 3.7.4.4, 3.7.4.5, 3.7.4.6
[NAPS-UCR-2013-001]
Removed discussion relate d to the old Seismic Instrumentation Program.
3.7.4, 3.7.4.1, 3.7.4.2, 3.7.4.3, 3.7.4.4, 3.7.4.5, 3.7.4.6, References 84 (new), Reference 85 (new), Reference 86 (new), 3A.51, 3A.52
[NAPS-UCR-2012-018]
Seismic discussion updated to reflect seismic
monitoring instru mentation upgrade.Table 15.4-32[NAPS-UCR-2012-032]Table updated to latest as sessments allocated to the peak cladding temp erature analys es of record for the AREVA realistic large break loss-of-coolant accident analyses.
3.8.1.1.5[NAPS-UCR-2012-026]
Service Building description modified for clarification.
12A, 12A.1, 12A.2, 12A.3, 12A.4.1, 12A.4.2, 12A.4.3, 12A.4.4, 12A.4.5, 12A.4.6, Table 12A-6 (new), Table 12A-7 (new), Figure 12A-3, Figure 12A-6, Figure 12A-8 (new)
[NAPS-UCR-2010-029]
Reactor vessel supplementary neutron shielding description updated to reflect removal of the sa ddle assembly and replacement of the insulation.
Revision 49-09/30/13 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 11 Revision 48-09/27/12 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
12.3.2[NAPS-UCR-2012-016]
Modified description of health physics facility
to clarify location of th e health physics change
out area.3.7.4.1, 3.7.4.2, 3.7.4.5, 3.7.4.6
[NAPS-UCR-2012-003]
Seismic discussion updated to reflect seismic
monitoring instru mentation upgrade.Table 4.4-2y[NAPS-UCR-2012-019]Table modified to co rrect thermal hydraulic design parameter
. Table 4.1-2, 4.2.1.1. 4.2.1.1.1, 4.2.1.1.2, 4.2.1.2, 4.2.1.2.1, 4.2.1.2.2, 4.2.1.3.1, 4.2.1.3.2, 4.2.1.4.2, 4.2.1.4.3, 4.2.2.2, 4.2.3.1.3, 4.2.3.2.1, 4.2.3.3.1, 4.2 Refs, Table 4.2-2, Figure 4.2-1, Figure 4.2-3x (new), Figure 4.2-7y (new), Figure 4.2-7z (new), Figure 4.2-19, 4.3.1.2, 4.3.1.3, 4.3.1.4, 4.3.2.1, 4.3.2.2.6, 4.3.2.3.1, 4.3.2.3.2, 4.3.2.5, 4.3.2.5.4, 4.3.2.5.7, 4.3.2.7, 4.3.3 (deleted), 4.3 Refs, Table 4.3-6 (deleted), Table 4.3-7 (deleted), Table 4.3-8 (deleted), Table 4.3-9 (deleted), 4.4.1.1, 4.4.1.5, 4.4.2.1, 4.4.2.2.2, 4.4.2.2.6, 4.4.2.3.2.3, 4.4.2.3.4.2, 4.4.2.7.2, 4.4.2.8.3, 4.4.2.9, 4.4.2.10.1, 4.4.2.10.7, 4.4.3.1.1, 4.4.3.1.3, 4.4.3.2.2, 4.4.3.4.1, 4.4.3.4.2, 4.4.3.5, 4.4.3.6, 4.4.3.1 1, 4.4 Refs, Table 4.4-2y (new), Table 4.4-3x (new), Table 4.4-4, 4.5.2.1.2, 4.5.3.3 (deleted), 4.5.4.3.2, 4.5.4.3.4.1.2, 4.5 Refs, 5.1.2.1.1, 5.1.2.1.2, 6.3.3.12, 6.3.3.13, 6.3 Refs, Table 6.3-8, Figure 6.3-16, Figure 6.3-17, Figure 6.3-18, Figure 6.3-19, 7.2.1.1.2, 7.7.1, 9.1.3.3.1, Table 9.1-2, 15.0, 15.1.2.2, 15.1.2.3, 15.1.8.1, 15.1.8.4, 15.1.9, 15.1 Refs, [NAPS-UCR-2010-007]Various sections have been updated to reflect
addition of Westinghouse Robust Fuel Assembly 2 (RFA-2) fuel design, Optimized
ZIRLO fuel cladding, wet annular burnable absorber (WABA) assembly, and integral fuel burnable absorber (IFB A). Descriptions of analyses have been updated on RFA-2 fuel design including transition cycles containing AREVA Advanced Mark-BW fuel. Descriptions of Low Parasitic fuel (LOPAR)
and North Anna Improved fuel (NAIF) have been updated to reflect the safety analyses for these products do NOT support implementation of the AECL containment sump strainer or the measurement uncertainty recapture power uprate and will no longer be used in the reactor
cores.
Revision 52-09/29/2016 NAPS UFSAR 12Table 15.1-2, Table 15.1-3, 15.2.1.2.1, 15.2.1.2.2, 15.2.2.2.1, 15.2.2.2.2, 15.2.3.2, 15.2.7.2.1, 15.2.7.2.2, 15.2.8.1, 15.2.8.2.2, Figure 15.2-9, Figure 15.2-10, Figure 15.2-11 (deleted), Figure 15.2-12 (deleted), Figure 15.2-13 (deleted), Figure 15.2-43 (deleted), Figure 15.2-45, Figure 15.2-46 (Sh eet 2), Figure 15.2-47 (Sheet 2), Figure 15.2-48 (Sheet 2), Figure 15.2-51, Figure 15.2-53, Figure 15.2-54, Figure 15.2-55, Figure 15.2-56, 15.3.1, 15.3.1.1, 15.3.1.2, 15.3.1.3, 15.3.1.4, 15.3.1.5.1, 15.3.1.5.2, 15.3.1.6, 15.3.1.7, 15.3.1.8, 15.3.1.12.1, 15.3.2.3, 15.3.4.2.1, 15.3.4.2.2, 15.3.4.2.6, 15.3.4.3, 15.3 Refs, Table 15.3-1, Table 15.3-2, Table 15.3-3, Table 15.3-3aa (new), Table 15.3-3ab (new), Table 15.3-3b (new), Table 15.3-3c (new), Table 15.3-3d (new), Table 15.3-4, Table 15.3-24, Figures 15.3-1a & 1b (new), Figure 15.3-2, Figure 15.3-3, (new) Figures 15.3-3aa, 3ab, 3ac, 3ad, 3ae, 3af, 3ag, 3ah, 3ba, 3bb, 3bc, 3bd, 3be, 3bf, 3bg, 3bh, 3ca, 3cb, 3cc, 3cd, 3ce, 3cf, 3cg, 3ch, 3da, 3db, 3dc, 3dd, 3de, 3df, 3dg, 3dh, 3ea, 3eb, 3ec, 3ed, 3ee, 3ef, 3eg, 3eh, 3fa, 3fb, 3fc, 3fd, 3fe, 3f f, 3fg, 3fh, 3ga, 3gb, 3gc, 3gd, 3ge, 3gh, 3ha, 3hb, 3hc, 3hd, 3he, 3hf, 3hg, 3ia, 3ib, 3ic, 3id, 3ie, 3if, 3ig, 3ja, 3jb, 3j c, 3jd, 3je, 3jf, 3jg, Figures 15.3-4 through 15.3-27 (deleted), Figure 15.3-39 (deleted), Figure 15.3-44 (deleted), 15.4.1, 15.4.1.1, 15.4.1.2, 15.4.1.3, 15.4.1.6, 15.4.1.7, 15.4.1.8, 15.4.1.20, 15.4.2.1.2.1, 15.4.2.13.2, 15.4.4.2.1, 15.4.4.2.2, 15.4.6.1.2, 15.4.6.2.1, 15.4.6.2.1.1, 15.4.6.2.1.3, 15.4.6.2.3, 15.4.6.2.3.1, 15.4.6.2.3.2, 15.4.6.2.3.3, 15.4.6.2.3.4, 15.4.6.2.3.5, 15.4.6.3, 15.4 Refs[NAPS-UCR-2010-007](continued)
Revision 48-09/27/12 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 13Tables 15.4-1, 2, 3, 4 & 5 (deleted), (new)
Tables 15.4-5a, 5b, 5c, 5d, 5e, 5f, 5g, 5h, 5i, 5j, Table 15.4-8, Table 15.4-9, Table 15.4-14, Table 15.4-18q (new), Table 15.4-26, (new)
Figures 15.4-a through 15.4-aa, Figures 15.4-1 through 15.4-57 (deleted), Figures 15.4-58 through 15.4-65, Figures 15.4-66 & 67 (deleted), Figures 15.4-82 through 15.4-85
[NAPS-UCR-2010-007](continued)Table 6.4-1[NAPS-UCR-2010-020]
Chemical storage table updated to reflect chemical changes from IONICS to the GE trailers for Reverse Osmosis.
Figure 8.2-1, Figure 8.2-2 (Sheet 5)[NAPS-UCR-2011-002]
230 kV switchyard drawi ngs updated to reflect the addition of breakers and a variable shunt
reactor.1.2.7, Figure 10.1-1, 10.2, 10.2.1, sections 10.2.1.2 through 10.2.1.6 (deleted),
10.2.1.7, 10.2.1.8, 10.2 Refs, Tables 10.2-2 through 10.2-7, Figure 10.2-1 through 10.2-5 (deleted), Figures 10.2-6 through 10.2-10, Figure 10.3-1 (Sh. 2)[NAPS-UCR-2011-004]Turbine generator discu ssion updated to reflect installation of the HP turbine and retrofit of the LP turbines for Unit 1.
9.2.2.5.1[NAPS-UCR-2012-007]Reactor coolant pump thermal barrier cooling coil leak discussion updated to reflect changes to the header trip valves and relief valves.Table 5.2-25, 11A.1.2
[NAPS-UCR-2012-009]
Reactor coolant water chemis try specification updated to reflect change in pH control agent. 5.1.1.8, 5.5.7.2, Table 5.5-15[NAPS-UCR-2012-011]
Reactor coolant system updated to reflect the removal of the internals on Unit 1C cold leg loop stop valve.Table 9.2-4[NAPS-UCR-2012-013]Service Water System component data
modified to restore units for submer gence value.15.4.1.18[NAPS-UCR-2012-015]Large break loss-of-c oolant accident core geometry discussion updated to reflect current AREV A grid deformation analysis.
Revision 48-09/27/12 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 14 3.8.4.5.4.5
[NAPS-UCR-2012-002]
Service water expansion joint discussion
corrected to reflect appropriate unit of measure
and revised properties of the rubber expansion jo int.8.3.1.1.1[NAPS-UCR-2012-004]Emergency diesel gene rator discussion updated to reflect replacem ent of the W oodward governor motor operated potentiometer with a
digital reference unit.Table 6.4.1[NAPS-UCR-2012-005]Table updated to reflect chemicals stored at the North Anna Power Station Paint Shop in quantities greater than 100 pounds.
2.5.2.5.1, Figure 2.5-15 (new), Figure 2.5-16 (new), 2.5 Refs), 3.7.7. 3.7 Refs[NAPS-UCR-2012-010]
Seismic discussion updated to record the August 23, 201 1 seismic event.
9.5.3
[NAPS-UCR-2010-018]
Lighting System descript ion updated to reflect use of incandescent lighting in auxiliary and decontamination buildings.Table 7.2-2, Table 7.5-3[NAPS-UCR-2011-016]Reactor trip system accuracies and ranges updated to reflect use of RF A-2 fuel.9.5.1.1, 9.5.1.2.4.1, 9.5 Refs[NAPS-UCR-2010-037]
Fire Protection System updated to reflect
Unit 2 compliance with Regulatory Guide 1.189.8.2.2, 8.2, Figure 8.2.2[NAPS-UCR-2011-012]
Switchyard descripti on updated to reflect installation of a passi ve lightning protection system.Table 8.3.8[NAPS-UCR-2010-032]Table updated to include junction boxes installed that contain two separate color-coded electrical trains.
6.3.2.1.4[NAPS-UCR-2010-034]Valve description updated to include reverse flow configuration.Table 3.9-2, Table 3.11-1[NAPS-UCR-2010-035]Tables updated to reflect change in type of
valve.Table 15.4-26[NAPS-UCR-2011-008]Table updated to latest as sessments allocated to the peak cladding temp erature analys es of record for the AREVA realistic large break loss-of-coolant accident analyses.
Revision 48-09/27/12 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 15 6.2.4.2[NAPS-UCR-2011-009]
Containment isolation valve design bases
updated to reflect that timing for fast acting
valves of the engineered safety features is based on the accident an alyses requirements.
8.3.1.1.1[NAPS-UCR-2011-014]Transformer descripti on updated to reflect removal of the sudden pressure rise trip.Revision 47-09/29/11 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.Table 6.2-40[FN 2005-003]Update to Containment Depressurization System design data reflects replacement of the re fueling water refrigeration units.
15.1.4[FN 2008-009]Update to secondary power calorimetric
measurement reflects installation of Unit 2 ultrasonic flowmeter
.15.1.4
[FN 2008-013]Update to secondary power calorimetric
measurement reflects installation of Unit 1 ultrasonic flowmeter
.10.4.5.2, Figure 10.4-7[FN 2008-032]Update reflects replacement of Unit 1 Bowser lubrication oil conditioner
.9.4.8.1[FN 2008-033]Update reflects modification to the Emergency Core Cooling System pump room exhaust air cleanup subsystem bypa ss and filter dampers.
10.2, 10.4.7.2
[NAPS-UCR-2009-009]Update reflects electr ical rating and cooling requirements of the U1 generator
.5.2.5.1[NAPS-UCR-2011-011]
Reference to the ISI Plan modified.
9.3.2.1.2; Figure 9.3.2 (Sheets 7 of 12, 9 of 12, and12 of 12)
[NAPS-UCR-2009-002]Updated to reflect steam generator feedwater chemistry is monitored in the mechanical equipment room.
6.3.2.1.4.2
[NAPS-UCR-2010-036]
Class 152 piping updated with an exception for valve 2-CC-229.
5.2.4.1.1, 5.2 Refs
[NAPS-UCR-2011-001]
A discussion about the approved
leak-before-break analysis that eliminates the augmented inspections on the RCS bypass lines was added.
Revision 48-09/27/12 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 16 9.2.2.4.2[NAPS-UCR-2011-006]
Description of check valves updated to reflect a
different type for 1-CH-240.
3.1.53.1, 3.1.53.2, 3.1.54.2, 4.3.2.7, 9.1.1, 9.1 Refs[NAPS-UCR-2010-033]
Updated sections to reflect North Anna has chosen to comply with the requirements of
10 CFR 50.68(b) with respect to spent fuel pool criticality prevention.
10.2
[NAPS-UCR-2009-008]Turbine generator discu ssion updated to reflect Unit 1 main generator exciter upgrade.
10.4.7.2[FN 2006-027]Bearing cooling water de sign flow to the Unit 2 isolated phase bus du ct air coolers updated.
1.2.7, 10.2, 10.2.1, 10.2.1.1, 10.2.1.2, 10.2.1.3, 10.2.1.4, 10.2.1.5, 10.2.1.6, 10.2.1.7, 10.2.1.8, 10.2 Refs, Table 10.2-2, Table 10.2-3, Table 10.2-4, Table 10.2-5, Table 10.2-6, Table 10.2-8, Figure 10.2-1, Figure 10.2-3, Figure 10.2-4, Figure 10.2-5, Figure 10.2-6 (new), Figure 10.2-7 (new), Figure 10.2-8 (new), Figure 10.2-9 (new), Figure 10.2-10 (new), Figure 10.3-1[NAPS-UCR-2009-005]Turbine generator discu ssion updated to reflect installation of the HP turbine and retrofit of the LP turbines for Unit 2.Table 9.2-4[NAPS-UCR-2009-032]Service Water pump component data updated
to reflect the modified impellar.
5.5.10.2[NAPS-UCR-2010-030]ASME Class applicable to U1 and U2 reactor head and pressurizer vent solenoid operated valves corrected.
9.5.1.2.3, 9.5.1.3.4
[NAPS-UCR-2009-020]
Fire protection discus sion updated to reflect replacement of Unit 1 station service transformers rate comp ensated heat detectors with a linear detector
.6.2.2.2
[NAPS-UCR-2010-038]
Inconsistency in the discussion on quench
spray injection into recirculation spray suction was co rrected.3C.2.7.9, Figure 3C-11[FN 2008-012]Leak detection discussion updated to reflect Unit 1 leak detection annunciator removed.Table 3.9-2, Table 3.11-1, Table 5.2-23, Table 6.2-47[NAPS-UCR-2010-021]Tables updated to reflec t valve replacements for MOV/JOG program.Revision 47-09/29/11 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 17Table 6.2-52, Table 6.2-53[NAPS-UCR-2010-024]Tables updated to reflect an increase in the minimum number of containment temperature
detectors.
9.1.4.4.4, 9.1.4.6.1.1
[NAPS-UCR-2010-002]
Discussion on the manipulat or crane fuel mast updated to reflect the installation of AREV A in-mast sipping system for Unit
- 1. 5.5.1.3.12
[NAPS-UCR-2010-008]Reactor coolant pump updated to reflect the
installation of an oil co llection assembly on the
reactor coolant pump stator motor coolers.5.1.1.8, 5.5.7.2, Table 5.5-15[NAPS-UCR-2010-012]
Reactor coolant system updated to reflect the removal of the internals on Unit 2B cold leg loop stop valve.
12.2.5, 12.2 Refs
[NAPS-UCR-2010-017]
Radiation protection ventilation operating
procedures updated to reflect use of the MSA
Model Firehawk M7 SCBA.
5.2.5.4, 5.5.1.2
[NAPS-UCR-2010-025]Reactor coolant pump vibration monitoring
system updated to reflect new proximity probe
system.Revision 46-09/30/10 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
3C.2.7.9, Figure 3C-11[FN 2008-010]Leak detection discussion updated to reflect Unit 2 leak detection annunciator removed.Table 6.4-1[NAPS-UCR-2010-023]Table modified to reflect phased implementation of new co rrosion inhibitor in the Bearing Cooling System.Table 6.4-1[NAPS-UCR-2010-022]Table updated to remove chemicals no longer
stored on-site and re flect current use of Dianodic DN2472.Table of Contents, List of Tables, List of Figures for following chapters: 2, 3, 6, 9, 11, 12, 14, & 15
[NAPS-UCR-2010-019]Table of Contents modified to include the Appendices Table of Contents.
9.5.1.2.3, 9.5.1.3.4[FN 2008-029]Updated to reflect replacement of Unit 2 station service transformers ra te compensated heat detectors with a linear heat detector.Revision 47-09/29/11 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 18 10.2[NAPS-UCR-2009-007]
Update reflects Unit 2 Main Generator Exciter upgrade.3.7.3.2.2.4, 3.7 Refs[NAPS-UCR-2010-016]
Deleted reference to T echnical Report CE-0076 due to its content being incorporated into the General Engineering Nuclear Standard
STD-GN-0038 reference.1.1, 1.2.3, 3.2.2, 3.8.2.2, 4.0, 4.1, Table 4.1-1, 4.3.2.2.6, Figure 4.3-22, 4.4.2.1, 4.4.2.1, 4.4 Refs, Table 4.4-2, 4.5.3.2.2.6, Table 4.5-3, 5.1.2.1.2, Table 5.1-1, Table 5.2-3, 6.2.1.1.1.1, 6.2.1.1.1.3, 6.2.1.3.1.2.1, 6.2.1.3.1.2.2, 6.2.2.6.3, Table 6.2-2, Table 6.2-16, Table 6.2-16a (new), Figure 6.2-6, 7.7.1.8, 9.2.1.3, 10.1, Figure 10.1-1, Figure 10.1-2, 10.3-1, 10.3-2, 10.4.2.1, 10.4.6.2, Table 10.4-4, 1 1.1.1.2, 15.0, 15.0 Refs, 15.1.2.1, 15.1.2.1, 15.1.2.2, 15.1 Refs, Table 15.1-1, Table 15.1-2, Table 15.1-4, 15.2.2.2.1, 15.2.2.2.2, 15.2.2.3, 15.2.3.2, 15.2.7.1, 15.2.7.2.1, 15.2.7.2.2, 15.2.8.2.1, 15.2.10.2, 15.2.11.2.1, 15.2.11.2.2, 15.2.12.2.1, 15.2.13.2.1, 15.2.13.2.2, 15.2.1.3.3, 15.2 Refs, Figure 15.2-1, Figure 15.2-2, Figure 15.2-6, Figure 15.2-8, Figures 15.2-10, 11, 12, 13, 14, 15, 16, 17, 18, & 19, Figure 15.2-24, Figure 15.2-38, Figure 15.2-44, Figures 15.2-46, 47, 48, & 49, Figure 15.2-55, Figure 15.2-60, 15.3.1.4, 15.3.1.7, 15.3.4.2.1, 15.3.4.2.2, Table 15.3-1, Table 15.3-5, Figure 5.3-35, Figure 5.3-40, 15.4.1.4, 15.4.1.5.4, 15.4.1.14, 15.4.1.18, 15.4.2.2.2.1, 15.4.4.2.1, 15.4.4.3, 15.4.4.3.1, Table 15.4-1, Table 15.4-6, Table 15.4-11, Table 15.4-12, Table 15.4-14, Table 15.4-18, Table 15.4-19, Table 15.4-26, Figure 15.4-79, Figure 15.4-82, Figure 15.4-84[FN 2008-023]Update reflects the MUR power uprate to a
core thermal output of 2940 MWt (NSSS
power of 2952 MWt).
10.4.5.3, Figure 10.4-7[NAPS-UCR-2009-014]Update reflects replacement of Unit 2 Bowser lubrication oil conditioner
.Revision 46-09/30/10 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 196.2.1.3.2.6, Table 6.3-8[NAPS-UCR-2009-026]
Update reflects installation of permanent loop room scaffold.
5.4.2[NAPS-UCR-2010-014]
Update adds a description of the canopy seal
clamp assembly added to spare CRDM nozzle penetration.
9.1.4.4.4, 9.1.4.6.1.1
[NAPS-UCR-2009-024]
The Unit 2 manipulator crane fuel mast discussion was updated to include the installation of the AREVA in-mast sipping system.3.3.2
[NAPS-UCR-2010-003]
Modified description for tornado-resistant
structures to include both types of doors as
originally installed.Table 1.5-1, Table 1.5-2, Figure 1.5-1, Figure 1.5-2, 1.6, 4.5.3.1.1, 4.5.3.1.2, 4.5.3.1.3, 4.5.3.1.4, 4.5.3.1.5, 4.5.3.1.6, 4.5.3.1.7, 4.5.3.2.2, 4.5.3.2.2.1, 4.5.3.2.2.2, 4.5.3.2.2.3, 4.5.3.2.2.4, 4.5.3.2.2.7, 4.5.3.2.2.8, 4.5.3.2.2.9, 4.5.3.2.3, 4.5.3.2.3.1, 4.5.3.2.3.2, 4.5.3.2.3.3, 4.5.3.2.3.4, 4.5.3.2.3.5, 4.5.3.2.4, 4.5.3.2.4.1, 4.5.3.2.4.2, 4.5.3.2.4.3, 4.5.3.2.4.4, 4.5.3.2.4.5, 4.5.3.2.4.6, 4.5.3.2.4.7, 4.5.3.2.4.8, 4.5.3.2.4.9, 4.5.3.2.5, 4.5.3.2.5.1, 4.5.3.2.5.2, 4.5.3.2.5.3, 4.5.3.2.5.4, 4.5.3.2.5.5, 4.5.3.2.5.6, 4.5.3.2.5.7, 4.5.3.2.6, 4.5.3.2.8, 4.5.3.2.9, 4.5.3.3, 4.5.3.3.1, 4.5.3.3.2, 4.5.3.3.2.1, 4.5.3.3.2.2, 4.5.3.3.2.3, 4.5.3.3.2.4, 4.5.3.3.2.5, 4.5.3.4, 4.5.3.4.1, 4.5.3.4.2, 4.5.3.4.2.1, 4.5.4.1.3, 4.5.4.1.4, 4.5.4.2.9, 4.5.4.2.10.4, 5.2.3.3.1, 9.5.1.2.3
[NAPS-UCR-2010-010]
Labeled tables and figures associated with
original design testing as historical. Changed
title for WCAPs to genera l references. Clarified various sections to indi cate they are applicable to Advanced Mark-BW fuel. Corrected
typographical errors a nd clarified location terminology.
9.5.1.2.2.1, 9.5.1.2.2.2, 9.5.1.2.3, 9.5.4.2[FN 2008-035]The fire detection comput er system description was updated to reflect th e new system installed for the Fire Detection System Replacement Project.9.3.3.2[NAPS-UCR-2009-018]
Description of the Unit 1 air handling room floor drains was updated to reflect the removal of the backflow preventers.
Revision 46-09/30/10 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 20 3.8.2.2[NAPS-UCR-2009-036]
Containment air partial pressure and maximum containment bulk air te mperature discussion was modified to re flect current technical specification limits.
4.5.3.2.2.6.2, 4.5.4.2.2.6, 4.5 Refs, Table 4.5-3[NAPS-UCR-2010-004]The linear heat rate to fuel melt for AREVA fuel was updated to reflect code error correction.
6.3.3.12[NAPS-UCR-2010-011]
A discussion on containment pressure
information was modifi ed to note it is historical.Table 3C-2[NAPS-UCR-2010-001]Updated the high-energy steam generator
blowdown lines.
4.3.2.7, 4.5.3.2.7
[NAPS-UCR-2009-037]Text updated to reflect that the spent fuel pool
criticality analysis was evaluated in support of a measurement uncertainty recapture power uprate.9.4.2.1, 9.4.2.3, Figure 9.4-5[NAPS-UCR-2009-033]Text updated to reflect auxiliary building central exhaust motor-operated dampers replaced with back draft dampers.
3.8.1.1.13, 3.8.1.1.14, 3.8.4.5.4.7, 9.2.1.1, 9.2.1.2.4.2
[NAPS-UCR-2009-013]
Revised description to reflect removal of expansion joints from Service Water tie-in vault and valve house. Allowable settlement
value revised to reflect pipe stress and pipe support analyses.Table 9.2-4[NAPS-UCR-2009-031]Service Water pump data updated to reflect
change in impeller
.9.5.1.2.3[NAPS-UCR-2009-034]Updates the table of containment heat detector
setpoints to reflect new heat detectors in Unit 1.2.3.4.3[NAPS-UCR-2009-035]
Updates the Meteorological Information Dose Assessment System information and how the plant computer processes that data.
Figure 8.2-1[FN 2007-027]Revised figures to reflect replacement of switchyard transformers.Table 11.2-1[FN 2007-036]Liquid Waste Disposal Equipment Design
Table updated to reflect removal of powdered resin recirculation pump powdered resin holdup tank and water return pump.
Revision 46-09/30/10 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 2111.4.2.1, Table 11.4-1[FN 2007-034]Updated to incorporate replacement of letdown radiation monitors with new GM tube monito rs.7.1.4, 7.1 Refs
[FN 2008-008]Updated to incorporate TRM Section 3.3.9 as a new reference for RG 1.97 instrument
functionality , reportability, and alternate indications.
3.8.2.1.4.1
[NAPS-UCR-2009-004]
Clarified components that qualify as secondary overload protection as sociated with Unit 2 containment electric al penetrations.
18.3.5.6
[NAPS-UCR-2009-019]
Updated discussion on reactor coolant pump
and ASME code case N-481.Table 15.3-24, Table 15.4-26[NAPS-UCR-2009-025]Incorporated the latest assessments allocated to
the peak cladding temp erature analysis of record for the AREVA small break loss-of-coolant accident and AREVA realistic large break loss-of-coolant accident analyses.
Revision 45-09/30/09 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
KWI[NAPS-UCR-2009-023]
Removes the key word index.11.2.2.2[FN 2008-002]Reflects replacement of the ion exchange
filtration system.6.4.1.1, 6.4.1.2, 6.4.1.3, 6.4.1.3.1, 6.4.1.4, 6.4.1.5, 7.7.1.12.1, 9.4.1.1, 9.4.1.2, 9.4.1.3, 9.4.1.5, Table 9.4-2, 12.1.2.10, 15.4.1.7, 15.4.1.7.7, 15.4.5.2, 15.4.5.3, 15.4.5.4, Table 15.4-6, Table 15.4-13[NAPS-UCR-2009-016]
Incorporates technical specification change to remove requirements for the control room
bottled air system.11.4.2, 11.4.2.15
[NAPS-UCR-2009-021]
Corrected description of the reactor coolant letdown radiation de tection equipment.
6.2.2.2, 6.3.2.1.6[FN 2008-026]Reflects the installation of the seal closure frames on the containment sump strainer for Unit 1.Revision 46-09/30/10 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 22 9.3.2.1.2, 9.3.2.1.3, Figure 9.3-2 (Sheets 7, 9, &12)[FN 2008-039]Reflects modification os online chemistry monitoring system for Unit 1 steam generator feedwater chemistry.
9.2.2.3.1[NAPS-UCR-2009-010]
Changed the pH range for the chromated
component cooling water
.12.3.3
[NAPS-UCR-2009-012]Added Effective Dose Equivalent to the types
of exposure that are determined by
Thermoluminescent Dosimetry badges.
9.5.2.1.3
[NAPS-UCR-2009-015]
Corrected location of the communications
tower.Figure 10.1-1, Table 10.4-2[FN 2008-004]Updated the design information for the 6th point feedwater heaters.
5.2.5.4[FN 2007-032]Replaced the reactor coolant pump vibration
monitoring system.
Figure 8.2-2[FN 2008-015]Updated figure to reflect modifications made to the switchyard buses.
7.7.2.6[NAPS-UCR-2009-006]
Corrected section on safe ty injection actuation input logic to align it with actual signal inputs for low pressurizer pressure.
9.6.1, 9.6.5, 9.6 Refs[FN 2008-036]Updated Heavy Loads discussion to include
reactor vessel head drop analysis.
8.2.2[FN 2006-007]Clarifies the backup sources of power to the battery char ger for the dc system in the 230kV Control House in the Switchyard.
9.5.1.2.3
[FN 2007-009]An interim update of setpoints of the Unit 2 containment heat detectors installed under the Fire Detection Replacem ent Project. Relocated setpoints from note to list of detectors.
Figure 10.1-2, Table 10.4-2[FN 2007-028]Updates design information for the Unit 2 sixth point feedwater heaters and Unit 2 power heat balance figure.
Figure 6.2-38 [FN 2008-034]Corrects snubber figure to be consistent with plant configuration.Table 10.4-4, Table 15.1-2, Table 15.4-35[NAPS-UCR-2009-001]
Corrects tables to be consistent with the
accident analysis of record calculations.
Revision 45-09/30/09 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 23 10.2, 10.4.7.2 [FN 2008-005]Updated electrical rati ngs and cooling water requirements of the U2 ge nerator. Corrected the U1 generator rating.
6.2.2.2, 6.3.2.1.6
[FN 2008-017]Added description of the containment sump
strainer seal frames.18.2.1, 18.2.11, Table 18-1[FN 2008-021]Revised to indicate clos ure of license renewal commitments 2 (addition of inspection of
pressurizer sur ge line and 11 (evaluation of industry initiatives related to the inspection of
small-bore piping).12.1.1, Table 12.1-1, Figure 12.1.1, Figure 12.1.2, Figure 12.1.3, Figure 12.1.4, Figure 12.1.5[FN 2008-031]Designated original plant shielding zone criteria as historical.
18.5 Refs. [FN 2008-037]Updated references associated with the Steam
Generator Program.
6.2.2.2, 6.2.2.3, 6.2.2.4, 6.2.2.5, 6.2.2.6, 6.2.3.1.1, 6.2 Refs, Table 6.2-38, Table 6.2-39, Table 6.2-40, Figure 6.2-55, Figure 6.2-56, Figure 6.2-58, Figure 6.2-59, 6.3.2, 6.3.2.1.6, 6.3.4.2, 6.3 Refs, Table 6.3-1, Table 6.3-6[FN 2007-031]Updated various sections to reflect compliance
with GSI-191 for the strainer assembly
.Table 15.1-3,15.2.7.2.2, Table 15.2-1, Figure 15.2-19, Figure 15.2-20, Figure 15.2-21, Figure 15.2-22, Figure 15.2-23, Figure 15.2-24, Figure 15.2-25, Figure 15.2-26, Figure 15.2-27, Figure 15.2-28, Figure 15.2-29, Figure 15.2-30[FN 2008-018]Updated the loss of load event figures and
tables to reflect curren t analysis of record.
Changed the safety analysis limit on High Pressurizer Pressure.
2.1.3, Figure 2.1-4, Figure 2.1-5, Figure 2.1-6, Figure 2.1-7, Figure 2.1-8, Figure 2.1-9, Figure 2.1-10, Figure 2.1-11, Figure 2.1-12, Figure 2.1-13, Figure 2.1-14 [FN 2008-020]Designated section on Population and
associated figures as historical.
Revision 45-09/30/09 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 24Table 5.2-25, 11A.1.2[FN 2008-022]Increased RCS pH (300C) from the current program to 7.0-7.2 based on EPRI PWR Primary Water Guidelines, EPRI PWR Fuel Cladding Corrosion Guidelines, and fuel Vendor recommendations.9.6.4.4, Table 9.6-1 [FN 2008-024]Incorporated the new spent filter cask spreader
beams and new filter casks.Table 6.4-1 [FN 2008-027]Updated quantity of chem icals stored on site and in the warehouse to reflect current system
configuration.
KWI, 13.3, 13.3 Refs[FN 2008-028]Reflects use of emergency action levels in
accordance with NEI 99-01, Rev
.4.Revision 44-09/30/08 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
8.3.1.1.1, 9.5.1.2.3[FN 2008-016]Corrected a note for the temperature detecting
sensors and added additional
temperature-detecting sensor setpoints.
Clarified the discussion on Unit 1 main generator breaker
.6.3.2.2.5[FN 2008-019]Updates the description of the limiting LHSI pump NPSHa case.5.5.1.3.11[FN 2008-014]Amends the discussion on RCP seal-water
in jection filter size.
Figure 1.2-2, 9.2.3.2.1[FN 2007-002]Reflects changes to the reverse osmosis system and removal of the domestic water tank.
9.4.4.5[FN 2007-022]Changes the method of controlling the Turbine
Building ventilation supply dampers from auto to manual.15.3.1.13, 15.3 Refs, Table 15.3-24, 15.4.1.18, 15.4 Refs, Table 15.4-27[FN 2008-011]Incorporates the latest assessments allocated to the peak clad temperature analysis of record for the AREVA small break LOCA and large break
LOCA.Revision 45-09/30/09 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 25 2.4.3.4, Figure 2.4-3, Figure 2.4-6, Figure 2.4-8, 2.A.2.3.1, Figure 2A-2, Figure 2A-8[FN 2005-046]Corrects the radial gate description regarding the maximum radial gate opening at the spillway.Table 9.5-1[FN 2006-021]Incorporates changes associated with fire protection system upgrade.
9.5.1.2.2.1
[FN 2007-021]Corrects the CO2 system description to reflect
that the total flooding extinguishment is
provided by one-shot.
15A.3.1
[FN 2008-006]Updates the site boundary dose for postulated
cask drop accidents.
3.8.2.1.4.2, Figure 3.8-11, 9.2.2.1.1, 9.2.2.3.1[FN 2007-017]Updated the description of the hot pipe containment penetration coolers (Unit 1)12.3.1, 13.4[FN 2007-024]Incorporates changes in titles to the Quality
Assurance Program Description (QAPD) and Facility Safety Review Committee (FSRC).3.8.2.7.6.3, Table 3.8-10, Table 3.8-11, Table 3.8-19, Table 3.8-20, Table 3.8-21[FN 2007-033]Added discussion of GSI-191 coatings review and qualified and unqualif ied coating tables.
Figure 8.2-1[FN 2008-003]Revised figure to reflect new type of
disconnect for H204M.
9.5.9.2
[FN 2005-045]Added description of vacuum drying system
that facilitates the dry shielded canister in the decontamination facility.
3.8.2.7.6.1.1[FN 2007-026]Added description for restoration of recirculation spray sump trench floor
.Revision 44-09/30/08 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 26 KWI, 6.1, 6.2.1.1.1, 6.2.1.1.1.1, 6.2.1.1.1.2, 6.2.1.1.1.3, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.1.3.1.2, 6.2.1.3.1.2.1, 6.2.1.3.1.2.2, 6.2.1.3.1.3, 6.2.2.1, 6.2.2.2, 6.2.2.3.1, 6.2.2.3.2, 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.3, 6.2.2.3.2.4, 6.2.2.3.2.5, 6.2.2.3.2.6, 6.2.2.3.3, 6.2.3.1.1, 6.2.3.2, 6.2.3.3, 6.2.6.3, 6.2 Refs, Tables 6.2-1, 6.2-2, 6.2-3, 6.2-4, 6.2-1 1, 6.2-12, 6.2-13, 6.2-14, 6.2-15, 6.2-16, 6.2-17, 6.2-18, 6.2-19, 6.2-40, 6.2-46, 6.2-47, 6.2-48, 6.2-49, 6.2-58, 6.2-62, & 6.2-63, Figures 6.2-6, 6.2-7, 6.2-8, 6.2-51, 6.2-63, 6.2-64, 6.2-65, 6.2-66, 6.2-67, 6.2-68, 6.2-69, 6.2-70, 6.2-71, 6.2-72, 6.2-73, 6.2-74, 6.2-75, 6.2-76, 6.2-77, 6.2-78, 6.2-79, 6.2-80, 6.2-81, 6.2-96, &
6.2-97, 6.3.2.2.2, 6.3.2.2.6, 6.3.3.12, 6.3 Refs, Table 6.3-9, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-1 1, 6.3-12, &
6.3-13, 15.4.1.7, 15.4.1.8, 15.4.1.8.1, 15.4.1.8.2, 15.4.1.8.3, 15.4.1.8.4, 15.4.1.8.5, 15.4.1.8.6, 15.4.1.8.7, 15.4.1.8.8, 15.4.5.2, 15.4 Refs, Table 15.4-6, 15.4-7, 15.4-14, &
15.4-37, Figures 15.4-110 &
15.4-111[FN 2006-010]Performed containment analyses and LOCA
alternate source term analyses to support
GSI-191 modifications Unit 1.6.2.1.3.2.3, 6.2.2.2, 6.2.2.3.2.2, 12.1.2.1, Table 12.1-2, Figure 12.1-8[FN 2006-020]Added the Unit 1 incore sump room drain to support GSI-191 containment sump modifications.Table 3.2-1, Figure 6.1-1, 6.2.2.2, 6.2.2.3, 6.2.2.4.3, 6.2.2.4.4, 6.2.3.3, 6.2 Refs, Table 6.2-38, Table 6.2-40, Figure 6.2-55, Figure 6.2-58, Figure 6.2-59, Figure 6.2-60, Figure 6.2-74, Figure 6.2-87, 6.3.2.2.3, Table 6.3-1[FN 2007-008]Completed partial installation of Unit 1 containment sump stra iners to support GSI 191 modifications. 6.2.2.2, 6.2.2.3.2.1, 6.2.3.1.1, Table 6.2-2, Table 6.2-12, Figures 6.2-63, 64, 65, 66, 67, 68, 69, 70, 71, 72, & 73, Figures 6.3-7, 8, 9, & 10, Table 15.4-7[FN 2007-020]Incorporates reduction in the minimum IRS
and OSR safety analysis pump flow rates and updates the LOCA alternate source term analysis.Revision 44-09/30/08 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 27 9.1.4.9, 9.1.4.9.1, 9.1.4.9.2, 9B.2, 15A.1, 15A.2, 15A.3.1
[FN 2007-029]Replaces detailed information about cask
loading and unloading with references to the
TSARs and FSARs. Adds NUHOMS OS-187H to the list of evaluated cask designs.
6.2.1.3.1.1, 6.2.2.1, 6.2.2.2, 6.2.3.1.1, 6.2.3.3, Table 6.2-41, 15.4.1.8.7, 15.4.5.2, Table 15.4-7, Table 15.4-14[FN 2008-001]Editorial changes; Clarifies final markups for
GSI-191 multiple packages.
9.5.1.2.2.2[FN 2007-012]Replaced ionization type smoke detectors with Photoelectric type detectors.7.3.1.3.2, 7.3.1.3.2.2, 7.3.1.3.3.2, 7.3.2.11, Table 7.3-2[FN 2007-016]Updated the description of the RWST level-low
engineered safety features actuation system (ESF AS) function to include Unit 1 GSI-191 modification.
Figures 8.2-1 & 8.2-2[FN 2006-015]Switchyard figures were m odified to reflect the upgrade on buses 3, 4, and 5 in the switchyard.Table 5.2-22[FN 2007-025]Updated the description of the steam generator secondary side clos ure bolting material.
6.2.1.2.20
[FN 2007-018]Provided for use and storage of a manbasket
inside the containment.
7.2.1, 7.2.1.2, 7.2.2.2.1.7, 7.2 Refs, 15.1.3[FN 2007-010]Updated the description of reactor trip system response time testing and verification.
9.5.2.2.4[FN 2007-006]Corrected the description of the emergency notification system.
10.2[FN 2007-004]Modified the turbine overspeed protection control circuitry
.15.4.1.5.3, Table 15.4-5[FN 2007-014]Incorporated the peak clad temperature
penalties and benefits for the lar ge break LOCA. [10 CFR 50.46]18.2.11, 18.2.13, 18.2.15
[FN 2007-023]Clarified the description of developing and
submitting the Inservice Inspection Plan.
Revision 44-09/30/08 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 28 Revision 43-09/27/07 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
KWI, 6.1, 6.2.1.1.1, 6.2.1.1.1.1, 6.2.1.1.1.2, 6.2.1.1.1.3, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.1.3.1.2, 6.2.1.3.1.2.1, 6.2.1.3.1.2.2, 6.2.1.3.1.3, 6.2.2.1, 6.2.2.2, 6.2.2.3.1, 6.2.2.3.2, 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.3, 6.2.2.3.2.4, 6.2.2.3.2.5, 6.2.2.3.2.6, 6.2.2.3.3, 6.2.3.1.1, 6.2.3.2, 6.2.3.3, 6.2.6.3, 6.2 Refs, Tables 6.2-1, 6.2-2, 6.2-3, 6.2-4, 6.2-1 1, 6.2-12, 6.2-13, 6.2-14, 6.2-15, 6.2-16, 6.2-17, 6.2-18, 6.2-19, 6.2-40, 6.2-46, 6.2-47, 6.2-48, 6.2-49, 6.2-58, 6.2-62, & 6.2-63, Figures 6.2-6, 6.2-7, 6.2-8, 6.2-51, 6.2-63, 6.2-64, 6.2-65, 6.2-66, 6.2-67, 6.2-68, 6.2-69, 6.2-70, 6.2-71, 6.2-72, 6.2-73, 6.2-74, 6.2-75, 6.2-76, 6.2-77, 6.2-78, 6.2-79, 6.2-80, 6.2-81, 6.2-96, &
6.2-97, 6.3.2.2.2, 6.3.2.2.6, 6.3.3.12, 6.3 Refs, Table 6.3-9, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-1 1, 6.3-12, &
6.3-13, 15.4.1.7, 15.4.1.8, 15.4.1.8.1, 15.4.1.8.2, 15.4.1.8.3, 15.4.1.8.4, 15.4.1.8.5, 15.4.1.8.6, 15.4.1.8.7, 15.4.1.8.8, 15.4.5.2, 15.4 Refs, Table 15.4-6, 15.4-7, 15.4-14, &
15.4-37, Figures 15.4-110 &
15.4-111[FN 2007-035]Performed containment analyses and LOCA
alternate source term analyses to support
GSI 191 modifications.Table 3.2-1, 4.1, Figure 6.1-1, 6.2.2.2, 6.2.2.3, 6.2.2.4.3, 6.2.2.4.4, 6.2.3.3, 6.2 Refs, Tables 6.2-40 & 6.2-42, Figures 6.2-57, 6.2-58, 6.2-59, 6.2-60, 6.2-61, 6.2-62, &
6.2-80, 6.3.2.2.3, 6.3.3.12, 6.3.3.13, Table 6.3-1, 6.3-8, & 15.4-2[FN 2006-037]Completed partial installation of Unit 2 containment sump strainers to support GSI 191 modifications.
3.8.2.1.4.2, 3.8.2.1.4.5[FN 2006-028]Increased the temperature limitation for containment penetrations from 150°F to 200°F
.3.8.2.1.4.2, Figures 3.8-11 & 3.8-15[FN 2007-001]Removed the outside cooler on hot pipe containment penetrations (except installed spares).3.8.2.1.4.2, Figures 3.8-11, & 3.8-15, 9.2.2.1.1, 9.2.2.3.1
[FN 2007-003]Updated the description of the hot pipe
containment penetration coolers.
Revision 52-09/29/2016 NAPS UFSAR 29 4.1, 4.4.1.6, 4.5.2.1.2, 4.5.3.2.1, 4.5.4.1.6, 4.5 Refs, Tables 4.5-1, 4.5-2, 4.5-3, 15.4.1.9, 15.4 Refs[FN 2005-043]Updated the reconstitution methodology for AREV A Advanced Mark-BW fuel.Table 4.1-2, 4.5.4.1.1, 4.5.4.1.5, 4.5.4.2.1, 4.5.4.2.3.1, 4.5.4.2.3.4.2, 4.5.4.2.3.4.3, 4.5.4.2.5, 4.5.4.2.6, 4.5.4.2.8.1, 4.5.4.2.8.3, 4.5.4.2.10.4, 4.5.4.2.10.5, 4.5.4.3.1.3, 4.5.4.3.4.1, 4.5.4.3.4.1.3, 4.5 Refs, Table 4.5-3, 7.2.2.1.2.1, 15.1.9.8, Table 15.1-2, 15.3.4.2.1, 15.4.4.2.1, 15.4.4.2.2
[FN 2005-023]Incorporated use of the VIPRE-D/BWU computer code to perform thermal-hydraulic evaluations of AREVA Advanced Mark-BW fuel. [10 CFR 50.90 License Amendment]Table 5.2-22[FN 2006-031]Updated the description of the pressurizer
closure bolting material.
6.2.1.3.2.3, 6.2.2.2, 6.2.2.3.2.6, 12.1.2.1, Table 12.1-2, Figure 12.1-8[FN 2006-011]Added the Unit 2 incore sump room drain to support GSI 191 containment sump modifications.
6.2.2.2[FN 2007-007]Corrected the description of debris generation
and transport evaluation for the Unit 2 containment sump strainer design.7.3.1.3.2, 7.3.1.3.2.2, 7.3.2.11, 7.3 Ref Dwgs, Table 7.3-2[FN 2006-035]Modified the Unit 2 refueling water storage tank engineered safety features actuation system to support GSI 191 containment sump modifications.
8.1.2, 9.2.1.1, 9.2.1.2.2, 9.2.1.3.1, 9.2.2.3, 9.3.1.2, 9.3.2.1.3, 9.3.2.2.3, 9.3.4.2.1, 9.3.4.3.1, 9.5.1.2.3, 9.5.1.3.4, 9.5.1.4.2, 9.5.1.6, 9.5.1.6.1, 9.5.1.6.2, 9.5.2.1.1, 9.5.6.2, 10.3.4, 10.4.1.4, 10.4.7.4, 1 1.4.5, 12.1.4.1[FN 2007-011]Modified the terminol ogy associated with determinations of opera bility and functionality in accordance with Regulatory Issue Summary 2005-20.9.2.1.2.2[FN 2006-013]Reduced the frequency of monitoring the service water reser voir sludge depth from annually to once per five years.
9.2.2.5.1[FN 2007-015]Clarified the description of system operation following a reactor coolant pump thermal barrier coil leak.Table 9.2-4[FN 2006-032]Replaced auxiliary service water pump, 1-SW-P-4.Revision 43-09/27/07 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 30 9.5.1.2.2.2, 9.5.1.2.3[FN 2006-009]Replaced heat and sm oke detectors in the Training Center records vault.
15.3.1.6, 15.3 Refs, Table 15.3-4[FN 2007-013]Incorporated the peak clad temperature penalties and benefits for the Westinghouse SBLOCA. [10 CFR 50.46]15.3.1.13, 15.3 Refs, Table 15.3-4, 15.4.1.17, 15.4 Refs, Table 15.4-26[FN 2006-022]Incorporated the peak clad temperature penalties and benefits for the Westinghouse SBLOCA and AREVA RLBLOCA. [10 CFR 50.46]15.4.2.1.3.2, 15.4.3.4.2, 15.4.4.3.2
[FN 2005-047]Revised the description of steam generator
leakage. [10 CFR 50.90 License Amendment]18.2.6, 18.2.19, Table 18-1[FN 2006-033]Reflected the completion of License Renewal Commitment Item Nos.
16, 18, and 28.Revision 43-09/27/07 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 31 Revision 42-09/29/06 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
KWI, 1.2.9, 2.1.3.4, 2.3.4.1, 2.3.4.2, Table 2.3-18, 3.1.15.1, 3.1.15.2, 3.6.1, 3.7.3.2, 6.2.1.3.1, 6.2.2.1, 6.2.3.1, 6.2.3.1.1, 6.2.3.2, 6.2.3.3, Table 6.2-41, 6.3.3.6, Table 6.3-6, 6.4.1.1, 6.4.1.2, 6.4.1.3, 6.4.1.3.1, 7.7.1.12.1, 9.4.1.3, 9.4.5.3, Table 10.4-3, 11.1.1.1, 12.1.1, 12.1.2.8, 12.1.2.10, Figure 12.1-10, 15.1.7.1, 15.2.13.3, 15.4, 15.4.1.7, 15.4.1.7.1, 15.4.1.7.2, 15.4.1.7.3, 15.4.1.7.4, 15.4.1.7.5, 15.4.1.7.6, 15.4.1.7.7, 15.4.1.7.8, 15.4.1.8.3, 15.4.2.1.3, 15.4.2.1.3.1, 15.4.2.1.3.2, 15.4.2.1.3.3, 15.4.2.1.3.4, 15.4.2.1.3.5, 15.4.3.2.1, 15.4.3.2.3, 15.4.3.3, 15.4.3.4, 15.4.3.4.1, 15.4.3.4.2, 15.4.3.4.3, 15.4.3.4.4, 15.4.3.4.5, 15.4.4.2.2, 15.4.4.3, 15.4.4.3.1, 15.4.4.3.2, 15.4.4.3.3, 15.4.4.3.4, 15.4.4.3.5, 15.4.5, 15.4.5.1, 15.4.5.2, 15.4.5.3, 15.4.5.4, 15.4.7.1, 15.4.7.2, 15.4.7.2.1, 15.4.7.2.2, 15.4.7.2.3, 15.4.7.2.4, 15.4.7.2.4.1, 15.4.7.2.4.2, 15.4.7.2.4.3, 15.4.7.2.4.4, 15.4 Refs, Tables 15.4-6, 15.4-7, 15.4-12, 15.4-13, 15.4-14, 15.4-15, 15.4-17, 15.4-18, 15.4-29, 15.4-30, 15.4-31, 15.4-32, 15.4-33, 15.4-34, 15.4-35, 15.4-36, &
15.4-37, Figures 15.4-74 & 15.4-110[FN 2003-036 & F N 2004-021]Implemented an alternat e source term from NUREG-1465 as the design basis source term.
[1 0 CFR 50.90 License Amendment]
3.8.2.1.4.2, Figures 3.8-11 & 3.8-15[FN 2005-038 & F N 2005-042]Isolated ten Unit 2 containment penetrations' outer cooler component cooling supply and return by seal plate or plug.
3.8.2.1.4.2, Figures 3.8-11 & 3.8-143[FN 2006-002]Isolated ten Unit 1 containment penetrations' outer cooler component cooling supply and return by seal plate or plug.Table 3F-8[FN 2006-025]Revised the emergency diesel generator rooms maximum temperature.
4.4.3.2.1, 4.4 Refs, 4.5.4.2.2.6[FN 2006-005]Provided a generic formula for nuclear
enthalpy rise hot channel factor , , and referred to the Core operating Limits Report for curren t values of and the total heat flux hot-channel factor, F Q.F NH F NH Revision 52-09/29/2016 NAPS UFSAR 32 4.5.3.2.2.6.4[FN 2005-018]Modified the discussion of Unit 1 peaking factor uncertainty
.4.5.3.2.2.6.4[FN 2005-019]Modified the discussion of Unit 2 peaking factor uncertainty
.Table 4.5-3[FN 2006-008]Reflected the increase in core pressure drop due to use of the Advanced Mark-BW one-quarter turn quick disconnect top nozzle.Tables 5.1-1 & 5.5-17[FN 2006-023]Corrected the description of pressurizer spray flow rate.
5.2.2.2, 5.2 Refs, Tables 5.2-20 and 5.2-21, 5.4.1.2, 5.4 Refs[FN 2003-053]Revised the reactor coolant system
pressure-temperature limits, LTOPS setpoints, LTOPS T enable values, and administrative cooldown rate limit. [10 CFR 50.90 License Amendment]5.2.3.3.1, 5.2 Refs, 5.4.3.6, 5.4 Refs, Tables 5.4-2 & 5.4-3[FN 2005-005 & F N 2005-041]Updated the surveillance capsule withdrawal schedules to incorporat e the renewed operating licenses for both units. [10 CFR 50, Appendix H]5.2 Refs, 18.2.12[FN 2005-037]Removed specific interval and ASME XI edition and addenda references to allow
required periodic update.Table 5.2-3[FN 2006-003]Clarified that the narrow range RTD
thermowells and RVLIS pipe connections on the reactor coolant hot leg piping are designed in accordance with ASME Section III - 1980 Edition.6.2.2.2.3, Table 6.2-42[FN 2004-041 & F N 2004-043]Updated the description of the design code for
the RWST cooling subsystem.
6.2.2.3[FN 2005-021]Clarified the descripti on of the layup condition of the recirculation spray heat exchangers.
6.4.1.3, 7.7.1.13, 9.4.1.3[FN 2006-019]Installed Unit 1 and Unit 2 carbon dioxide monitors in the control rooms.
8.1.1, 8.2.2, Figures 8.2-1 & 8.2-2[FN 2005-030]Replaced feeder cables to reserve station service transformers A, B, & C, and installed an additional 500 kVA transformer.
8.2.3.1, Figure 8.2-1[FN 2005-048]Relocated and replaced switchyard breakers.
Revision 42-09/29/06 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 33 Figure 8.2-1, 8.3.1.1.2.3, 8.3.1.2.1, 8.3.1.2.2.4, Table 8.3-8[FN 2005-011]Replaced vital bus inverters 2-III & 2-IV and added an additional bypass transformer.
Figure 8.2-1, 8.3.1.1.2.3, 8.3.1.2.1, 8.3.1.2.2.4, Table 8.3-8[FN 2005-031]Replaced vital bus inverters 1-III & 1-IV and added a new bypass switch.9.1.3.1, 9.1.3.3.1, Table 9.1-2[FN 2005-028]Provided for offload of fuel from the reactor vessel to the spent fuel pool as early as 100
hours after shutdown.
Figure 9.1-8[FN 2005-016]Removed an electrical cable reel from the fuel
handling bridge crane.9.2.3.1, Table 9.2-10[FN 2003-048]Replaced domestic water Well No.
3 with Well No. 7.9.3.3.2, 10.4.2.3
[FN 2006-017]Installed backflow prev enters in the floor drains of the Unit 1 & 2 air conditioning rooms.Table 9.3-2, 10.4.7.2, Table 10.4-2[FN 2006-001]Increased the design flow for the Unit 1 isolated phase bus du ct air coolers and abandoned in place certain flash evaporator system components.Tables 9.3-2 & 10.4-2[FN 2006-024]Corrected the description of Unit 1 flash evaporator system components previously
abandoned in place.Table 9.3-7[FN 2006-004]Corrected the description of boron recovery system equipment.
9.4.6.3[FN 2005-036]Updated the description of the safeguards supply fans noting that the high speed function
is disabled.
9.4.9.3[FN 2004-050]Updated the description of containment isolation during refueli ng to include the hi-hi radiation signal from the manipulator crane radiation monitor
.9.5.1.2.3, 9.5.1.3.4[FN 2005-017]Replaced the heat detectors on the Unit 2 main transformers.
10.2, 10.2.1.1.2, 10.2 Refs[FN 2006-014]Reduced the frequency of main turbine and governor valves surveill ance testing from once per three months to once every six months.
Revision 42-09/29/06 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 34 10.3.1[FN 2005-034]Clarified the description of the steam generator PORVs' design function and control cables.
10.4.2.3[FN 2005-035]Reanalyzed the maximum flooding elevation of the T urbine Building due to a failure of a condenser outlet expansion joint.
10.4.7.1
[FN 2005-013]Replaced the bearing c ooling tower chemical addition system.11.4.2.1, 12.1.4.1[FN 2005-026]Updated the description of radiation monitor
recorders.12.4.3, Chapter 17 (all)[QA 2004-002 & FN 2004-017]Replaced Chapter 17 in its entirety with a brief description of and refe rence to the recently implemented T opical 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)]Revision 41-09/30/05 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.2.4.11.1, 2.4.11.2, 2.4.11.3, 2.4.11.5, 2.4.11.6, 2.4.14, Table 2.4-6[FN 2004-002]Corrected the extreme low water level value
and clarified its basis. Provided revised values for the auxiliary service water pumps' and the reverse osmosis water pump's minimum operating level, required submergence, and actual submergence.3.1.37.2, 3.11.2.5, Table 3.11-2, 3A.7, 6.1, 6.2.5.1, 6.2.5.2, 6.2.5.3, 6.2 Refs, Table 6.2-55 & 6.2-62, Figures 6.2-91, 6.2-92, 6.2-96, 6.2-97, 6.2-98, &
6.2-99[FN 2005-004]Incorporated licen se amendments on elimination of requi rements for hydrogen
recombiners and hydrogen monitors using the Consolidated Line Item Improvement Process.
[1 0 CFR 50.44]Table 3.5-5, 9.2.3.2.1[FN 2005-022]Reflected the removal of the use of hydrogen, the hydrogen storage facility , and the de-oxygenation trailer for the reverse osmosis system.Revision 42-09/29/06 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 35 3.8.1.4.7, 3.8 Refs[FN 2004-042]Provided clarification to the description of
masonry block walls.
4.4.2.3.4.2, 4.4 Refs, 4.5.3.2.2.6.4[FN 2004-045]Described the overal l peaking factor uncertainty associated with the Framatome ANP Advanced Mark BW fuel product.
[1 0 CFR 50.90 License Amendment]
5.2
[FN 2005-024]Updated the code descript ion of the pressurizer safety valves.5.2.5, 5.2.5.1, 7.3.1.2, Tables 15.4-16, 15.4-23, & 15.4-26[FN 2005-006]Incorporated editorial corrections to improve readability , corrected spelling, and incorporated changes omitted from previously implemented UFSAR changes.5.5.10.4, 6.2.2.4.2, Table 6.3-1[FN 2004-049]Changed the ASME Code reference for
inservice testing activities from Section XI to a general reference to the ASME Code.Tables 6.2-44, 6.2-45, &
6.2-46, 6.3.2.2.6, 6.3.4.4
[FN 2004-018]Revised the safety analysis flow rate for
maximum low head safety injection recirculation mode flow rate for the LHSI pump net positive suction head analysis.
6.3.2.1.4.2[FN 2005-027]Allowed that check valves 1-CH-240 and
2-CH-155 can be fitted with or without a spring.6.4.1.2, Tables 11.4-1 & 12.1-4[FN 2005-033]Reflected consistent mark number format for the radiation monitoring system.6.4.1.3.3, Table 6.4-1[FN 2004-031]Updated the concentration of ethanolamine up to 85%.Tables 7.2-2, 7.5-1, 7.5-2, &
7.5-3[FN 2004-040]Updated the indicated accuracy for the containment pressure (narrow range), pressurizer water level, low reactor coolant
flow, primary coolant flow, pressurizer pressure, steamline pressure, main feedwater flow, and steam flow.Tables 7.2-2, 7.5-1, 7.5-2, &
7.5-3[FN 2005-001]Updated the indicated accuracy for the steam generator water level.Tables 7.2-2 & 7.5-3[FN 2005-002]Updated the indicated accuracy for
overtemperature T and overpower T.Revision 41-09/30/05 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 367.3.1.3.5, 8.3.1.1.2.3, Table 8.3-8, 9.2.1.1, 9.2.1.2.2, 9.2.1.2.5[FN 2003-012]Modified the Unit 1 service water spray array motor-operated valve safety injection signal actuation cross-tie.Table 7.5-2[FN 2005-014]Updated the indicated accuracy for the
refueling water storage tank water level.8.3.1.1.1, Table 8.3-1, Figures 8.2-1 & 8.2-2[FN 2001-040]Removed the 34.5-kV shunt reactor banks from the switchyard.
9.1.4.4.5, Figures 9.1-8 & 9.1-12[FN 2004-019 & F N 2005-007]Modified the fuel handling bridge crane controls with a program mable logic controller and adjustable speed drives.
9.2.1.1
[FN 2005-020]Incorporated editorial changes to
cross-reference and be consistent with the Section 9.2.1.2.5 description of service water pump auto start.
9.2.1.6
[FN 2002-024]Provided for the continued use of corrosion rate
test specimens instead of the probe monitoring system in the service water system.Table 9.2-10[FN 2004-033]Incorporated Well No.
6 into the domestic water supply component design data.
9.3.2.1.2, 9.3.2.1.5, Figure 9.3-2[FN 2005-025]Corrected the description of the sampling system.9.5.1.1, 9.5.1.2.1, Figure 9.5-1, Table 10.4-6[FN 2004-044]Replaced the cooling tower for the Bearing
Cooling System.
9.5.1.2.3[FN 2004-013]Replaced the heat detectors on the Unit 1 main transformers.
9.5.1.6.2[FN 2005-015]Reduced the time allowed to establish a backup fire suppression water system from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to immediately.9.5.5.2, 9.5.7.2, Figures 9.5-6 & 9.5-8[FN 2004-046]Replaced the 2J emergency diesel generator
lube oil and jacket coolant temperature switches with a temperature converter system.
10.4.3, 15.4.1.5.1[FN 2004-047]Incorporated editorial spelling correction and corrected typographical error in reference document number
.Table 11.4-2[FN 2005-008]Updated the isotopic res ponse factors for Kr
-85 and Xe-133 for the condenser air ejector radiation monitors.
Revision 41-09/30/05 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 37 15.1 Refs, 15.2 Refs, 15.3 Refs, 15.4 Refs[FN 2004-038]Updated the RETRAN Topical Report
references.15.3.1,8, 15.3.1.13, 15.3 Refs, Table 15.3-24[FN 2005-009]Incorporated the peak clad temperature penalties and benefits for the small break LOCA for Framatome ANP Advanced Mark
BW fuel. [10 CFR 50.46]18.2.1, 18.2.6, 18.2.9, 18.2.19, Table 18-1[FN 2004-048]Reflected the completion of License Renewal
Commitment Item Nos.
3, 4, 5, 7, 8, 15, and 29.Revision 40-09/30/04 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.Table 2.4-6[FN 2002-047]Provided revised values for bearing lubricating water pump 1-BL-P-1B minimum operating level, required submer gence, and actual submergence.Table 2.4-6[FN 2003-027]Modified the minimum operating level and actual submer gence of one safety-related circulating water screen wash pump.Table 2.4-6[FN 2003-044]Provided revised (1-BL-P-1A) and corrected
(1-BL-P-1B) values fo r bearing lubricating water pumps minimum operating level, required submergence, and actual submergence.
3.8.1.1.13, 3.8.1.1.14, 9.2.1.2.4.2[FN 2003-011]Replaced metal expansion joints with rubber
expansion joints in the service water valve house and tie-in vault.
3.8.1.1.14, 3.8.4.5.4.7, 9.2.1.2.4.2[FN 2004-011]Deleted the description of pressure balanced expansion joints associated with replacement of metal expansion joints with rubber
expansion joints in the service water valve
house and tie-in vault. Incorporated v-cone flow measurement devices in the tie-in vault.
3A.58
[FN 2000-011]Clarified non-destru ctive test personnel compliance with Regulatory Guide 1.58.Revision 41-09/30/05 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 38 3C.1.1, 3C.2.7, 3C.2.7.9, 3C.5.1.2.2, 3C.5.1.8.2, 3C.5.2.2.2, 3C.5.2.8.2, Table 3C-1[FN 2003-051]Replaced the main steam and feedwater line
leak detection sy stem function with daily operator inspections in the mechanical equipment rooms.Table 3C-3, 8.3.1.1.2.3, Table 8.3-8[FN 2004-027]Incorporated editorial co rrections to vital bus panel board mark numbers.
4.1, 4.1 Refs, Table 4.1-2, 4.5 All, 5.1.2.1.2, 6.3.3.12, 6.3.3.13, 6.3 Refs, 7.2.1, 11A.1.1, 11 A Refs, 15, 15.1.2.2, 15.1.9.7, 15.1 Refs, Tables 15.1-2 & 15.1-3, 15.3.1, 15.3.1.8, 15.3.1.9, 15.3.1.10, 15.3.1.1 1, 15.3.1.12, 15.3.1.12.1, 15.3.1.12.2, 15.3.1.13, 15.3.4.2.1, 15.3.4.2.2, 15.3.4.2.3, 15.3.4.2.5, 15.3.4.2.6, 15.3.4.3, 15.3 Refs, Tables 15.3-5 through 15.3-23, Figures 15.3-33 through 15.3-163, 15.4.1, 15.4.1.9, 15.4.1.10, 15.4.1.1 1, 15.4.1.12, 15.4.1.13, 15.4.1.14, 15.4.1.14.1, 15.4.1.14.2, 15.4.1.14.3, 15.4.1.15, 15.4.1.16, 15.4.1.16.1, 15.4.1.16.2, 15.4.1.16.3, 15.4.1.16.4, 15.4.1.17, 15.4.1.18, 15.4.4.1, 15.4.4.2.1, 15.4.4.2.2, 15.4.4.2.3, 15.4.4.3, 15.4.6.1.2, 15.4.6.2.1, 15.4.6.2.1.2, 15.4.6.2.2.2, 15.4.6.2.2.3, 15.4.6.2.3.1, 15.4.6.2.3.2, 15.4.6.2.3.3, 15.4.6.2.3.4, 15.4 Refs, Table 15.4-16 & 15.4-19 through 15.4-28, Figures 15.4-75 through 15.4-109[FN 2001-042, F N 2004-008, F N 2004-025 &
F N 2004-036]Added the description of the Framatome ANP Advanced Mark BW fuel product.
[1 0 CFR 50.90 License Amendment]Table 4.1-2, 4.3.2.2.6, 4.3.2.3.1, 4.3.3, 4.3.4, 4.3.4.1, 4.3.4.2, 4.3.4.2.1, 4.3.4.3, 4.3 Refs, Tables 4.3-6 & 4.3-10, 15.1 Refs, 15.3 Refs[FN 2003-035]Added the description of the Studsvik Core Management System computational model for reactor physics analyses.
4.2.1.4.2, 4.2.3.4.1[FN 2004-035]Updated the feed fuel and burnable poison rod vendor specifications to no longer require ultrasonic or x-ray testing on these
components.Tables 5.1-1 & 5.5-17[FN 2004-009]Corrected the description of pressurizer spray flow rate.
Revision 40-09/30/04 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 39 5.2.3.4[FN 2004-004]Corrected typographical and grammatical
errors.Table 5.2-22, 18.2.3[FN 2004-001]Corrected the description of reactor lower head instrumentation material. Clarified criteria for maintenance and corrective action due to
evidence of borated water leakage.Tables 5.2-22[FN 2004-020]Provided for another t ype of material for
pressurizer safety valve for gings.5.5.1.3.11[FN 2003-040]Incorporated a filter si ze range for the reactor coolant pump shaft seal-w ater injection filters.6.2.1.2.19, Table 6.2-62[FN 2004-012]Added storage boxes for scaffolding materials
in the annulus area of containment.
6.3 Refs, 15.4.1.14.1, Table 15.4-22, 15.4-23, 15.4-24, 15.4-28, Figures 15.4-86, 15.4-87, 15.4-88, 15.4-89, 15.4-90, 15.4-91, 15.4-92, 15.4-93, 15.4-94, 15.4-95, 15.4-96, 15.4-97[FN 2004-037]Incorporated a change to the Unit 1 summary of p eak clad temperatur e penalties and benefits for the large break LOCA. [10 CFR 50.46]Table 6.4-1[FN 2002-040]Removed chemical storage tank 1-WT-TK-18.Table 6.4-1[FN 2004-007]Replaced the bearing cooling biocide product name with the generic chemical compound.Table 7.2-4, 15.4.2.2.2.1, 15.4 Refs[FN 2004-005]Provided analysis results that smaller feedline breaks are protected by the high pressurizer pressure trip.7.3.1.3.5, 8.3.1.1.2.3, Table 8.3-8, 9.2.1.1, 9.2.1.2.2[FN 2002-056]Modified the Unit 2 service water spray array motor-operated valve safety injection signal actuation cross-tie.
8.2.2[FN 2002-021]Clarified the requirements for switchyard stability.8.2.2[FN 2003-025]Replaced switchyard protective relays.
8.3.1.1.2.6, 8.3 Refs[FN 2003-047]Provided for the use of UL 910 fire propagation testing for non-safety related and non-Appendix R applications.
Revision 40-09/30/04 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 40 8.3.1.2.1[FN 2004-023]Introduced compensatory measures that will be
implemented when an instrument bus inverter
is unavailable. [10 CFR 50.90 License Amendment]9.2.1.2.1, 9.2.1.2.2, 9.2.1.3.2
[FN 2003-049]Established the requirement that the service
water spray array supply valves be secured in th e accident position (open) with power removed from the operators in order to change the number of spray ar rays required for loop operability from three to two.9.2.2.2.2, 9.2.2.3.2, Table 9.2-6[FN 2003-001]Converted the mechanical chilled water unit
refrigerant from R-12 to R-134a.Table 9.2-4[FN 2004-014]Replaced auxiliary service water pump, 2-SW-P-4.9.3.4.2.4.21[FN 2004-003]Provided a new packi ng configuration for char ging system modulating valves that have no leakoff line.9.4.1.2, Table 9.4-2[FN 2003-037]Corrected the description of the control and
relay room air supply a nd exhaust flow rates.
9.5.5.2, 9.5.7.2, Figures 9.5-6 & 9.5-8[FN 2003-026]Replaced the 1H emergency diesel generator lube oil and jacket coolant temperature switches with a temperature converter system.
9.5.5.2, 9.5.7.2, Figures 9.5-6 & 9.5-8[FN 2003-045]Replaced the 2H emergency diesel generator lube oil and jacket coolant temperature switches with a temperature converter system.
10.4.8.5[FN 2004-015]Modified the conductivi ty monitoring function for the condensate polishing system.Table 10.4-2[FN 2004-022]Incorporated editorial correction to properly
locate the flash evaporator duty and shell
design pressure data.
Figure 11.3-1, 11.4.3, 11.4.3.2, Table 11.4-4, 12.2.4
[FN 2003-031]Replaced the Process Vent, Vent A, and Vent B radiation monitors.
12.2.2.1, 12.2 Ref Dwgs[FN 2002-043]Restored the 12.2 Reference Drawings section.
Revision 40-09/30/04 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 41 15.2.4.2.2[FN 2004-032]Corrected the description of valves required to
be locked in order to provide isolation of
primary grade makeup water from the reactor coolant system.
15.2.4.2.3[FN 2004-010]Corrected typographical error in reference
document number
.15.4.1, 15.4.1.1, 15.4.1.4, 15.4.1.5.2, 15.4.1.5.6, 15.4 Refs, Table 15.4-1, 15.4-2, 15.4-3, 15.4-4, &
15.4-5, Figures 15.4-1, 15.4-2, 15.4-3, 15.4-4, 15.4-5, 15.4-6, 15.4-7, 15.4-8, 15.4-9, 15.4-10, 15.4-11, 15.4-12, 15.4-13, 15.4-14, 15.4-15, 15.4-16, 15.4-17, 15.4-18, 15.4-19, 15.4-20, 15.4-21, 15.4-22, 15.4-23, 15.4-24, 15.4-25, 15.4-26, 15.4-27, 15.4-28, 15.4-29, 15.4-30, 15.4-31, 15.4-32, 15.4-33, 15.4-34, 15.4-35, 15.4-36, 15.4-37, 15.4-38, 15.4-39, 15.4-40, 15.4-41, 15.4-42, 15.4-43, 15.4-44, 15.4-45, 15.4-46, 15.4-47, 15.4-48, 15.4-49, 15.4-50, 15.4-51, 15.4-52, 15.4-53, 15.4-54, 15.4-55, &
15.4-56[FN 2004-016]Revised the large break loss-of-coolant
accident analyses.15.4.1.14.2, Table 15.4-25, 15.4-26, 15.4-27, & 15.4-28, Figures 15.4-98, 15.4-99, 15.4-100, 15.4-101, 15.4-102, 15.4-103, 15.4-104, 15.4-105, 15.4-106, 15.4-107, 15.4-108, 15.4-109[FN 2004-026]Incorporated a change to the Unit 2 summary of p eak clad temperatur e penalties and benefits for the large break LOCA. [10 CFR 50.46]17.2.1.2.D.3.c, Figure 17.2.1-3[QA 2004-004]Deleted the Manager Nuclear Engineering's 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[QA 2004-005]
Updated terminology to the current naming convention for inservi ce inspection personnel.
[1 0 CFR 50.54(a)(3)]
17.2.10[QA 2003-001]
Updated the description of qualification requirements for pe rsonnel performing non-destructive examinations.
[1 0 CFR 50.54(a)(3)]
Revision 40-09/30/04 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 42 18.3.2.4, 18 Refs, Table 18-1[FN 2003-052]Completed evaluation of and eliminated enhanced inspections for safety injection
accumulator nozzles' and char ging line nozzles' environmentall y-assisted fatigue.
Revision 39-09/30/03 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.KWI, 3.6.2.4, Table 3.7-3, 3.11.2.9, 3A.46.1, 5.2.2.4, 6.2 Refs, 13.2.1[FN 2003-041]Incorporated editorial corrections of a key
word index reference, misspelled words, and a
table footnote.1.1, 2.1.3.1, Table 3.8-7, 3.11.2.2, 3E.3.4, 4.0, 4.2.3.1.4, 5.1, Tables 5.1-1, 5.2-20, 5.2-21, 5.4-2, & 5.4-3, 5.5.2.3.4, 6.1, 7.1, 8.1, 9.1, 10.1, 1 1.0, 18.0, 18.1, 18.1.1, 18.1.2, 18.1.3, 18.1.4, 18.2, 18.2.1, 18.2.2, 18.2.3, 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[FN 2002-010]Reflected the increased operating life basis from 40 to 60 years and added Chapter 18 [1 0 CFR 54.21] to describe the programs and activities that manage the ef fects of aging materials during the extended operation period associated with license renewal.2.3.3.2.5.1, 2.3.4.3, Tables 2.3-15 & 2.3-16, Table 7.5-2, 7.7.1.10[FN 2002-011]Replaced the emergenc y response facilities computer systems.Table 2.4-6[FN 2003-030]Modified the submergence of one auxiliary flash evaporator pump a nd three screen wash pumps.3.1.36.2, 6.2.2.3, 6.2.2.4.1
[FN 2002-004]Revised the frequency of inspection for the
quench spray and recirculation spray nozzles.
[1 0 CFR 50.90 License Amendment]
Revision 40-09/30/04 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 433.1.53.1, 6.2.2.2, 6.2.3.1.1, Table 6.2-40, 6.3.3.4, Tables 6.3-1 & 6.3-5, 9.1.4.5, 9.3.4.2.4.8, 15.2.13.2.2[FN 2000-027 & F N 2000-027B]
Revised the boron concentr ation limits for the refueling water storage tank, casing cooling tank, safety injection accumulators, and the spent fuel pool in accordance with the
T echnical Specifications. [10 CFR 50.90 License Amendment]Table 3.2-1, 6.4.1.3[FN 2003-021]Accurately reflected control room dose limits, auxiliary shutdown pane l plant status, and refueling procedures. Deleted reference to the guide tube cover handl ing tool. Changed air conditioning chiller room fans from "supply" to "exhaust."
3.7.2.7.3, 3.7.2.7.3.1, 3.7.2.7.3.2, 3.7.2.7.3.3, 3.7.2.7.3.4, 3.7.2.7.3.5, 3.7.3.1.3.7, 3.7 Refs, 4.2.3.2.2, Table 5.1-1, 5.2.3.1, 5.2.3.1.1, 5.2.3.3.1, 5.2 Refs, Tables 5.2-2, 5.2-3, 5.2-16, 5.2-22, & 5.2-27, 5.4.1.1, 5.4.4.2, 5.4.4.3, Tables 5.4-1, 5.4-4, &
5.4-5, Figures 5.4-1 & 5.4-2, 6.2.1.1.1.3, 7.7.1.9.1, Table 9.6-1[FN 2002-054]Replaced the Unit 2 reactor vessel closure head.3.7.2.7.3, 3.7.2.7.3.1, 3.7.3.1.4, 4.1, 4.2.3.2.2, Table 5.1-1, 5.2.3.1, 5.2.3.1.1, 5.2.3.3.1, 5.2 Refs, Tables 5.2-2, 5.2-3, 5.2-22, 5.2-26, & 5.2-27, 5.4.1.1, 5.4.2, 5.4.4.2, Tables 5.4-1, 5.4-4, 5.4-5, Figures 5.4-1 & 5.4-2, 6.2.1.1.1.3, 7.7.1.9.1, Table 9.6-1[FN 2003-008]Replaced the Unit 1 reactor vessel closure head.3.8.1.5.1, 3.8.1.5.2, 3.8.1.5.2.1, 3.8.1.5.3, 3.8.2, 3.8.2.1.2.3, 3.8.2.1.2.4, 3.8.2.3, 3.8.2.7, 3.8.2.7.1, 3.8.2.7.2, 3.8.2.7.3, 3.8.2.9, 3.8.2.9.1, 3.8.2.9.2, 3.8.2.9.3, 3.8.2.9.4, 3.8.2.9.5, 3.8 Refs, 3A.10, 3A.15, 3A.18, 3A.19
[FN 2002-051 & F N 2003-005]Completed the restora tion of construction opening in the containm ent structure for the Unit 2 reactor pressure vessel head replacement.3.8.1.5.3.1, Table 17.2-0[FN 2002-050]Provided for the repair and testing of a
temporary opening in the containment due to reactor vessel head replacement. [10 CFR 50.54(a)(3)]
Revision 39-09/30/03 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 44 3.8.2.9, 3.8.2.9.2, 3.8.2.9.4, 3.8.2.9.5[FN 2003-007 & F N 2003-019]Completed the restora tion of construction opening in the containm ent structure for the Unit 1 reactor pressure vessel head replacement.
3.8.4.5.4.2, 3.8.4.5.4.5, Figures 3.8-41 & 3.8-43[FN 2002-022 & F N 2002-029]Replaced service water discharge piping mechanical (metal) expansion joints with rubber expansion joints.
Figure 3.8-4, 5.1.1.9[FN 2002-055]Corrected spelling and typographical errors.
4.2.1.1.2, 4.2 Refs[FN 2002-057]Included description of the consideration of
corrosion of zirconium-based fuel assembly
structural components.
4.2.1.2, 4.2.1.2.1, 4.2.1.2.2, 4.2.3.3.1, Table 4.2-2[FN 2002-049]Incorporated small dimensional changes for
fuel assemblies and accurately reflected burnable poison assembly design.
4.2.3.4.2
[FN 2002-044]Eliminated the seismic al lowance in the control rod drop time surveillance requirement.
Figure 4.4-21, 7.9.2.1, Table 7.9-1[FN 2003-006]Described that Unit 2 incore instrumentation thermocouple 2-RC-TC-T9 was abandoned in
place at core location F5.
5.1.1.9, 5.2.3.4, 5.2 Refs, 6.2.1.2.15, Table 6.3-8, 9.1.4.4.2, Figures 9.1-5 & 9.1-6, 9.6.4.4, Table 9.6-1[FN 2002-052]Modified the service structure, cooling air shroud and shroud support, insulation, and in termediate lift ring for the Unit 2 reactor ves sel head replacement.
5.1.1.9, 5.2.3.4, 5.2 Refs, 6.2.1.2.15, Table 6.3-8, 9.1.4.4.2, Figures 9.1-5 & 9.1-6, 9.6.4.4, 9.6 Refs, Table 9.6-1[FN 2003-009]Modified the service structure, cooling air
shroud and shroud support, insulation, and
in termediate lift ring for the Unit 1 reactor ves sel head replacement.
5.2.2.2[FN 2003-003]Reflected Low Temperature Overpressure Protection System (LTOPS) bistable settings that were changed to preserve LTOPS setpoints.5.5.3.2.1, Table 5.5-6[FN 2003-018]Removed a thermal sleeve from the Unit 1 accumulator safety injection line to reactor coolant loop 2.Revision 39-09/30/03 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 45 Unit 2 only: 6.1, 6.2.1.1.1.1, 6.2.1.1.1.2, 6.2.1.1.1.3, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.2.2, 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.4, 6.2.2.3.2.6, 6.2.2.3.3, 6.2.6.3, Tables 6.2-1, 6.2-2, 6.2-4, 6.2-1 1, 6.2-12, 6.2-13, 6.2-38, 6.2-44, 6.2-45, & 6.2-56, Figures 6.2-61, 6.2-62, 6.2-63, 6.2-64, 6.2-65, 6.2-66, &
6.2-82, 6.3.2.2.2, 6.3.2.2.6, Table 6.3-9, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-1 1, 6.3-12, &
6.3-13[FN 2002-046]Implemented the Unit 2 revised LOCA containment integrity analysis. [10 CFR 50.90 License Amendment]
6.1, 6.2.1.1.1.1, 6.2.1.1.1.2, 6.2.1.1.1.3, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.2.2, 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.4, 6.2.2.3.2.6, 6.2.2.3.3, 6.2.6.3, Tables 6.2-1, 6.2-2, 6.2-4, 6.2-11, 6.2-12, 6.2-13, 6.2-38, 6.2-44, 6.2-45, & 6.2-56, Figures 6.2-61, 6.2-62, 6.2-63, 6.2-64, 6.2-65, 6.2-66, &
6.2-82, 6.3.2.2.2, 6.3.2.2.6, Table 6.3-9, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-1 1, 6.3-12, &
6.3-13[FN 2000-042 & F N 2002-015]Implemented the Unit 1 revised LOCA containment integrity analysis. [10 CFR 50.90 License Amendment]6.2.1.4.4, Table 6.2-37 & 6.2-53[FN 2002-030]Removed water-filled penetrations from the
10 CFR 50, Appendix J Type C Program.
6.4.1.2, 6.4.1.3, 6.4 Ref Dwgs, 9.4.1.1, 9.4.1.2, 9.4.1.3, 9.4.1.5, Table 9.4-2[FN 2001-029]Installed two new cont rol room bottled air trains to provide a total of four trains supplying breathing air and pressurization.
7.2.1.1.2, Figure 7.2-4[FN 2003-014]Reformatted the equations describing overtemperature delta T and overpower delta T setpoints.8.1.2[FN 2002-023]Eliminated the battery charger for the spillway gate supervisory control system batteries.
8.2.1, Figures 8.2-1 & 8.2-2[FN 2003-024]Installed an additional 500/230 kV transformer and rearranged the 230 kV bus in the switchyard.
Figure 8.2-1[FN 2003-020]Replaced vital bus inverters 2-I & 2-II and added an additional bypass tran sformer for each unit.8.3.1.1.2.3, 8.3.1.2.1, 8.3.1.2.2.4, Table 8.3-8[FN 2003-004]Replaced vital bus inverters 1-I & 1-II.Revision 39-09/30/03 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 468.3.1.1.2.3, 8.3.1.4.1.4, 8.3.1.2.2.4, Table 8.3-8[FN 2002-017]Installed replacement vital bus inverters 2-I and 2-II.9.1.4.9.1, 9.1.4.9.2, 9A.2, 9B.2, 9B.3, 15A.1[FN 2003-029]Placed a cask pedestal in the cask loading area
of the spent fuel storage pool.9.2.3.1, Table 9.2-10[FN 2003-034]Refurbished Well 4 of the domestic water system.9.3.1.3.2[FN 2002-041]Provided cross-reference to UFSAR
Section 3.1.19.2.9.3.4.2.4.20, Table 9.3-5, 12.1.6.2[FN 2003-015]Corrected the description of the operation of the primary ion exchangers.
9.5.1.3.1.3[FN 2003-033]Corrected the description of the auxiliary
feedwater pump rooms as 10 CFR 50 Appendix R areas.9.5.2.1.1
[FN 2003-017]Allowed the public addr ess system to be powered from either vital bus 1-II or 2-II.9.5.5.2, 9.5.7.2, Figures 9.5-6 & 9.5-8[FN 2003-013]Replaced the 1J emergency diesel generator
lube oil and jacket coolant temperature
switches with a temperature converter system.
10.2
[FN 2002-035]Clarified the operating pr essure limit for high pressure turbine gland steam header pressure.
10.4.2.2[FN 2002-039]Provided a clarified desc ription of the function of the circulating water vacuum priming system to remove noncondensable gases.
10.4.8.2, 10.4.8.4, 10.4.8.5[FN 2002-012 & F N 2002-048]Upgraded the Unit 1 and Unit 2 condensate polishing systems with programmable logic controllers.11.4.2.1, 11.4.2.2, 11.4.2.3, 11.4.2.4, 11.4.2.5, 11.4.3, 11.4.3.1.1, 11.4.3.1.2, 11.4.3.1.3, 11.4.3.2, 11.4.5, Table 11.4-1 & 11.4-2[FN 2003-038]Replaced the Process Vent, Vent A, and Vent B radiation monitors.
15.1.2.3[FN 2002-031]Provided an enhanced te xt description of rod cluster control assembly bank operability consistent with the T echnical Specifications.
15.4 Refs, Table 15.4-5[FN 2003-028]Incorporated a change to the summary of peak clad temperature penaltie s and benefits for the lar ge break LOCA. [10 CFR 50.46]Revision 39-09/30/03 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 4717.2.0.2, Table 17.2-0, 17.2.2.1, 17.2.2.5, 17.2.2.6, 17.2.10, 17.2.17
[FN 2003-023]Made editorial corrections to correctly refer to Table 17.2-0.17.2.1.1.A, 17.2.1.2.B, 17.2.1.2.B.1, 17.2.1.2.B.1.b.1.1, 17.2.1.2.C.1, 17.2.16.2.B.2, 17.2.16.2.C, 17.2.1.16.2.D, Figures 17.2.1-1 & 17.2.1-2, Table 17.2-0, App C A.8.e, B.6.e, B.6.i, B.7.c, &
B.8[FN 2003-016]Revised organizational titl es of the Senior Vice President Nuclear Operations, Shift Manager, and Unit Supervisor. [10 CFR 50.54(a)(3)]
17.2.1.2
[FN 2003-010]Assigned responsibility for maintenance of
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[FN 2002-008]Deleted the description of and reference to the
Nuclear Oversig ht Board. [10 CFR 50.54(a)(4)]
2.3.4.3
[FN 2002-037]Updates the Meteorological Information Dose
Assessment System (MIDAS) information and
how the plant computer processes the data.
Revision 38-09/03/02 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
KWI[FN 2002-026]Deleted "Hypochlorite Treatment" from the Key Word Index listing for the domestic water system.Figure 1.2-1[FN 96-021]Added the Independent Spent Fuel Storage Installation to the Site Plan.
Revision 39-09/30/03 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 48 2.4.3, 2.4.14, 2A.4, 2A.5, 3.1.7.2, 3.8.4.5.2, 3.8.4.5.3, 3.8.4.6, 3.8.4.8, Table 3.8-15, 3A.13, 3A.16, 4.3.1.3, 4.3.1.5, 4.3.2.2.6, 4.3.2.4, 4.3.2.5.2, 4.3.2.5.6, 4.4.5.3, 5.1.3.1, 5.2.1.2, 5.2.4.1.1, 5.2.4.2, Table 5.2-4, 5.5.4.4, 5.5.7.3, 5.5.9.2.2, 6.2.1.4.5, 6.2.2.4.1, 6.2.4.4, 6.2.7.5, Tables 6.2-50, 6.2-58, &
6.2-59, 6.3.2.1.4.5, 6.3.2.1.4.7, 6.4.1.2, 6.4.1.3.1, 6.4.1.4, 7.1.1, 7.2.1, 7.2.1.1, 7.2.1.10, 7.2.2.1.1, 7.2.2.1.2, 7.2.2.2.1.7, 7.2.3.1, 7.2.3.2, Table 7.2-5, 7.3.1.1.1, 7.3.2.1.5.9, Table 7.3-2, 7.7.1.3.3, 7.7.1.13.1, 7.7.2.2, Table 7.7-2, 9.1.2, 9.1.4.6.1.1, 9.2.1.5, 9.2.2.6, 9.2.2.7, 9.2.5.4, 9.3.4.2.5.2, 9.3.4.3.1, 9.3.4.4, 9.4.1.1, 9.4.1.3, 9.4.1.4, 9.4.5.3, 9.4.5.4, 9.4.6.4, 9.4.8.5, 9.5.4.2, 9.5.4.4, 9.6.3, 10.3.2, 11.3.3.2, 11.4.2, 11.4.2.14.2, 11.4.3.1.1, 11.4.3.1.2, 11.4.3.1.3, 11.4.5, 11.5, 11C cover, 12.0, 12.1.4.1, 12.2.4, 12.3.1, 13.4, 13.5, 13.5 Refs, 14A, 15.1.2.3, 15.2.3.1, 15.2.6.3.1, 15.2.10.1, 15.3.1.4, 15.4.1.2, 15.4.1.4, 15.4.1.7, 15.4.5.2.1, 15.4.5.2.3, 15.4.7.2.1, 15.4.7.2.4.1, 15.4.7.2.4.4, 16.1, 16.2
[FN 2002-014]Implemented the conversion to Improved
Technical Specifications including the relocation of requirements to the UFSAR. [10 CFR 50.90 License Amendment]2.4.10, 2.5.5, 2A.3, 2A.4, Table 3.2-1, 3.8.6, 3.8.6.1, 3.8.6.2, Figure 3.8-61[FN 2001-006]Provided description of the flood protection dike.2.4.11.4[FN 2000-040]Included reservoir disc har ge flow reductions for drought conditions in accordance with the Lake Level Contingency Plan.
3.1.53.2, 4.3.1.1, 4.3.1.5, 4.3.2.1, 4.3.2.7, 4.3 Refs, 9.1.2, Table 15.3-1
[FN 2000-037]Established spent fuel pool soluble boron
concentration and fuel assembly loading
restrictions based on burnup and enrichment.
Increased maximum fuel enrichment from 4.3 to 4.6 weight percent U-235. [10 CFR 50.90 License Amendment]
Revision 38-09/03/02 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 49 3.1.53.2, 6.2.2.2, 6.2.3.1.1, 6.2.3.3, Table 6.2-40, Figures 6.2-76 & 6.2-77, 6.3.3.4, Tables 6.3-1 & 6.3-5, 9.1.4.5, 9.3.4.2.4.8, 15.2.13.2.2, Table 15.2-1[FN 2001-041]Increased the boron concentration in the spent
fuel pool and Unit 1 refueling water storage tank, casing cooling storage tank, and safety injection accumulators. [10 CFR 50.90 License Amendment]3.8.2.1.4.1, 4.3.2.7, Table 5.5-17, 15.4.5.3[FN 2002-036]Corrected typographical and editorial errors.
3C.3.3, 3C.5.4.6.2, & 10.4.6.5[FN 2001-038]Provided discussion of the auxiliary building
ambien t temperature m onitoring system for detection of a high energy line break and associated automatic/manual actions.
4.2.1.3.1, 4.2 Refs, 4.4.2.8.1, 4.4.3.4.2, 4.4 Refs, 15.4 Refs[FN 2002-028]Supplemented the fuel rod design criteria references to new fuel performance models.
5.2.5.1, 5.2 Refs[FN 2001-039]Updated references to the current inservice
inspection interval.6.2.2.1, 7.1.3.2.4, Table 7.5-3, 8.3.2.1, 9.5.1.3.1.4
[FN 2001-022]Incorporated technical a nd editorial corrections and clarifications related to containment depressurization systems, environmental requirements of the reactor trip system, control room indicators, a nd dc power system.
6.2.2.3.2.1
[F N 2001-016]Updated the containment analysis NPSH
available for the recirculation spray pumps.6.2.3.2, Table 6.2-50, 9.4.2.3, 9.4.6.3, 9.4.8.2[FN 2001-025]Indicated that the maximum relative humidity of the auxiliary building charcoal filter inlet air will be below 70%. Clarified the design description of the primary ventilation system.
6.2.5.3, 6.2 Refs, Tables 6.2-54 & 6.2-59, Figures 6.2-80, 6.2-81, 6.2-82, 6.2-86, 6.2-87, 6.2-88, 6.2-89, 6.2-90, &
6.2-91[FN 2002-016]Reanalyzed hydrogen concentration in
containment following a LOCA.
6.2 Refs, 6.4.1.3.3, Table 6.4-1[FN 2001-033]Corrected a typographical error and incorporated changes omitted from a previously implemented UFSAR change.
Revision 38-09/03/02 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 50Tables 6.2-44 & 6.2-45, 6.3.2.2.6, 6.3.4.4[FN 2002-005]Revised the safety analysis flow rate for maximum low head safety injection recirculation mode flow rate NPSH analysis. Clarified the safety injection pump test description.Table 6.2-50, 9.4.8.1, 9.4.8.4[FN 2000-038]Clarified that auxiliary building central exhaust is manually aligned to the filters rather than automatically. 6.4.1.3.3, Table 6.4-1
[FN 2001-035]Deleted the product name for zinc chloride and revised its storage tank capacity
.6.4.1.3.3, Table 6.4-1[FN 2002-013]Updated the description of potentially
hazardous chemicals stored on the plant site to add sodium hydroxide, hydrochloric acid, and hydrogen peroxide. Eliminated references to specific products and methods.
Figures 7.7-6 & 7.7-7[FN 2001-026]Updated the figure representations of the
pressurizer pressure and level control and
pressurizer heater control systems to agree with the text description.
Figure 8.2-1[FN 2001-034]Corrected a minor error in the figure
representation of the 34.5 kV system in the switchyard.
8.3.1.1.2.3, 9.5.1.1, 17.2.1.2, 17.2.5[FN 2001-032]Removed terminology associated with the former 10 CFR 50.59 regulation and incorporated wording from the current rule.
9.2.1.2.1, 9.2.1.4.1
[FN 2000-012]Clarified the two-valve isolation from the
service water header provided by the manual isolation valve and the single check valve.
Added stainless steel service water piping and
Hastelloy C276 valves.
9.2.1.2.1, Figure 9.2-1[FN 2000-036]Reconfigured the service water supply and
return headers for the instrument air compressors and the charging pump lube oil and gear coolers.9.2.1.2.4, Table 9.2-4
[FN 2001-020]Replaced the service water air system
compressor, dryer, and receiver tank.
9.2.2.3.1[FN 2001-028]Clarified the component cooling system thermal relief requirements.
Revision 38-09/03/02 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 51 9.3.2.1.2, 9.3.2.1.3, Figure 9.3-2[FN 2001-031]Corrected the description of the steam generator on-line chemistry monitoring system.
9.3.2.2, 9.3 Refs[FN 2002-007]Clarified the status of the High Radiation
Sampling System - Post-Accident.
[1 0 CFR 50.90 License Amendment]
9.5.1[FN 2002-009]Clarified the description of the low pressure
carbon dioxide system zone isolation.
9.5.1.1[FN 2001-036]Identified fire protecti on systems that are not required to satisfy re gulatory requirements.
[1 0 CFR 50.48]9.5.1.1
[FN 2002-003]Identified fire protecti on systems that are not required to satisfy re gulatory requirements.
[1 0 CFR 50.48]Figure 15.2-44, 15.4.6.2.3.4[FN 2002-019]Corrected a typographical error and
in corporated a cha nge omitted from a previously implemented UFSAR change.
15.4.2.2.2.2, 15.4 Refs
[FN 2002-020]Incorporated the evaluation of steam generator
mid-deck plate pressure differential on safety analysis transients.
17.2.1.1, 17.2.1.2, 17.2.10, Figures 17.2.1-1, 17.2.1-2, &
17.2.1-3[FN 2002-006]Modified organizational titles and realigned certain reporting relationships within the Nuclear Business Unit. [10 CFR 50.54(a)(3)]
17.2.1.2, Figures 17.2.1-1 &
17.2.1-3[FN 2001-037]Relocated the Records Management Program or ganization from General Services to Nuclear Engineering. [10 CFR 50.54(a)(3)]17.2.1.2, 17.2.3, 17.2.5, 17.2.6, 17.2.11, 17.2.15, 17.2.16, 17.2.18, 17.2 Refs, Table 17.2-0, Appendix C[FN 2001-021]Relocated North Anna Power Station current technical specification requirements for the
Management Safety Review Committee, Station Nuclear Safety and Operating Committee, and Station Nuclear Safety to the QA Topical Report. [10 CFR 50.90 License Amendment]17.2.7[FN 2002-032]Updated the description of the organizational 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 38-09/03/02 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 52 Revision 37-09/04/01 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
1.1, 1.2.3, 1.3.2, 1.5, 1.5.1, 1.5.1.1, 1.5.1.2, 1.5.1.3, 1.5.1.4, 1.5.1.5, 1.5.1.6, 1.5.2, 1.5.2.1, 1.5.2.2.1, 1.5.2.2.2, 1.5.2.2.3, 1.5.2.2.4, 1.5.2.2.5, 1.5.2.3, 1.5.3, 1.5.3.1, 1.5.3.2, 1.5.3.2.1, 1.5.3.2.2, 1.5.3.2.3, 1.5.3.2.4, 1.5.3.2.5, 1.5.3.2.6. 1.5.3.2.7, 1.5.3.2.8, 1.5.3.2.9, 1.5.3.2.10, 1.5.3.2.11, 1.5.3.2.12, 1.5.3.2.13, 1.5.3.2.14, 1.5.3.2.15, 1.5 Refs, 3.1.23.2, 3.1.53.2, 3.9.1.2.9, 3.9.3.1.4, 3.9 Refs, 3A.19, 3A.80, 5.5.1.1, Figure 6.2-2, 7.7.1.3.3, 7.9.2.1, 7.9.2.2, 9.3.4.2.5.2, 9.3.4.3.1, 1 1A.1.3, 11A.3, 11A Refs, Table 11A-1, & Table 14.1-1[FN 2000-022]Incorporated technical a nd editorial corrections and clarifications related to miscellaneous
portions of the reactor design.2.1.3.3, 3.9.1.2.3, Table 6.4-1, 9.1.4.5[FN 2001-023]Corrected typographical, administrative, and
format errors.
2A, 3.8 Refs
[FN 2000-045]Corrected typographical and editorial errors.Table 3.5-5, 9.5.1.2.1, 9.5.1.2.4.4, 9.5.1.3.1.2, 9.5.1.4.1.2
[FN 2001-011]Updated the description of fire protection and fire fighting equipment.
3.7.2.5, 3.7.3, 3.7.3.2, 3.7.3.2.2.3, 3.7.3.2.2.4, 3.7.3.3.5, 3.7 Refs, 3.9.1.3, 3.10.1, 3.10.2, 3.10.3, 3.10 Refs[FN 2001-007]Incorporated the crit eria and methodology of the generic implement ation procedure for seismic design and equipment verification.
[Unresolved Safety Issue A-46]3.8.1.1.6, 9.1.4.4.12, 9.5.9.1, 9.5.9.2[FN 96-024]Installed Helium and Va cuum Drying System equipment that supports loading of
Independent Spent Fuel Storage Installation casks. Updated the cask trolley description.
Figure 3.8-31[FN 2000-033]Deleted pump house gate and fence symbols
and labels from the service water reservoir figure representation.
3A.46.1, 6.2.2.1, 12.1.4.2, 12.2.6, 15.2.4.2.2[FN 2001-009]Corrected typographical spelling errors and electronic scanning discrepancies, and incorporated a phrase omitted from a previously implemented UFSAR change.
Revision 52-09/29/2016 NAPS UFSAR 53Table 3C-2[FN 2001-001]Revised operating pressure and temperature, line size, seismic cla ss, and quality class parameters for specific high-energy lines outside containment.4.2.1.2, Table 4.2-2, 4.3.2.6, Figures 4.3-38 & 4.3-39, 6.2.1.3.1.1, 6.2.1.3.1.3, 6.2 Refs, 6.3.2.2.1, Figures 6.4-2 & 6.4-3, 7.2.2.1.2.1, 7.6.3.2, 11.1.1.2, Table 11.1-11, 15, 15 Refs, 15.1, 15.1.2.1, 15.1.2.2, 15.1.2.3, 15.1.3, 15.1.5, 15.1.6, 15.1.7.2, 15.1.8.1, 15.1.8.2, 15.1.9.2, 15.1.9.4, 15.1 Refs, Tables 15.1-2, 15.1-3, 15.1-4, 15.1-7, &
15.1-8, Figure 15.1-2, 15.2, 15.2.1.2.1, 15.2.1.2.2, 15.2.2.1, 15.2.2.2.1, 15.2.2.3, 15.2.3.2, 15.2.4.2.2, 15.2.6.1, 15.2.6.1.1, 15.2.6.1.2, 15.2.6.2.1.1, 15.2.6.2.2.1, 15.2.6.2.3.1, 15.2.6.2.3.2, 15.2.7.2.1, 15.2.7.2.2, 15.2.10.3.2, 15.2.10.3.3, 15.2.13.2.1, 15.2.13.2.2, 15.2.13.3, 15.2.14.1, 15.2.14.2.1, 15.2 Refs, Table 15.2-1, Figures 15.2-19, 15.2-20, 15.2-21, 15.2-22, 15.2-23, 15.2-24, 15.2-25, 15.2-26, 15.2-27, 15.2-28, 15.2-29, 15.2-30, &
15.2-31, 15.3.1.3, 15.3.1.4, 15.3.1.5.2, 15.3.1.6, 15.3.3.1, 15.3.3.3, 15.3.4.1, 15.3.5.2, 15.3.7.1, 15.3.7.2, Figure 15.3-29, 15.4.1.5.4, 15.4.1.8.1, 15.4.2.1.2.2, 15.4.2.2.2.1, 15.4.3.4.1, 15.4.3.4.2, 15.4.5.1, 15.4.5.2.3, 15.4.5.2.4, 15.4.6.2.1, 15.4.6.2.1.2, 15.4.6.2.2.5, 15.4.6.2.3.6, 15.4.7.2.4.2, 15.4 Refs, & Table 15.4-15[FN 99-066]Incorporated technical a nd editorial corrections and clarifications related to plant safety analyses.4.2.1.2.2[FN 2001-004]Changed the material of the fuel assembly hold-down spring bolts that attach the springs to the top nozzle.
Revision 37-09/04/01 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 54 4.3.1.1, 4.3.1.3, 4.3.1.5, 4.3.2.1, 4.3.2.2, 4.3.2.2.3, 4.3.2.2.4, 4.3.2.2.5, 4.3.2.2.6, 4.3.2.2.7, 4.3.2.3.1, 4.2.3.2.3, 4.3.2.3.4, 4.3.2.4, 4.3.2.4.2, 4.3.2.4.6, 4.3.2.4.8, 4.3.2.4.9, 4.3.2.5.1, 4.3.2.5.3, 4.3.2.5.4, 4.3.2.5.6, 4.3.2.6, 4.3.2.7, 4.3.2.8.4, 4.3.2.8.5, 4.3.2.9, 4.3.3, 4.3.3.1, 4.3.3.2, 4.3.3.2.1, 4.3.3.2.2, 4.3.3.2.3, 4.3.3.2.4, 4.3.3.2.5, 4.3.3.3, 4.3 Refs, Tables 4.3-1, 4.3-3, 4.3-6, 4.3-7, 4.3-8, 4.3-9, 4.3-10, & 4.3-11, Figures 4.3-4, 4.3-14, 4.3-15, 4.3-16, 4.3-17, 4.3-18, 4.3-19, 4.3-20, 4.3-23, 4.3-37, 4.3-40, 4.3-43, 4.3-44, 4.3-45, &
4.3-46[FN 99-037]Incorporated technical a nd editorial corrections and clarifications related to reactor design nuclear.4.4.1.1, 4.4.1.5, 4.4.2.1, 4.4.2.2, 4.4.2.2.1, 4.4.2.2.2, 4.4.2.2.3, 4.4.2.2.5, 4.4.2.2.6, 4.4.2.3, 4.4.2.3.1, 4.4.2.3.2.1, 4.4.2.3.2.2, 4.4.2.3.3, 4.4.2.3.4, 4.4.2.3.4.1, 4.4.2.3.4.2, 4.4.2.5, 4.4.2.6, 4.4.2.7.1, 4.4.2.7.2, 4.4.2.8.1, 4.4.2.8.2, 4.4.2.8.3, 4.4.2.10.1, 4.4.2.10.2, 4.4.2.10.4, 4.4.2.10.5, 4.4.2.10.6, 4.4.2.10.7, 4.4.2.10.8, 4.4.2.1 1, 4.4.3.1.1, 4.4.3.1.2, 4.4.3.1.3, 4.4.3.2.1, 4.4.3.2.2, 4.4.3.3., 4.4.3.4.1, 4.4.3.4.2, 4.4.3.6, 4.4.3.7, 4.4.3.10, 4.4.4.1, 4.4.4.2, 4.4 Refs, Tables 4.4-1 & 4.4-2, Figures 4.4-1, 4.4-2, 4.4-3, 4.4-7, 4.4-8, & 4.4-15[FN 2000-023]Incorporated technical a nd editorial corrections and clarifications related to thermal-hydraulic reactor design.
5.2.2.2[FN 2001-019]Updated the calculation of the LTOPS enabling temperature.
5.2.2.2, 5.2.3.3.1, 5.2 Refs, Tables 5.2-20 & 5.2-21, 5.4.3.6, 5.4.3.6.1, 5.4.3.6.3.2, 5.4 Refs, Tables 5.4-2 & 5.4-3[FN 2000-048]Revised the analysis basis for reactor coolant system pressure/tempera ture operating limits, LTOPS setpoints, and LTOPS enable temperatures. [10 CFR 50.90 License Amendment]5.2 Refs, & Table 5.2-21[FN 2001-013]Revised the Pressurized Thermal Shock screening calculati on result for Unit 2 vessel weld 05A. [10 CFR 50.61]Revision 37-09/04/01 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 55 6.2.4.1, 6.2 Refs[FN 99-016]Documented the evaluation of isolated water-filled contai nment penetrations potentially susceptible to over-pressurization during a DBA. [Generic Letter 96-06]6.2.4.2, Table 6.2-33, 9.1.4.3.2, 9.1.4.6.3[FN 99-076]Provided additional description of the fuel transfer tube design, the function of its isolation valve, and associated test requirements.6.2.5.3, Table 6.2-59[FN 2001-010]Updated the description of the containment
hydrogen generation analysis.Table 6.2-51, 9.4.8.1[FN 99-054]Clarified the description of testing of the
safety-related ch arcoal filters installed in the auxiliary building and c ontrol room ventilation exhaust systems. [Generic Letter 99-02 and 10 CFR 50.90 License Amendment]Table 6.2-53[FN 2000-050]Corrected a typographical error.
6.3.3.10, 6.3 Refs
[FN 2000-027A]
Incorporated the revi sed cold-to-hot leg
recirculation switchover time associated with increased boron concentration. [10 CFR 50.90 License Amendment]Table 6.3-3, Table 9.3-53[FN 2000-006]Revised the description of the charging/high
head safety injection pumps' material construction.Table 6.4-1[FN 2001-002]Changed the bearing cooling tower biocide to Isothiazolin.
8.3.1.1.1[FN 2000-046]Provided discussion allowing the reserve
station service load shed circuit to be defeated for short periods to support maintenance activities.9.1.3.3.1, Table 9.1-2
[FN 2001-018]Updated the maximum spent fuel pit heat load
analysis results for various refueling scenarios.
9.2.1.2.1, 9.2.1.2.2, 9.2.1.3.1, 9.2.1.2.3[FN 2000-049]Clearly defined the number of service water system reservoir spray a rrays that are required to be operable to meet minimum design basis
requirements.
9.2.1.2.2, Figure 9.2-1[FN 99-032]Implemented periodic blowdown of the service
water reservoir to reduce concentration of
chlorides and other contaminants.
Revision 37-09/04/01 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 56 9.6.4.1[FN 2000-044]Deleted the requirement for Station Nuclear
Safety and Operating Committee review and
approval of safe load path and exclusion area procedure changes prior to use.
9.6.4.4[FN 2000-043]Listed the reactor vessel head stud racks and
the reactor cavity seal ring flip rig as NUREG-0612 special lifting devices.
12.3.1, 12.4.3, 13.2.2.3, 17.2.1.1, 17.2.1.2, 17.2.2.1, 17.2.2.5, 17.2.3, 17.2.7, 17.2.10, 17.2.15, 17.2.16.2, 17.2.17, 17.2.18, Figures 17.2.1-1, 17.2.1-2, &
17.2.1-3, Table 17.2-0[FN 2001-015]Modified organizationa l titles and reporting relationships associated with the entire Nuclear Business Unit. [10 CFR 50.54(a)(3)]
15.2.6, 15.2.6.1, 15.2.6.1.1, 15.2.6.1.2, 15.2.6.2, 15.2.6.2.1, 15.2.6.2.1.2, 15.2.6.2.2, 15.2.6.2.2.2, 15.2.6.2.3, 15.2.6.2.3.2, 15.2.6.3, 15.2.6.3.1, 15.2.6.3.2, 15.2.6.4
[FN 2000-047]Reflected the current design bases that credit
T echnical Specification controls with precluding the preconditions for significant and uncontrolled reactivity insertion during the
startup of an inactive loop. Incorporated conservative analysis of reactivity effects of the isolated loop recirculation activity required by Technical Specifications.15.2.7.2.1, Table 15.2-1, Figures 15.2-20, 15.2-21, 15.2-22, 15.2-23, 15.2-24, 15.2-25, 15.2-26, 15.2-27, 15.2-28, 15.2-29, 15.2-30, & 15.2-31[FN 2001-005]Updated the analysis of the Loss of External Electric Load and/or Turbine Trip transient.17.2.17, Table 17.2-0[FN 99-075]Updated the Quality A ssurance T opical Report description of the retent ion of quality assurance records in electronic media. [10 CFR 50.54(a)(4)]Table 17.2-0[FN 2001-017]Clarified the provision for substitution of experience for a bachelor's degree. [10 CFR 50.54(a)(3)]Tables 17.2-0, 17.2-2, &
17.2-3[FN 2000-004]Reduced records retention requirements
consistent with ANSI N45.2.9 or applicable regulations. [10 CFR 50.54(a)(4)]
Revision 37-09/04/01 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 57 Revision 36-09/01/00 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
KWI, 1.2.2, 1.2 RefDwgs, Ch 2, Tbl 2.1-2, 2.3.4.1, 2.4.1.2, 2.4.2.2, 2.4.3, 2.4.3.1, 2.4.3.2, 2.4.3.3, 2.4.3.4, 2.4.3.5, 2.4.3.6, 2.4.8, Tbl 2.4-6, Figs 2.4-4 & 2.4-7 thru 2.4-15, 2.5.4.3, 2.5.5, Fig 2.5-3, 2A.2.1, 2A.2.4.1.1, 2A.2.4.1.2, 2A.2.5.3, 2A.2.7, 2A.2.8, 3.2.2, Tbl 3.2-1, 3.3.2, 3.5.3, 3.5.4, 3.5.5, Tbl 3.5-5, 3.7.1, 3.7.2, 3.7.2.1, 3.7.2.3, 3.7.2.5, 3.7.2.6, 3.7.2.7, 3.7.2.7.1.7, 3.7.3.1.1, 3.7.3.1.2.2, 3.7.3.1.2.4, 3.7.3.2.2.2, 3.7.5, 3.7 Refs, Tbls 3.7-3 thru 3.7-8, 3.8.1.1.1, 3.8.1.1.5, 3.8.1.1.6, 3.8.1.2, 3.8.1.2.1, 3.8.1.4.7, 3.8.2.1.4.1, 3.8.2.1.4.4, 3.8.2.5, 3.8.2.7.6.1.2, 3.8.2.7.6.1.2.1, 3.8.2.7.6.1.2.2, 3.8.2.7.6.1.2.3, 3.8.2.7.6.1.2.4, 3.8.2.7.6.1.2.5, 3.8.2.7.6.2, 3.8.2.7.6.2.1, 3.8.2.7.6.2.2, 3.8.2.7.6.2.3, 3.8.2.8.1.8, 3.8.3.5, 3.8.4.5.3, 3.8.4.6, 3.8.4.7.5, 3.8.4.7.7, 3.8.4.8, 3.8.5.4, 3.8 Refs, 3.8 RefDwgs, Tbls 3.8-1 thru 3.8-6, 3.8-12, 3.8-15, 3.8-16, &
3.8-19, Figs 3.8-1, 3.8-4, 3.8-12, 3.8-20, 3.8-21, 3.8-23 thru 3.8-25, 3.8-30, 3.8-31, 3.8-35, 3.8-38, 3.8-39, 3.8-42,
& 3.8-52 thru 3.8-59, 3.9.1.2.4, 3.9.1.2.4.1, 3.9.1.2.4.2, 3.9.1.2.6, 3.9.2.2, 3.9.3.3.1, 3.9.3.3.2, Fig 3.9-1, 3.10.1, 3.10.2, 3.10 Refs, Tbl 3.10-1, 3.11 Refs, Tbl 3.11-4, App.
3E, Tbl 3E-8, App.
3E Att. 2, App. 3E Att. 4, App. 3E Att. 5 Fig. 8, 11, & 12, App. 3E Att. 6, 5.2.1.2, 5.2.3.3.2, 5.5.1.4.1, 5.5.1.4.2, 5.5.1.4.2.1, 5.5.1.4.2.2, 5.5.1.4.2.3, 5.5.1.4.2.4, 5.5.1.4.3, 5.5.3.1, 5.5.9.2.2, 5.5.9.3.3, 7.9.1, Tbl 9.6-1, 9B.4.1[FN 99-014]Incorporated technical a nd editorial corrections and clarifications related to civil, structural, and seismic topics.
Revision 52-09/29/2016 NAPS UFSAR 58KWI, 2.3.3.1.2, Table 3.2-1, 3.7.2.1, 3.7.2.6.1.7, 3.7.3.1.1, 3.7.3.1.2.3, 3.7.3.1.2.4, 3.7.3.1.2.5.1, 3.7.3.1.3.2, 3.7.3.2.2.2, 3.8.5, Figure 3.8-32, 4.3.2.2.6, 4.3.2.8.2, 5.5.9.3.3, 5A Att. 1 Table 1, 6.2.1.3.2.5, Table 6.2-52, Tables 6.2-52 & 6.2-54, 6.4.1.5, Table 6A-1, 9.2.2.1, Table 9.2-5, 9.3.3.1, 9.5.1.1, Table 11.5-1[FN 99-048]Corrected cross-refere nces, typographical and editorial errors, and electronic scanning discrepancies and stan dardized equation and footnote notations.1.1, 1.2.7, 1.2.11, 1.4, 1.4.1, 1.4.2, 1.4.3, 1.4.3.1, 1.4.3.2, 1.4.4, 1.4.4.1, 1.4.4.2, Table 1.4-1, 3.2.2, 3.9.2.1, Table 3.11-3, 3A, 3A.20, Table 3A-1, 9.1.3.2, 9.1.3.3.1, 9.1.3.3.3, Table 9.1-2, Figures 9.1-1 & 9.1-3, 9.2.2.1.2, 9.2.2.1.3, 9.2 RefDwgs, Figures 9.2-3 & 9.2-4, 10.2.1.2, 10.2.1.7, Figures 10.2-1 & 10.2-2, 10.4.7.2, Figure 10.4-9[FN 99-069]Incorporated technical a nd editorial corrections and clarifications related to the bearing cooling
and condensate systems.
1.2.5, 2.1.1.3, 2.1.2.1, 3.1.51.2, 6.3.3.5, 9.3.5.1, 9.3.5.2, Tables 9.3-7 & 9.3-8, Figure 9.3-6, Chapter 11, 11.2.1, 11.2.2, 11.2.2.2, 11.2.3, 11.2.5, 11.2.5.1, Table 11.2-1, Figures 11.2-1 through 11.2-4, 11.4.4.1, 11.5, 11.5.2.1, 11.5.2.4, 11.5.3, 11.5.3.1, 11.5.3.2, 11.5.3.3, 11.5.4, 11.5.5, Tables 11.5-1 & 11.5-2, Figure 11.5-3, 11.6.3[FN 99-043]Incorporated technical a nd editorial corrections and clarifications relate d to boron recovery and waste disposal systems.
1.2.8, 8.1.1, 8.1.2, 8.2.1, 8.2.2, 8.2 RefDwgs, Table 8.2-1, Figures 8.2-1 through 8.2-15, 8.3, 8.3.1.1.1, 8.3.1.1.2.3, 8.3.1.2, 8.3.1.2.1, 8.3.1.2.2.3[FN 99-042]Incorporated technical a nd editorial corrections and clarifications related to vital bus and
station service systems.
Revision 36-09/01/00 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 591.2.11, Tables 3.2-1 & 3.9-2, 3.11.1.1, Tables 3.11-1 & 3C-3, 5.2.3.2, Table 5.2-19, 6.3.2.1.2, 9.3.4.1, 9.3.4.1.2, 9.3.4.2.1, 9.3.4.2.2.1, 9.3.4.2.2.3, 9.3.4.2.2.4, 9.3.4.2.4, 9.3.4.2.4.1, 9.3.4.2.4.2, 9.3.4.2.4.5, 9.3.4.2.4.8, 9.3.4.2.4.9, 9.3.4.2.4.13, 9.3.4.2.4.16, 9.3.4.2.4.22, 9.3.4.2.4.23, 9.3.4.2.5.1, 9.3.4.3.1, 9.3.5.2, Tables 9.3-5 & 9.3-6, Figure 9.3-5, 12.1.2.7, 15.2.4.1[FN 99-030]Incorporated technical a nd editorial corrections and clarifications related to Chemical and Volume Control System.
Figure 1.2-2, 9.1.4.4.12[FN 99-025]Added the Fuel Building trolley enclosure.
2.3.2.2.1.3, 2.3.3.2.1, 2.3.3.2.2, 2.3.3.2.4, 2.3.3.2.5.1, Table 2.3-15, 3.11.2.10, 7.7.1.4[FN 2000-019]Incorporated technical a nd editorial corrections and clarifications related to the electrical instrumentation system.
2.4
[FN 99-049]Update the description of the service water reservoir spray array freeze protection.3.1.15.2, 3.11.1.2, 3A.13, 3A.97, Table 3C-3, 6.2.2.3, 6.2.3.2, Tables 6.2-48, 6.2-49, & 6.2-51, 6.3.2.1.4.1, 6.4.1.1, 6.4.1.2, 6.4.1.3, 6.4.1.3.1, 6.4.1.3.3, 6.4.1.4, 7.7.1.12.1, 7.7.1.13, 9.2.3.1, 9.4.1.1, 9.4.1.2, 9.4.1.3, 9.4.1.4, 9.4.1.5, 9.4.1.6, 9.4.2.1, 9.4.2.2, 9.4.2.3, 9.4.3.1, 9.4.3.2, 9.4.3.3, 9.4.3.4, 9.4.4.3, 9.4.5.1, 9.4.5.2, 9.4.5.3, 9.4.5.6, 9.4.5.7, 9.4.6.1, 9.4.6.2, 9.4.6.3, 9.4.6.4, 9.4.6.5, 9.4.7.1, 9.4.7.2, 9.4.7.3, 9.4.7.4, 9.4.7.5, 9.4.8, 9.4.8.1, 9.4.8.2, 9.4.8.3, 9.4.8.5, 9.4.9.1, 9.4.9.2, 9.4.9.3, 9.4.9.4, Tables 9.4-2 & 9.4-4, Figures 9.4-1 through 9.4-6, 9.5.1.2.2.1, 9.5.9.2, 9.5.10.3, Table 9.5-5, 11.3.5.7, 11.3.5.8, 12.1.2.10, 12.2.1, 12.2.2, 12.2.2.4, 12.2.4, 12.2.5.2, 15.4.5.2.3[FN 99-044]Incorporated technical a nd editorial corrections and clarifications related to the ventilation system.3.1.42.2, Table 3.9-1, 9.2.2.1.3, 9.2.2.2.1, 9.2.2.2.4, 9.2.2.3.1, 9.2.2.3.3, 9.2.2.5.1, Tables 9.2-5, 9.2-8, &
9.2-9, Figures 9.2-2 & 9.2-3[FN 99-053]Incorporated technical a nd editorial corrections and clarifications relate d to component cooling water system.
Revision 36-09/01/00 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 603.1.46.2, 3.1.47.2, 3.1.48.2, 3.11.2.3, 5.2.4.1.1, 6.1, 6.2.1.1.1.1, 6.2.1.2.6, 6.2.1.2.9, 6.2.1.2.13, 6.2.1.3.1.1, 6.2.1.3.2.1, 6.2.1.3.2.3, 6.2.1.3.2.4, 6.2.1.3.2.5, 6.2.1.3.2.6, 6.2.1.4.2, 6.2.1.4.3, 6.2.1.4.4, 6.2.2.1, 6.2.2.2, 6.2.2.3, 6.2.2.3.2.4, 6.2.2.3.2.7, 6.2.2.3.3, 6.2.4.4, 6.2.6.2, 6.2.6.3, 6.2.7, 6.2.7.2, 6.2.7.3, 6.2.7.4, 6.2.7.5, 6.2 Refs, Tables 6.2-22 through 6.2-28, 6.2-30, 6.2-34 through 6.2-37, 6.2-39, &
6.2-58, Figures 6.2-11, 6.2-13, 6.2-15 through 6.2-18, 6.2-27, 6.2-28, 6.2-46, 6.2-84, &
6.2-85, 6.3.3.12, Table 6.3-8[FN 99-020]Incorporated technical a nd editorial corrections and clarifications related to containment systems.3.1.53.2, 4.2.1.4.1, 4.2.1.4.2, 6.2.2.2, 9.1.1, 9.1.2, 9.1.4.2, 9.1.4.3.1, 9.1.4.4.1, 9.1.4.4.4, 9.1.4.4.6, 9.1.4.4.8, 9.1.4.4.10, 9.1.4.4.12, 9.1.4.5, 9.1.4.6.6.1, 9.1.4.7, Figure 9.1-4[FN 99-067]Incorporated technical a nd editorial corrections and clarifications related to the fuel handling system.3.6.2.3[FN 96-038]Revised the list of piping runs subject to
augmented inservice inspection. [10 CFR 50, Appendix A, GDC 4]3.6.2.3, 3.6.2.4, 3.6.2.5.3, 3.6.3.2.1, 3.6.3.2.2, 3.6.3.3, 3.6 Refs, 3C.1.1, 3C.1.2, 3C.1.3, 3C.2.7, 3C.2.7.1, 3C.2.7.2, 3C.2.7.3, 3C.2.7.9, 3C.4.3, 3C.5.1.1, 3C.5.1.1.1, 3C.5.1.1.2, 3C.5.1.1.3, 3C.5.1.2.2, 3C.5.1.8.1, 3C.5.2.1, 3C.5.4.1, 3C.5.4.6.2, 3C.5.4.9, 3C RefDwgs, Tables 3C-1 through 3C-4, & 3C-7, Figures 3C-3, 3C-12, 3C-13, 3C-22 through 3C-24, & 3C-26, 3F.1, 3F.3, 3F.4, 3F Refs, Tables 3F-1, 3F-3 through 3F-7, Figures 3F-1, 3F-4, 3F-6, 3F-7, 3F-12, App 5A Att.1 Table 1, 9.3.4.2.5.2[FN 99-072]Incorporated technical a nd editorial corrections and clarifications related to the high ener gy line break report.
3.8.2.1.4[FN 99-059]Incorporated a description of the containment liner repair procedure for through-wall defects.
Revision 36-09/01/00 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 61 3.8.2.1.4.1, 5.5.4.3.1, 5.6.2.1, 6.4.1.3.2, 7.2.2.3.2, 7.2.2.3.4, 8.3.1.1.2.6, Table 9.2-10, 9.3.3.2, 9.4.8.5, 9.5.1, 9.5.1.1, 9.5.1.2.2.1, 9.5.1.2.2.2, 9.5.1.2.3, 9.5.1.2.4.4, 9.5.1.3.1.1, 9.5.1.3.1.3, 9.5.1.3.1.8, 9.5.1.3.1.10, 9.5.1.3.1.1 1, 9.5.1.3.5, 9.5.1.3.6, 9.5.1.3.8, 9.5.1.4.1.2, 9.5.1.5, 9.5.1.6.2, Tables 9.5-1 & 9.5-7, Figures 9.5-1 through 9.5-3, 12.2.5, 12.2 Refs, 12.2 RefDwgs[FN 99-062]Incorporated technical a nd editorial corrections and clarifications related to the fire protection system.3.8.4.8
[FN 2000-029]Updated description of the methodology of calculating service water reserv oir losses.Table 3.8-17, Figure 3.8-33[FN 97-053A]Reincorporated indi vidual piezometer designation numbers. [10 CFR 50.90 License Amendment]3.9, 6.2.2.2, 7.7.1.14, 9.1.3.3.3, Tables 9.2-6, 10.2-7, & 10.2-8, 15.2.10.3.2, Tables 15.4-5 & 15.4-6[FN 2000-005]Incorporated editorial changes consisting of grammatical enhancement, correction of
typographical errors and cross-references, and consistent use of terminology , capitalization, and punctuation.
3.9.2.1, 10.3.1[FN 99-056]Clarified the design code for the main steam
safety system valves.Table 3.9-1, 5.5.2.2, 9.2.3.2, 9.2.3.2.2, 10.1, 10.4.3.2, 10.4.4.3, 10.4.6.2, 10.4.6.3, 10.4.6.5, 10.4.8.2, 10.4 Refs, Tables 10.4-2 & 10.4-4, Figure 10.4-4[FN 99-021]Incorporated technical a nd editorial corrections and clarifications related to feedwater, condensate, steam generator blowdown, and condensate polishing systems.3.11.1.3.1, 3.11.1.3.2, 3.11.1.3.3, 3.11.2.2, 4.2.3.5, 5.5.1.3.9, 7.2.2.3.2, 7.5.1, 7.5.2, Tables 7.5-1 through 7.5-3, 7.7.1.3.3, 7.7.1.4.2, 7.7.1.8.2, 7.7.2.2, 7.7.2.6, Table 7.7-1, Figures 7.7-1, 7.7-3, 7.7-5, 7.7-9, 7.7-10, & 7.7-12[FN 99-057]Incorporated technical a nd editorial corrections and clarifications related to nuclear control
system.Table 3.11-2, 6.1, 6.2.5.2[FN 99-061]Incorporated technical a nd editorial corrections and clarifications related to containment
atmosphere cleanup system.
Revision 36-09/01/00 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 62 3C.5.1.6.1, 3C.5.1.6.2[FN 2000-010]Added a description of the environmental
effects of a high energy line break in the turbine building on the adjacent safety-related equipment located in the control room envelope and emergency diesel generator rooms.Table 3C-3, 15.4.2.1.2.1[FN 2000-025]Incorporated technical a nd editorial corrections and clarifications related to main steam line break feedwater isolation.
Chapter 4, 4.1, 4.4 Refs, Tables 4.1-1 & 4.1-2, 4.2.1.1.1, 4.2.1.1.2, 4.2.1.2, 4.2.1.2.1, 4.2.1.2.2, 4.2.1.3.1, 4.2.1.3.2, 4.2.1.4.2, 4.2.1.4.4, 4.2.2.1, 4.2.3.1.1, 4.2.3.1.3, 4.2.3.2, 4.2.3.2.1, 4.2.3.2.2, 4.2.3.3.1, 4.2.3.3.2, 4.2 Refs, Figures 4.2-6 through 4.2-8, 4.2-10, 4.2-11, &
4.2-16 through 4.2-27
[FN 2000-013]Incorporated technical a nd editorial corrections and clarifications related to the reactor design (mechanical).
4.2.1.4.3[FN 2000-001]Updated the new fuel and insert component
inspection requirements to apply to either preshipment or postshipment inspections.
4.2.3.4.2
[FN 99-046]Incorporated a discussi on of the allowance, taken to account for seismic activity , in the control rod drop time test criteria.
5.1.3.5, 5.1 Refs, 5.5.4.1, 5.5.4.2.1.1, 5.5.4.2.1.3, 5.5.4.2.2.1, 5.5.4.2.2.3, 5.5.7.2, 5.6.1, 7.6.2.1
[FN 99-045]Incorporated technical a nd editorial corrections and clarifications related to residual heat
removal system.Tables 5.4-2 & 5.4-2[FN 98-049]Updated the surveillance capsule withdrawal schedules for both units. [10 CFR 50, Appendix H]5.5.1.2, 5.5 Refs[FN 2000-007]Updated the design description of the reactor
coolant pump thermal barrier heat exchanger
.5.5.10.2, 5.5.10.3[FN 2000-015]Modified the reactor head vent line to provide clearance for reactor cavity seal ring installation and removal.
6.2.1.2.5[FN 2000-031]Corrected the description of the structural integrity of the neutron shield sur ge tank.Revision 36-09/01/00 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 63 6.2.1.3.2.5, 6.2.2.2[FN 2000-021]Corrected the description of materials used in
containment subcompart ment blowout panels, reactor cavity drain, and containment sump screen.Table 6.2-51[FN 2000-039]Corrected typographical, administrative, and format errors.6.4.1.3.3, Table 6.4-1
[FN 99-071]Updated the description of potentially
hazardous chemicals stored on the plant site to
add Calgon H-940 and to include the additional amount of sodium hypochlorite used in the
activated bromine system.7.7.1.10[FN 97-020]Revised the description of the plant computer
system in accordance with approved plant modifications.
8.3.1.1.2.3, 8.3.1.1.2.5, 8.3 Refs, Table 8.3-8, 9.5.2.1.2, 9.5.2.1.3, 9.5.2.1.4, 9.5.2.2.1, 9.5.2.2.2, 9.5.2.2.3, 9.5.2.2.4, 10.2
[FN 2000-002]Incorporated technical a nd editorial corrections and clarifications relate d to the electrical and communication systems.9.1.3.2, Table 9.1-1, 9.3.4.2.2.3, Table 9.3-5[FN 99-074]Added descriptions of the administrative
controls applied to the filters for the chemical volume and control system and refueling purification system.9.2.2.1.1, 9.3.2.1.1, 9.3.2.1.3, Table 9.3-2, 10.
4.7.2
[FN 97-055]Incorporated modifications to the on-line chemistry monitoring system.
9.2.2.1.2, 9.2.2.2.2, 9.2.2.3.1, 9.2.2.3.2
[FN 97-010]Added notes reflecting that some steam
generator sampling coolers have been abandoned in place.
9.2.2.1.2, 9.2.2.2.2, 9.2.2.3.2, 10.4.7.2[FN 99-023]Incorporated a plant modification that allows the Unit 1 isolated phase bus duct air cooler to be supplied by chilled wate r as an alternative to bearing cooling.Table 9.2-5[FN 97-050]Revised the design code and tube material for the component cooling wa ter heat exchangers to reflect a design modification.
9.3.1.2, 9.3.1.3, 9.3.1.3.1, 9.3.1.3.2, Table 9.3-1, Figure 9.3-1, 9.5.10.3, 10.3.2[FN 2000-003]Incorporated technical a nd editorial corrections and clarifications related to instrument air system.Revision 36-09/01/00 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 64 9.3.2.1.1, 9.3.2.1.2, 9.3.2.2.3, 9.3.3.2, Tables 9.3-3 & 9.3-10, Figures 9.3-2 & 9.3-3, 10.4.8.4[FN 99-051]Incorporated technical a nd editorial corrections and clarifications related to feedwater, condensate, steam generator blowdown, and
condensate polishing systems.
9.3.2.1.2[FN 98-042]Add a discussion of the on-line chemistry
monitoring system.
9.3.2.1.5
[FN 99-068]Clarified the use of the on-line chemistry
monitoring system panel.
9.3.4.2.4.7[FN 2000-009]Augmented the description of purging gases
from the volume control tank.
9.4.1.4[FN 2000-035]Corrected a typographical error.
9.5.1.2.2.2, 9.5 Refs
[FN 99-033]Adds a description of the design basis for the
emer gency switchgear room halon system.Table 10.4-1[FN 99-052]Revised an existing description of the Unit 1 auxiliary feedwater system design basis to
reflect the bases for both Units 1 & 2.Table 10.4-2[FN 96-074] & F N 99-035]Revised design data to reflect the replacement moisture separator-reaheaters on Units 1 and 2.Table 10.4-4, 15.2.8.1, 15.2.8.2.1, 15.2.8.2.2, 15.2.8.3, 15.2.9.1, 15.2.9.2.1, 15.2.9.2.2, Table 15.2-1, Figures 15.2-28 through 15.2-35[FN 99-047]Incorporated changes resu lting from the revised loss of normal feedwate r accident analysis.
13.2.1, 16.1[FN 2000-028]Corrected reference from Environmental T echnical Specifications to Environmental Protection Plan.
13.4
[FN 2000-024]Updated the name of the subcommittee
responsible for Manage ment Safety Review Committee independent reviews.
15.2.10.1
[FN 99-041]Corrected the description of feedwater pump
dischar ge valve closure due to associated pump trip and provided a closure signal directly to each discharge valve.
15.3.1.6, 15.3.1.7, 15.3 Refs, Table 15.3-4, 15.4.1.5.3, 15.4 Refs, Table 15.4-5[FN 99-070]Incorporates a summary of the peak clad temperature penalties and benefits for the small and large break LOCA which are reported per 10 CFR 50.46 requirements.
Revision 36-09/01/00 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 65 15.3.5.2[FN 99-055]Corrected the values of total activity assumed to be released by a waste gas decay tank
rupture. [10 CFR 50.90 License Amendment]
17.2.1.2, 17.2.2.1, 17.2.17, Figure 17.2.1-1
[FN 2000-032]Modified organizationa l titles and reporting relationships associat ed with information technology.
17.2.1.2, 17.2.2.6, Figure 17.2.2-1[FN 2000-008]Updated organizational de scription to reflect Supply Chain Management (Generation) titles.
17.2.1.2, Figure 17.2.1-2[FN 2000-017]Modified organizationa l titles and reporting relationships associated with records
management.
17.2.1.2, Figure 17.2.1-2[FN 2000-034]Modified organizationa l titles and reporting relationships associated with the radwaste
facility.Revision 36-09/01/00 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 66 Revision 35-09/01/99 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
KWI, 1.2.12, 2.1.1.1, 2.1.1.2, 2.1.2.1, 2.1.2.2, 2.1.3.3, Table 2.1-2, 2.2.1.3, 2.2.1.5, 2.3.2.2.1, 2.3.2.4, 2.4.1.1, 2.4.1.2, 2.4.2.2, 2.4.3, 2.4.4, 2.4.8, 2.4.10, 2.4.11.1, 2.4.11.4, 2.4.11.5, 2.4.11.6, Table 2.4-2, 2.5.4.1, 2.5.4.2, 2.5.5, Table 2.5-1, 2A.2.2, 2A.2.3.1, 2A.2.4.1.1, 2A.2.4.1.2, 2A.2.4.1.3, 2A.2.5.1, 2A.2.5.2, 3.4, 3.8.1.1.7, 3,8.1.1.9, 3.8.2.1.3, 3.8.3.1, 3.8.3.2, 3.8.4.1, 3.8.4.5.2, 3.8.4.5.4.7, 3.8.4.5.4.8, 3.8.4.6, 3.8.4.7.5, 3.8.4.8, Table 3.9.1, 3.11.2.6, 3.11.2.7, 3.11.2.8, 3.11.2.9, 3.11.2.10, Table 3.11-2, 3A.27, 3E.2.1, 9.2.1.1, 9.2.1.2.1, 9.2.1.2.2, 9.2.1.2.3, 9.2.1.2.4, 9.2.1.2.4.1, 9.2.1.2.5, 9.2.1.3, 9.2.1.3.1, 9.2.1.3.2, 9.2.1.4.1, 9.2.1.6, 9.2.2.2.4, 9.2.3.2.2, 9.2.5, 9.2.5.1, 9.2.5.2, 9.2.5.3, 9.2 Refs, 9.2 Ref Dwgs, Tables 9.2-1, 9.2-3, &
9.2-4, Figure 9.2-1, 9.4.1.2, 9.4.10.2, 9.5.1.2.1, 9.5.1.3.2, 10.1, 10.4.2.2, 11.2.3, 11.2.5.1, 11.2.8, Tables 11.2-16 & 11.2-19, 11.4.2.1, 11.4.2.10, Table 11.4-2, 11.6.3.6, 11B.1, 11B.2.1, 11B.2.2, 11B.4, 11B.4.1.1, 11B.4.1.4, 11B.4.2.2, Tables 11B-4, 11B-6, 11B-7, &
11B-9, 15[FN 98-043]Incorporated technical a nd editorial corrections and clarifications related to the service water system.KWI, 1.2.3, 4.2.3.5, 5.5.2.3.5, 6.2.4.1, 6.2.4.2, 7.3.1.3.5.4, Table 7.5-3, 7.7.1.8, 7.7.1.8.1, 10.1, Figures 10.1-1 and 10.1-2, 10.2, 10.3.1, 10.3.2, 10.3.3, 10.3.3.2, 10.3.4, 10.3 RefDwg, Tables 10.3-1 through 10.3-4, Figures 10.3-1 and 10.3-3, 10.4.1.2, 10.4 RefDwg, 15.4.2.1.1[FN 98-031]Incorporated technical a nd editorial corrections and clarifications related to the main steam system.KWI, 2.3.5.1, 2.4.11.5, Table 3.2-1, 3.4, 3.7.2.4, 3.7.3.1.1, & Tables 3.7-4, 6.2-45, 9.6-1, & 15.4-10
[FN 98-046]Corrected references, spelling, and format.
Revision 52-09/29/2016 NAPS UFSAR 67 KWI, Ref Dwgs: 1.2, 2.4, 2.5, 3.6, 3.8, 3C, 5.1, 5.5, 5.6, 6.2, 6.3, 6.4, 7.1, 7.3 , 7.7, 8.1, 8.2, 8.3, 9.1, 9.2, 9.3, 9.4, 9.5, 9A, 10.2, 10.3, 10.4, 1 1.2, 11.3, 11.4, 11.5, 11C, 12.1, 12.2, 12.3, 14.1, 15, 15.4; Sections 2.4.2.2, 2.4.11.5, 2.4.13.1, 5.1.5.1, 5.5.4.2, 6.2.1.2.18, 6.3.2, 8.1.2, 8.3.1, 8.3.1.1, 8.3.1.1.1, 8.3.2.1, 9.2.1.2.4, 9.2.1.2.4.1, 9.2.1.2.4.2, 9.4.9.1, 9.4.10.2, 10.4.3.2, 10.4.4.3, 10.4.5.2, 10.4.6.2, 10.4.7.2, 10.4.8; Tables 2.4-8, 2.4-9, 5.5-6, 9.4-4[FN 99-003]Corrected a Key Word Index reference, supplemented the reference drawings lists, and
corrected text citations of reference drawings.KWI, Table 3.5-1, Table 6.2-46, 6.3.2.1.1, 6.3.2.1.4.6, 6.3.3.12, 6.3.5.3.2, 7.1, 7.1.3.1, 7.2.2.2.2, 7.2.2.2.3, 7.2.2.2.4, 7.2.2.2.5, 7.2.2.2.6, 7.2.2.2.8, 7.2.2.2.9, 7.3.2.1, 7.5.2, 7.6.2.2, 7.6.3.2, 7.6.5, 7.6 Refs, 7.9.1, 7.9 Refs, 9.2.3.2.1, Table 9.2-3, 11.3.5.4, Table 12.1-4, 12.2.6, 15.2.6.2.2.2, 15.2.13.2.2, Table 15.4-5, Table 15.4-6[FN 99-012]Corrected cross-refe rences, typographical errors, and electronic sc anning discrepancies; improved consistency of exponent, numerical, and Greek letter notation; improved consistency of abbrevia tions; and incorporated two tables omitted fr om a previous UFSAR change.1.2.10, 2.4.11.5, 2.4.11.6, Table 2.4-7, 10.4.2.3, Figures 10.4-1 and 10.4-2[FN 99-027]Incorporated technical a nd editorial corrections and clarifications related to the circulating water system.
Ref Dwgs: 1.2, 2.4, 2.5, 3.6, 3.8, 3C, 5.1, 5.5, 5.6, 6.2, 6.3, 6.4, 7.1, 7.3, 7.7 , 8.1, 8.2, 8.3, 9.1, 9.2, 9.3, 9.4, 9.5, 9A, 10.2, 10.3, 10.4, 1 1.2, 11.3, 11.4, 11.5, 11C, 12.1, 12.2, 12.3, 14.1, 15, 15.4[FN 99-009]Clarified the referenc e drawings lists by spelling out words abbrev iated in the titles and using consistent punctuation.
1.3, 1.3.1.1, 1.3.1.2, 1.3.1.3, 1.3.1.4, 1.3.1.4.1, 1.3.1.4.2, 1.3.1.5, 1.3.1.6, 1.3.2, Tables 1.3-1 through 1.3-13, 7.7.1.13.2, 8.1.2, 8.1 RefDwg, 8.3.1.1.1, 8.3.1.1.2.2, 8.3 Ref Dwg[FN 99-002]Incorporated technical a nd editorial corrections and clarifications related to the emer gency power system.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 68Table 1.3-1, 3.8.4.1, Tables 3.9-1 & 3, 3.11.2.2, Figure 4.3-6, 5.1.2.1.3, Figure 5.1-2, 5.2.3.3.1, 5.2.5.1, Tables 5.2-12, 22, &
28, Figures 5.2-5, 6, 9, & 10, 5.4.3.6.1, 5.4.3.6.2, 5.4 Refs, 5.6.2.3, Figure 6.2-66, 7.7.1.5, 11.4.3.1.1, 15.4.1.7.2, 15.4.1.7.3[FN 99-001]Corrected cross-refe rences, typographical errors, and electronic sc anning discrepancies; improved consistency of upper and lower case
and listing notation; improved superscript and subscript notation; and incorporated a list omitted from a previous UFSAR change.Table 1.3-2, 3.1.33.2, Tables 3.9-2 & 3.11-1, 3A.1.2, 6.3.2.1.1, 6.3.2.1.4.1, 6.3.2.1.4.2, 6.3.2.1.4.4, 6.3.2.1.4.5, 6.3.2.1.4.6, 6.3.2.1.5, 6.3.2.2.5, 6.3.3.5, 6.3.3.8.1, 6.3.3.10, 6.3.3.12, 6.3.4, 6.3.4.1, 6.3.4.2, 6.3.4.3, 6.3.4.4, 6.3.4.5, 6.3.5.2.1, 6.3 Refs, Tables 6.3-1, 6.3-2, and 6.3-4, through 6.3-6, Figures 6.3-1, 6.3-16, and 6.3-17, 6A.1, 9.5.10.2, 14.1, 14.1.1, 14.1.2, 14.1.2.1, 14.1.2.2, 14.1.2.3, 14.1.2.4, 14.1.3, 14.1.4, 14.1 Refs, Tables 14.1-1 through 14.1-5, Figures 14.1-1 through 14.1-3[FN 99-008]Incorporated technical a nd editorial corrections and clarifications related to the safety injection system.Table 1.3-2, 3.1.36.2, Table 3.9-1, 3.11.22, 3A.1.2, 6.2.2.2, 6.2.2.2.2, 6.2.2.2.3, 6.2.2.2.4, 6.2.2.3.2.1, 6.2.2.3.2.6, 6.2.2.4.2, 6.2.3.1.1, 6.2.3.3, Tables 6.2-4 & 6.2-42, Figures 6.2-50 & 6.2-68, 9.3.3.2[FN 98-057]Incorporated technical a nd editorial corrections and clarifications related to the recirculation spray system.Tables 1.3-8, 1.3-9, &
1.3-10, 3.1.55.2, 5.2.4.2, 7.7.1.12.2, 9.3.2.1.3, 11.2.3, 11.4.1, 11.4.2, 11.4.2.1, 11.4.2.13, 11.4.2.14, 11.4.2.14.1, 11.4.2.14.2, 11.4.2.15, 11.4.3, 11.4.3.1.1, 11.4.3.1.2, 11.4.3.1.3, 11.4.3.2, 11.4.4.1, 11.4.4.2, Tables 11.4-1 through 11.4-4, 12.1.4.1, 12.1.4.2, 12.1 RefDwg, Table 12.1-4, 12.2.4, 15.4.7.2.4.1, 14.4.7.2.4.2[FN 98-050]Incorporated technical a nd editorial corrections and clarifications related to the radiation monitoring system.Table 1.3-12, 11.3.5.1, Table 11.3-1, 11C.4.1.5[FN 95-031]Revised the catalytic hydrogen recombiner
description to reflect that it is no longer used.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 69 2.1.3.4, 2.4.13.4, 3.1.52.2, 3A.4, 3A.21, 3A.111, 3A.113, 11.1, 11.1.1.3, 11.1.1.4, Tables 11.1-7, 11.1-9, 11.1-11, &
11.1-12, 11.2.8, Table 11.2-4, 11.3.5, 11.3.5.1, 11B.4.1.1, 11.B.4.1.2, 11B.4.2, 11B.4.2.1, 11B.5, Table 11B-9, Figure 11B-1, 11C, 11C.1, 11C.2, 11C.3, 11C.4, 11C.4.1, 11C.4.1.2, 11C.4.1.3, 11C.4.1.4, 11C.4.1.5, 11C.4.1.6, 11C.4.1.7, 11C.4.2, 11C.4.3, 11C.4.4, 11C.4.5, 11C.5, 11C References, Tables 11C-1 through 11C-18, Figure 11C-1, 12.1.2.2, 12.1.2.5, 12.1.2.1 1, 12.1.3, 12.1.6.1, 12.1.6.2, 12.1.7.2, Table 12.1-3, 12.2.6, Table 12.2-1[FN 99-004]Incorporated technical a nd editorial corrections and clarifications related to the radiation
protection system.Table 2.2-3, 6.4.1.3.3, Table 6.4-1[FN 99-015]Updated the descriptions and of potentially hazardous chemicals found on-site 2.3.1.1, 2.3.2.1, Figure 2.3-23, 3.10.1, 3.11.2.8, 3A.32, 3A TOC, 3F.4, Table 3F-8, 5.6.2.1, 6.2.2.2, Figure 6.2-65, 7.9 References, Tables 8.3-6 & 7, Table 9.2-3, 11.1.1.3, 15.1.2.3, 17.2.16.2
[FN 98-060]Corrected cross-refe rences, typographical errors, and electronic sc anning discrepancies; improved consistency of upper and lower case and listing notation; and incorporated a title
change.2.3.5.1, 3.1.3.2, Table 3C-3, Figure 5.2-13, 9.5.10.3, 11.3.2, 11.3.3, 11.3.3.2, 11.3.5.2, 11.3.5.3, 11.3.5.6, 11.3.5.10, Table 11.3-1, Figure 11.3-1, 11.4.4.2, Table 11.4-1, 12.2.4, 15.4.7.2.4.2[FN 99-028]Incorporated technical a nd editorial corrections and clarifications related to the gaseous waste
system.2A.2.3.1, 2A.2.3.2, 2A.2.3.3, 2A.2.4.1.1, 2A.2.4.1.3, 2A.2.5.1, 2A.2.8[FN 99-050]Corrected text cross-references.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 703.1, 3.1.11.2, 3.1.16.2, 3.1.17.2, 3.1.20.2, Table 3.11-2, 4.3.1.7, 7.1.1, 7.1.3.2.3, 7.1.3.3.1.2, 7.1.3.3.3, 7.1.4, 7.1 Refs, 7.1 RefDwgs, 7.2.1, 7.2.1.1.1, 7.2.1.1.4, 7.2.1.1.5, 7.2.1.1.6, 7.2.1.3.1, 7.2.1.3.2, 7.2.1.8, 7.2.2.1.2.2, 7.2.2.2.1, 7.2.2.2.1.5, 7.2.2.2.1.7, 7.2.2.3.2, 7.2.2.3.3, 7.2.2.3.4, 7.2.2.3.5, 7.2.3.2, 7.2 Refs, Tables 7.2-1 through 7.2-4, Figures 7.2-1, 7.2-2, 7.2-3, 7.2-5 through 7.2-10, 7.2-12, &
7.2-13, 7.3.1.2, 7.3.1.31., 7.3.1.3.2, 7.3.1.3.2.1, 7.3.1.3.3.2, 7.3.1.3.5, 7.3.1.3.5.1, 7.3.2.1.4, 7.3.2.1.5.2, 7.3.2.1.5.6, 7.3.2.1.5.8, 7.3.2.1.5.1 1, 7.3.2.1.5.12, 7.3.2.2, 7.3.2.3, 7.3.2.4, 7.3.2.5, 7.3.2.6, 7.3.2.7, 7.3.2.8, 7.3.2.10, 7.3 Refs, Tables 7.3-1 through 7.3-4, Figures 7.3-2, 7.3-4, 7.3-5, 7.3-8, 7.3-10, &
7.3-11, Tables 7.5-1 through 7.5-3, 7.7.1.13.1, 7.7.2.1, 10.3.2
[FN 98-025]Incorporated technical a nd editorial corrections and clarifications related to the reactor protection system.
3.1.9.2, 3.1.26.2, 3A.2, 5.1, 5.1.1.9, 5.1.2.1, 5.1.2.1.1, 5.1.2.1.2, 5.1.2.1.3, 5.1.2.2, 5.1.2.3, 5.1.2.4, 5.1.3.1, 5.1.3.3, 5.1 Ref Dwgs, Figures 5.1-1 & 5.1-2, 5.5.4.2.2.3, 5.6.2.2, 5.6.2.3, 5.6 Refs Dwgs, Figure 5.6-1, 7.2.2.3.3, 7.2.2.3.4, 7.7.1.5, 7.7.1.6[FN 98-017]Incorporated technical a nd editorial corrections and clarifications related to the Reactor Coolant System.
3.1.53.2, 9.1.1, 9.1 Refs[FN 97-060]Added clarification that criticality monitors are not required in the new fuel storage area and added a reference to the exemption from this requirement. [10 CFR 70.24 Exemption]Table 3.7-7, 3.8.2.1.2.4, 3.8.2.1.3, 3.8.2.1.4.2, App. 3E Att. 4, App. 3E Att. 5, 5.5.9.3.1, 5.5.9.3.2, 9.2.1.4.1, Table 9.3-7, Table 10.4-2.[FN 99-038]Corrected errors associated with table formatting, text cross-re ferences, typographical entries, implementation of a previous update, and punctuation.3.8.2.7.6.2.4, Table 3.8-11[FN 98-053]Clarified the descript ion of unqualified coatings in containment.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 71 3.8.4.7.7, 3.8.4.8, 3.8 Refs, Table 3.8-17, Figures 3.8-32, 3.8-33, and 3.8-61[FN 97-053]Incorporated new piezometers locations and editorial corrections
.Table 3.8-12, Figure 3.8-24[FN 98-051]Updated the locations of piezometers at the
main da m.Table 3.8-14[FN 97-041]Corrected the factors of safety applicable to the service water reservoir dikes.Table 3.11-2, 6.2.2.3, Table 6.2-37, 6.3.3.12, 6.4.1.3.3, Table 6.4-1, 7.2.2.1.2, 7.2.2.1.2.1, Table 11.1-11, 11.2.8, 11B.2.1, 11B.2.2, 11B.4, 11B.4.1.1, 11B.4.1.4, 11B.4.2.2, Tables 11B-4, 1 1B-6, & 11B-7, 12.1.2.11[FN 99-022]Corrected spelling and typographical errors, eliminated duplicate phrases, updated text figure references, corrected punctuation, spelled out a non-standard acronym, standardized a system title, and capitalized the titles of computer codes.
3A, 7.4, 8.1, 8.3, 9.5, 14.1[FN 98-045]Incorporated technical a nd editorial corrections and clarifications related to the Emer gency Diesel Generator System.
3A.22, 4.4.5.1, 4.4.5.2, Figures 4.4-20 and 4.4-21, 7.1, 7.2.3.4, Figure 7.2-5, 7.3.2.1.5.10, Figure 7.3-9[FN 99-024]Incorporated technical a nd editorial corrections and clarifications related to the nuclear instrumentation system.
3C.1.1, 3C.2.7, 3C.2.7.1, 3C.5.1.2.2, 3C.5.1.8.2, 3C.5.2.8.2, 3C Refs[FN 96-007]Reduced the number of weld inspections
required to be performed on high ener gy piping outside containment. [NRC Safety Evaluation Report]4.1, Table 4.1-1, 4.2.3.2.2, 5.2.3.1.1, 5.4.2[FN 98-041]Incorporated changes to reflect removal of the Unit 2 part-length control rod drive mechanisms.
4.3.2.2.6, 4.3.2.7, 4.3 Refs[FN 96-046]Reflected changes to reload design
calculations, correcte d a reference, and correctly stated initial fuel enrichment.
Figures 4.4-20 and 4.4-21[FN 97-030]Modified the figure description of the incore thermocouples.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 72 5.2.1.1, 5.2.1.2, 5.2.2.1, 5.2.2.2, 5.2.2.4, 5.2.3.1, 5.2.3.1.1, 5.2.3.1.2, 5.2.3.1.3, 5.2.3.1.4, 5.2.3.1.5, 5.2.3.1.6, 5.2.3.1.7, 5.2.3.1.8, 5.2.3.1.9, 5.2.3.1.10, 5.2.3.1.1 1, 5.2.3.1.12, 5.2.3.3.1, 5.2.4.1.1, 5.2.4.1.2, 5.2.5.1, 5.2.5.3, 5.2 References, Figures 5.2-4 thru 5.2-10, 5.3[FN 98-035]Incorporated technical a nd editorial corrections and clarifications related to the Reactor Coolant System.
5.4.2, 5.4.3.6, 5.4.3.6.1, 5.4.3.6.2, 5.4.3.6.3.1, 5.4.3.6.3.2, 5.4.3.7, 5.4 References, Table 5.4-1, Figure 5.4-4, 5.5.1.3.1, 5.5.1.3.3, 5.5.1.3.10, 5.5.2.3.4, 5.5.2.3.5, 5.5.2.4, 5.5.3.2, 5.5.3.2.1, 5.5.3.3.1, 5.5.3.3.3, 5.5.4.3.4, 5.5.5.1.1, 5.5.5.3.2, 5.5.7.2, 5.5.8.2, 5.5.10.2, 5.5.10.3, 5.5 Ref Dwgs, Tables 5.5-1, 5, 6, &
12[FN 98-036]Incorporated technical a nd editorial corrections and clarifications related to the Reactor Coolant System.
5.5.1.3.4[FN 96-090]Clarified reactor coolant pump bearing
integrity discussion by deleting oil level shutdown of the pump and adding high bearing
temperature shutdown of the pump.
5.5.7.2, 7.6.2.2[FN 97-023]Removed the description of automatic closure
5.5.8.2, 5.5.8.3[FN 95-032]Added a description of th e surveillance criteria and function of the nitrogen reserve tanks for the pressurizer power-ope rated relief valves. [10 CFR 50.90 License Amendment]
5.5.8.2
[FN 97-012]Revised the description of the function of the pressurizer power-operated relief valve nitrogen reserve tanks.
5.5.9.3.3, Figures 5.5-16, 5.5-17, &
5.5-18[FN 97-038]Removed vendor specific information from the
description of snubbers.
6.2.1.4.3[FN 97-028]Revised the description of the Type B test equipment, deleted a reference to T ype C penetrations, and incorporated editorial changes.6.2.2.2.5, Table 9.2-3[FN 96-059]Revised the chloride concentration in the Service Water Reservoir and corrected a reference in the text.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 73 6.2.2.2[FN 98-055]Clarified encapsulation of insulation inside
containment.6.2.4.2[FN 99-036]Corrected the description of the hydrogen recombiner suction piping connection.
6.2.6.3[FN 92-161A]Reverted the description of containment
vacuum pumps to wording from the original FSAR.Table 6.2-54[FN 97-035]Revised the description of the outside recirculation spray containment penetrations.
6.3.2.1.1
[FN 99-007]Added clarification on th e applicability of the minimum boron concentration requirement to
the SI piping.6.3.2.1.1, Table 6.3-4
[FN 97-043]Incorporated changes to the safety injection accumulator test lines, level control descriptions, and sampling methods.
6.3.2.1.3.2, 6.3.3.1, 6.3.4.2, Figure 6.3-5[FN 97-007 & F N 97-007A]Incorporated revised ECCS analyses.
6.3.2.1.4.1, 6.3 Refs[FN 96-089]Added a description of design features that prevent valve-bonnet pressure locking of containment sump isolation valves and added a
reference to Generic Letter 95-07.6.3.3.1.4
[FN 97-013]Incorporated clarification to the effect of LHSI
valve misfunction on ECCS flow discussion.
6.3.4.4[FN 92-125A]Reverted description of routine periodic testing of ECCS components to that which preceded the present wording supported by an inadequate safety evaluation.
6.3.5.2.3[FN 97-026]Added description of pressure taps for checking proper seating of the Unit 1 accumulato r check valves.
6.3.5.2.3[FN 97-027]Changed the description of provisions for testing accumulator ch eck valve seating to pressure taps from pressure indicators.Tables 6.3-1 & 5[FN 92-127A]Reverted description of accumulator minimum
pressure to that whic h preceded the present value supported by an inadequate safety
evaluation.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 74Table 6.3-5, 8.3.1.1.1[FN 96-017]Updated to reflect new charging pump interlocks.
6.4.1.2[FN 97-058]Added requirements if the fuel pit bridge
radiation monitor is out of service.
6A.3.2, 12.1.2.10, 15.4.1.7, 15.4.1.7.2, Table 15.4-7[FN 98-056]Revised the control whole body dose resulting
from a LOCA.
7.1, 7.2.1, 7.2 Refs, 7.3.1.3.2, 7.3.1.3.5, 7.3.1.3.5.4, 7.3 Refs[FN 99-006]Incorporated clarific ations and editorial corrections and added a reference to the
instrumentation section.Table 7.2-2[FN 99-029]Corrected the reactor trip system over temperature de lta T range description.
8.1.2, 8.3.2.1, 8.3.2.2.4
[FN 95-039]Revised the description of the role of the
station battery swing char gers.8.3.1.1.2.1[FN 98-023]Revised the description of the emer gency diesel generator operation during transients or disconnection. [10 CFR 50.90 License Amendment]8.3.1.1.2.6
[FN 96-053]Added a description of the long term tests results on Dow Corning foam and eliminated
the required testing of pe netrations sealed with this foam.
8.3.2.1, 8.3.2.2.2, 8.3.2.2.3[FN 99-031]Incorporated technical a nd editorial corrections and clarifications related to the 125V dc (emergency diesel) system.
9.1.1[FN 96-064]Revised the description of new fuel container
unloading to clarify that the containers are not unloaded from trucks in the new fuel enclosure.
9.1.2, 9.6.3, 9.6.4.1[FN 97-002]Provided for moving the spent fuel pool gates over irradiated fuel in accordance with Technical Specifications. [10 CFR 50.90 License Amendment]
9.1.3.1[FN 98-039]Clarified the seismi c clas sification and associated contingency actions for refueling purification piping and equipment.
9.1.3.2[FN 96-043]Added a description of the administrative controls for isolation of the non-seismic portions of the refueling purification system.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 75 9.1.4.4.4[FN 96-014]Added a description of the manipulator crane
in-mast sipping system.
Figure 9.1-9[FN 96-048]Changed the fuel transfer system drive to cable from an air motor
.9.2.1.2.2
[FN 96-076A]Added an analysis of the impact of
accumulation of or ganic matter in the Service Water Reservoir.9.2.1.2.4, 9.2.1.3, Table 9.2-4[FN 96-023]Added the performance sp ecifications for new service water pumps and clarified NPSH requirements.
9.2.1.3.1[FN 96-067]Clarified the description of isolation of service water flow to the containment recirculation air cooling coils in the event of loss of instrument air.9.2.1.5[FN 97-015]Revised the description of the corrosion
coupons in the service water piping.
9.2.2.5.1[FN 97-008]Revised the description of how the component
cooling system may be aligned to supply cooling loads.
9.2.3.2, 9.2.3.2.1, 9.2.3.2.2, 10.4.7.2[FN 94-053]Revised the description of the water treatment
system to say that the flash evaporator is obsolete and no longer used.Table 9.2-5[FN 97-025]Revised the component cooling heat exchanger tube material description.
9.3.1.2[FN 97-017]Enhanced the description of the operation of the instrument air compressors regarding
in-service and standby lineups and staggered setpoints.9.3.2.2.1, 9.3.2.2.2.6[FN 96-071]Added a description of high radiation sampling system, post-accident required sample times.
9.3.2.2.2[FN 97-019]Revised the description of the high radiation sampling system containment sump pump.
9.3.4.1.3, 9.3.4.1.4, 9.3.4.2.2.3, 9.3.4.2.4.10, 9.3.4.3.2[FN 97-047]Added descriptions of hydrogen peroxide user during refueling shutdown, clarified the potential ef fects of demineralizer overheating, and incorporated editorial changes.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 769.3.4.2.4.11[FN 98-022]Added a description of hydrogen-form cation
resin use in mixed-bed demineralizers.
9.3.4.2.4.21.6[FN 96-083]Revised the description of the capacity of the
seal-water return line relief valve.
9.4.4.2[FN 97-006]Allowed blocking Turbine Building grating
ventilation path provide d compensatory actions are in place to monitor temperature.
9.4.5.1, 9.4.5.5
[FN 96-063]Added a description of when the Fuel Building
ventilation system can be secured.
9.5.1.2.3
[FN 98-058]Corrected the heat dete ctor temperature rating for the main and station service transformers.
10.2[FN 99-019]Revised the throttle and governor valve stem
freedom test frequenc y in accordance with T ech Spec Amend 210/191. [10 CFR 50.90 License Amendment]
10.3.2, 10.3.3, 10.3.4, 15.4.3.2.2
[FN 98-004]Added descriptions of atmospheric steam dump
valve use during steam generator tube rupture
events and revised the valve description.
10.3.2
[FN 97-014]Revised the normal relieving pressure of the
atmosp heric steam dump valves.
10.4.3.3.1[FN 98-052]Removed the auxiliary feedwater system from
th e list of systems analyzed for steam-hammer and water-hammer occasional mechanical loading.11.1.1.5, Tables 11.1-5 & 11.1-12, 15.3.6.2[FN 99-011]Revised the volume control tank analysis of
effects and consequences.11.3.2, 11.3.3, 11.3.3.2, 11.3.5.2[FN 97-036]Revised the gaseous waste system description to reflect that th e catalytic hydrogen recombiner and waste disposal evaporator are no longer used, to include the ion exchange
filtration system, and to describe other operational changes.11.3.5.8[FN 92-094A]Corrected errors introduced in a previously implemented change package.11.4.3.1.1
[FN 97-022]Corrected the calibration sources used for
ef fluent gas monitors.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 7715.1.6, Table 15.1-2, Figure 15.1-3[FN 99-040]Updated the Doppler reacti vity coef ficients to be consistent with the accident analysis basis.15.1.6, Table 15.1-2, 15.2.2.1, 15.2.2.2.1, 15.2.2.2.2, 15.2.2.4, Table 15.2-1, Figures 15.2-6 through 15.2-13[FN 99-034]Updated the results for th e transient analysis of the uncontrolled rod clus ter control assembly withdrawal at power (RWAP) accident.15.1.2.3, Table 15.1-3[FN 95-044]Added current trip setpoint and response time
values to Table 15.1-3 and removed a reference to Figure 15.1-1 for these values.
15.2.1.1, 15.2.1.2.1, 15.2.1.2.2, 15.2.1.3, 15.2.4.1, 15.2.4.2.1, 15.2.4.2.2, 15.2.4.2.3, Table 15.2-1, Figures 15.2-1 through 15.2-5[FN 97-037]Revised the description of the uncontrolled rod
withdrawal from subcri tical and uncontrolled boron dilution transients to reflect current analyses of record. [10 CFR 50.90 License Amendment]15.2.1.1
[FN 97-051]Revised the description of the setpoint for the
intermediate range high neutron flux reactor tr ip.15.2.6.1.2[FN 96-062]Modified the description of the loop stop valve
interlocks to reflect the elimination of the cold leg differential temperature and 90-minute pump run interlocks. [10 CFR 50.90 License Amendment]15.4.1.7.3, 15.4 Refs[FN 99-039]Incorporated the results of a sensitivity analysis of acceptable quantities of ECCS leakage in conjunction with potentially unfiltered exhaust
from the Auxiliary Building.
15.4.7.2.4.1, 15.4.7.2.4.2, 15.4.7.2.4.3, 15.4.7.2.4.4, Tables 15.4-16 thru 15.4.18[FN 98-048]Reflected the current analysis of record for a
fuel handling accident inside containment regarding containment purge, exhaust valve closure times, and radi ation detector response times.17.2.2.5[FN 98-059]Clarified the qualificati on requirements of key Nuclear Oversight personnel.Table 17.2-0[FN 98-047]Revised the description to indicate the both Innsbrook record vaults meet ANSI requirements.
Revision 35-09/01/99 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 78 Revision 34-9/01/98 SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
KWI, 1.5.2.1, 1.6, 2.5.2.5, 3.1.37.2, 3.1.43.2, 3.8.2.1.4.1, Figures 3E-18 thru 3E-24, 4.3.2.7, 6.1, 6.2.1.2, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.7.1, 6.3.2, 6.3.2.1.2, 6.3.2.1.5, 7.7.1.1, 9.3.4.2.2.4, 9.3.4.2.4.8, 9.3.5.1, 9.5.4.2, 11.3.3.2, 11B.3.3.3, 11C.4.1.1, 15.4.1.7, 15.4.1.7.2[FN 98-038]Corrected references and typographical errors, and clarified word spelling and illegible text.
1.2.6, 9.1, App. 9B & App. 15A
[FN 98-014]Updated descriptions of cask loading and
unloading operations; added an evaluation of the TN-32 cask; revised commitments for cask hook orientation, cask lift heights, and use of cask loading area gate; added of fsite dose estimate for TN-32 cask drop.1.3.1 & Table 1.3-7[FN 97-054]Added statements to cl arify applicability of turbine-driven AFW pump auto-start data.
Figure 2.1-3[FN 98-020]Added ISFSI to site boundary and unrestricted
areas map.Table 2.4-7, 9.2.3.2.1, 10.4.2.2[FN 95-059]Added raw lake water pumping system that supplies the upgraded Reverse Osmosis System.3.1.34.1, 3.1.35.1, 3.1.36.1, 3.1.37.1, 3.1.39.1, 3.11.2.1, 3.11 Refs, Table 3C-3, 6.2.2.2, 6.2.2.3.2.1, 6.2.2.4.1, 6.2.2.5.1, 6.2.3.4, Tables 6.2-40 & 6.2-42, Figure 6.3-8[FN 97-057]Incorporated technical a nd editorial corrections and clarifications related to the Quench Spray
System.3.1.40.2, 3.1.42.1, & 3.1.42.2
[FN 97-054]Added AFW system to GDC 44, 45, and 46 applicability discussions.
3.8.2.2, 6.2.1.1.1.2, 6.2.1.3.1.1, 6.2.2.1, 6.2.2.2, 6.2.2.3.2, 6.2.2.3.2.1, 6.2.2.3.2.6, 6.2.2.3.2.8, 6.2.2.3.3, Tables 6.2-2, 6.2-11, 6.2-14, & 6.2-38, Figures 6.2-7 thru 6.2-9, 6.2-64 thru 6.2-80, & 6.2-82 thru 6.2-86, 6.3.2.2.6
[FN 97-024]Updated containment analys is t o reflect revised flowrates for QS, IRS, ORS, and SW.
3.8.4.5.4.6[FN 98-030]Updated service water pump tilt measurement methodology
.3.11.3[FN 97-046]Clarified description of the cathodic protection system for under ground piping.
Revision 52-09/29/2016 NAPS UFSAR 793.C.5.3, Table 3C-2, 9.2.3.2.2, 10.4.6.2, Figures 11.2-3 & 11.2-4, 11.3.5.9, Table 11.4-1, 15.4.3.1[FN 95-009]Added high-capacity steam generator blowdown system.
6.2.1.3.1.2, 6.2.2.2, 6.2.3.3, 6.2.3.1.1, Tables 6.2-44 & 6.3-9[FN 98-001]Revised quench spray star t times and annotated
derivative information.6.2.1.3.1.2, Table 6.2-18, & Table 10.4-4[FN 97-056]Clarified AFW pump flow sensitivity analysis.
6.2.3.1, 6.2.3.1.1, 6.2.3.3, 6.2 References
27-41, Tables 6.2-47, 48 & 53 thru 62, 15.4.1.7, 15.4.1.8, 15.4.1.9.3, 15.4 References 59-67, Tables 15.4-5 thru 7, Figures 15.4-38 thru 41[FN 98-012]Incorporated updated LOCA dose calculations.
6.2.3.1.1[FN 97-061]Revised post-LOCA containment sump pH.6.2.4.2, 6.2 References, Table 6.2-37[FN 97-039]Provided for partial draining of several containment penetrations which are isolated during normal power operation.
6.2.5.3, 6.2 Refs, Tables 6.2-66 & 6.2-71, Figures 6.2-98 thru 6.2-111[FN 96-008]Revised calculation of post-LOCA containment hydrogen concentration.
7.2.1.1.5, 7.2.1.1.6, 7.2.2.3.5, 7.7.1.14, 7.7 Refs[FN 98-019]Clarified design and licensing basis for
AMSAC C-20 arming setpoint.
7.2.2.2.1.7[FN 98-005]Revised testing sequence for reactor trip breakers and reactor tr ip bypass breakers.
[1 0 CFR 50.90 License Amendment]
7.2.2.3.4, Figure 7.2-11[FN 97-021]Updated description of pressurizer water level measurement system.
7.3 & 10.4[FN 97-054]Reformatted mark numbers throughout to
conform with standard format (system-component-id).
7.3.1.3.5.3[FN 97-054]Expanded discussion about motor-driven AFW pump interlocks and turbine-driven AFW pump interlocks. Changed AFW MOV "pushbutton" to "switch."
Revision 34-9/01/98 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 80 7.3.1.3.5.3[FN 97-054]Rewrote description of AFW autostart interlocks. Rewrote description of Control
Room AFW flow indi cation qualifications.
7.6.7
[FN 96-002]Clarified pressurizer relief valve flow
indication environmental and seismic
qualification.
8.3.1.1.1
[FN 96-070]Corrected typographical errors.
9.1.3.1 & 9.1.3.3[FN 96-050]Added case for full core of fload, demonstrating spent fuel pit water temperature remains below limits for normal or planned offloads. Updated back-to-back refueling and abnormal offload cases.9.2.1[FN 96-092]Deleted references to the charging pump seal
coolers that were removed from the Service Water system.
9.2.1.4.1[FN 98-011]Incorporated provision for the use of high
corrosion resistant alloy steel in Service Water piping of ten-inch diameter and smaller.
9.2.2.3
[FN 98-027]Updated component cooling chemistry specifications for chro mate concentration and pH.9.3.4.2.4.1[FN 98-034]Deleted description that char ging pump seals have leakoffs to collect seal leakage before it can leak to the atmosphere.
9.3.4.2.5.2[FN 97-004]Clarified acceptable me thods for adding boron to the reactor coolant system.
9.5.1.2[FN 97-054]Added reference to fire protection system connections in descripti on of feedwater system.
9.6[FN 98-029]Included the Fuel Building Trolley in the
NUREG-0612 Heavy Loads Program.
10.2.1.1.2[FN 97-049]Added new section on the effect of extending turbine throttle and gover nor valve test interval.
[1 0 CFR 50.90 License Amendment]
10.4.3.1[FN 97-054]Updated referenced BTP to Auxiliary System
Branch (ASB). Deleted statement specifying Terry Turbine nominal speed.
Revision 34-9/01/98 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 81 10.4.3.2[FN 97-054]Clarified discussion of SG water level
management when there is a leaky SG tube.
Corrected description of SOV redundant power source. Corrected referenc e to PCV air line/air storage descriptions. Co rrected mark numbers and clarified that discussion applies to normal lineup. Rewrote to explain intent behind design of time delays.
10.4.3.3[FN 97-054]Clarified coincidence and actuations of high-high level function description. Deleted reference to a turbine trip on low-low water level and revised to clarify that a single turbine-driven AFW pump will start. Revised maximum temperature of emergency condensate storage tank water. Deleted statement that AFW suction piping is redundantly heat traced. Cl arified suction line pressure transmitter function. Clarified statement regarding c onditions addressed in Chapter 15 loss of normal feedwater analyses.
Deleted inappropriate reference to Section 5.1.3.3. Corrected condensate storage tank inventory loss following feedwater line break event.
10.4.3.4[FN 97-054]Deleted discussion of vital bus diversity.Table 10.4-3[FN 97-054]Clarified peak reactor c oolant system pressure criterion.Table 10.4-4[FN 97-054]Corrected initial SG inventories. Corrected main steam line break re ference for decay heat.
Added clarification footnote to main steam line break reference for AFW pump design
pressure.Table 12.1-4[FN 98-018]Changed an area radiat ion monitor location and range.13.1.1.2.1, 17.2, & KWI[FN 98-008]Updated Station Manager title to Site Vice President and Assistant Station Managers titles to Manager-Station O&M and Manager-Station S&L. [10 CFR 50.90 License Amendment]
Revision 34-9/01/98 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 82 15.1.2.2[FN 95-055]Reflected revised safety analyses that support an increas ed Reactor Cool ant System total flow rate. [10 CFR 50.90 License Amendment]15.1.4 & Table 15.1-4[FN 98-024]Clarified the assumed calorimetric error in core
thermal power determin ation from secondary plant measurements.15.2.8.1
[FN 97-054]Deleted parenthetical statement of
turbine-driven AFW pump capacity. Deleted outdated statement related to AFW pump capacity determination.
15.2.10[FN 98-015]Updated feedwater temper ature reduction event description.15A, TOC
[FN 98-028]Clarified spent fuel cask lift height restrictions.
16.2[FN 98-040]Included the Technica l Requirements Manual (TRM) in the UFSAR by listing the technical requirements.
17.2.1.2.B.1[FN 98-037]Identified the Site Vice President as the station
position fulfilling the Plant Manager position identified in the ISFSI Technical Specifications.
17.2.3
[FN 98-021]Revised to reflect replacement of A/E
Instruction Manual with an Engineering
Standard.Revision 33-03/31/98 SectionChanges 17.2, 17.2.1.2, 17.2.2.1, 17.2.3, 17.2.4, 17.2.5, Figure 17.2.1-1, & Table 17.2-0[FN 97-029]Deleted reference to the Nuclear Operations
Department Standards and replace with Nuclear Business Unit Standard. Added position of Project Ma nager (Configuration Management).
17.2.1.1 and 17.2.1.2[FN 98-010]Clarified organizational position descriptions by noting responsibilities for the ISFSI as they already exis t.Revision 34-9/01/98 (continued)
SectionChangesMade under the provisions of 10 CFR 50.59 except where indicated in brackets.
Revision 52-09/29/2016 NAPS UFSAR 83 17.2.1.2, Figures 17.2.1-2 & 17.2.1-3[FN 98-013]Deleted the position of Supervisor Administrative Services in the Nuclear Management or ganization and assigned duties and responsibilities to other positions.
17.2.2.6 and 17.2.2.8
[FN 97-048]Provided clarification of Quality Inspection
Coordinator qualifications.17.2.17, Tables 17.2-2 & 17.2-3
[FN 97-044]Added Generic Letter 88-18 commitment
regarding storage of qua lity assurance records on optical disk media.Table 17.2.0[FN 96-069]Added provision for storage of quality
assurance records in an approved offsite facility.Table 17.2-0[FN 97-052]Provided an additional alternative to
ANSI/ANS 3.1.Tables 17.2-2 & 17.2-3[FN 98-016]Clarified the descripti on of onsite and of fsite nuclear safety review committees.Revision 32-02/11/98 SectionChanges Foreword[FN 96-055]Updated to reflect re cent NRC initiatives regarding UFSAR submitt al requirements, and adequacy and consistency of design basis information; and to note Virginia Power's adoption of electronic methods to enhance UFSAR maintenance, an d UFSAR distribution in both hardcopy and electronic media.Tables 3.9-1 & 3.9-2
[FN 97-042]Updated to reflect current plant configuration.
3.10.2 & 3.10.3[FN 96-049]Deleted references to Virginia Power Engineering standards STD-CEN-0020, STD-CEN-0026, and STD-GN-0038 4.1[FN 96-051]Revised to indicate that fuel assemblies may be used that differ from those described in the UFSAR-with an NRC-approved exemption or license condition.
4.2.3
[FN 97-032]Revised to reflect removal of secondary
neutron sources starting with the Unit 1 Cycle 13 reload core; secondary source replacement in future reloads is optional.
Revision 33-03/31/98 (continued)
SectionChanges Revision 52-09/29/2016 NAPS UFSAR 84 5.2.4.1.1[FN 96-061]Eliminated seismic qualification requirements for the Containment Ga seous and Particulate Radiation Monitoring System. Added
procedural requirements for system operability verification after a seismic event.
6.2.1.2.18
[FN 96-027]New section to describe lead blanket shielding
storage boxes, explai n why they are not designated Seismic Category I, and provide references to drawings that depict storage box locations.
7.2.2.2.1.7[FN 96-084]Revised reactor trip br eaker test procedure.
7.2.2.3.5
[FN 92-005]Added discussion of IEEE-279 control and
protection interaction criteria as they apply to
steam generator low leve l/high steam-feed flow mismatch trip channels.
8.3.1.1
[FN 97-001]Clarified the "C" containment air recirculation
cooler fans operating description.
9.3.4.2.2.3
[FN 96-065]Clarified that the mixe d-bed demineralizer may be removed from service if primary coolant
activity is within normal limits.
9.5.3
[FN 96-036]Added High Pressure Sodium among types of
non-containment normal lighting.
9.5.4.2[FN 97-018]Revised duration of full-load operation with
minimum allowed day tank inventory
.13.7[FN 97-003]Deleted references to Regulatory Guide 1.17 and Section 2.790. Added references to 10 CFR 73, Sections 21, 55, 56, 57, and Appendices B & C.15.2.12[FN 96-034]Revised to reflect reanal ysis to support Virginia Power's Accident Analysis Design Basis Document project.
15.2.14[FN 96-005]Revised to reflect the results of an extended
Virginia Power evaluation of the "Spurious Operation of the Safety Injection System at Power" event.
15.4.3.1[FN 97-011]Deleted paragraphs that referred to the configuration of steam ge nerators just before the repair project that included replacement of the tube bundles.Revision 32-02/11/98 (continued)
SectionChanges Revision 52-09/29/2016 NAPS UFSAR 85Table 17.2.0[FN 96-060]Deleted reference to th e Surry Training Center records vault.Tables 17.2-2 & 17.2-3[FN 97-045]Corrected typos.
Clarified record retention requirements.
All (no change bars)
[FN 96-055 & F N 96-056]*Consolidated 17 volumes to 8 volumes*Referenced Station Drawings previously included in UFSAR; inserted simplified diagrams*Removed notations associated with previously deleted ma terial and renumbered sequentially*Renumbered previously inserted items that had suffixes (e.g., 4A, 4B)*Applied consistent type face and page layouts*Improved consistency of measurement notation (e.g., time, mass, velocity), including abbreviationsRevision 32-02/11/98 (continued)
SectionChanges Revision 52-09/29/2016 NAPS UFSAR 86 Intentionally Blank Revision 52-09/29/2016 NAPS UFSARTOC-iNorth Anna Power Station Updated Final Safety Analysis ReportTable of ContentsSectionTitle Page- VOLUME I -Assignment Sheet. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . T OC-iGeneral Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . TOC-iForeword. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1List of Effective Pages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . L EP-1CHAPTER 1INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 1.1-11.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-11.2General Plant Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.2-1 1.3Comparison Tables. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.3-1 1.4Identification of Agents and Contractors. . . . . . . . . . . . . . . . . . 1.4-11.5Requirements for Further Technical In formation. . . . . . . . . . . .
1.5-11.6General References-Westinghouse Topical Reports. . . . . . . . 1.6-1CHAPTER 2SITE CHARACTERISTICS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-12.1Geography and Demography . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-1 2.2Nearby Industrial, Transportation, and Military Facilities. . . . . 2.2-12.3Meteorology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-12.4Hydrology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-12.5Geology and Seismology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 Appendix 2ARevised Analysis, Probable Maximum Flood, North Anna Units 1 and 2, Virginia Electric and Power Company June 18, 1976 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-i2A.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-12A.2Flood Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-1 2A.3Safety Implications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-9 2A.4Corrective Action Implemented. . . . . . . . . . . . . . . . . . . . . . . . . 2A-10 2A.5Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2A V o lume I -Assignment SheetGeneral Table of Contents Revision 52-09/29/2016 NAPS UFSARTOC-iiNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle PageAppendix 2BSeismic Survey of the North Anna Power Station, Virginia Electric and Power Company Prepared for Stone & Webster Engineering Corporation by Weston Geophysical Engineers, Inc.. . . . . . . . . . . . . 2B-i Appendix 2CReport on Foundation Studies for the Proposed North Anna Power Station in Louisa County, Virginia . 2C-i
- VOLUME II -CHAPTER 3DESIGN CRITERIA - STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-13.1Conformance with Atomic Energy Commission (AEC)
General Design Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-13.2Classification of Structures, Components, and Systems . . . . . . 3.2-13.3Wind and Tornado Design Criteria . . . . . . . . . . . . . . . . . . . . . . 3.3-13.4Water Level (Flood) Design Criteria . . . . . . . . . . . . . . . . . . . . .
3.4-13.5Missile Protection Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
3.5-13.6Criteria for Protection Against Dy namic Effects Associated with a Loss-of-Coolant Accident. . . . . . . . . . . . . . . 3.6-13.7Seismic Design. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.7-1 3.8Design of Seismic Class I Structures . . . . . . . . . . . . . . . . . . . . . 3.8-13.9Mechanical Systems and Co mponents. . . . . . . . . . . . . . . . . . . . 3.9-13.10Seismic Design of Class I Instrumentation and Electrical Equipment. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
3.10-13.11Environmental Design of Mechanical and Electrical Equipment. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
3.11 VOLUME III -
Appendix 3ACompliance with Safety Guides. . . . . . . . . . . . . . . . . . . 3A-i3A.1Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps (Safety Guide No.
1)3A-1 Revision 52-09/29/2016 NAPS UFSARTOC-iiiNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle Page3A.2Thermal Shock to Reactor Pressure Vessels (Safety Guide No. 2). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-23A.3Assumptions Used for Evaluating the Potential Radiological Consequences of a LOCA for Boiling Water Re actors (Safety Guide No.
- 3) . . . . . 3A-33A.4Assumptions Used for Evaluating the Potential Radiological Consequences of a LOCA for Pressurized Water Reactors (Safety Guide No.
- 4) . . 3A-33A.5Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam-Line Break for Boiling Water Reactors (Safety Guide No.
5). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-33A.6Independence Betwee n Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide No.
6). . . . 3A-43A.7Personnel Selection and Training (Safety Guide No.
- 8) . . . . . . 3A-43A.8Selection of Diesel-Generator Se t Capacity for Standby Power Sources (Safety Guide No. 9). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-43A.9Mechanical (Cadweld) Splices in Reinforcing Bars of Concrete Containments (Safety Guide No. 10). . . . . . . . . . . . . . . . . . . . . 3A-53A.10Instrument Lines Penetrating Prim ary Reactor Containment (Safety Guide No. 11) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-63A.11Nuclear Power Plant Instrumentation for Earthquakes (Regulatory Guide 1.12). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-73A.12Fuel Storage Facility Design Basis (Safety Guide No.
- 13) . . . . 3A-73A.13Reactor Coolant Pump Fl ywheel Integrity (Safety Guide No. 14)3A-73A.14Testing of Reinforcing Ba rs for Concrete Structures (Safety Guide No.
15). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-83A.15Reporting of Operating Information. . . . . . . . . . . . . . . . . . . . . . 3A-83A.16Protection Against Industria l Sabotage (Safety Guide No.
- 17) . 3A-83A.17Structural Acceptance Test for C oncrete Primary Reactor Containment (Safety Guide No. 18). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-93A.18Nondestructive Examination of Pr imary Containment Liners (Safety Guide No. 19). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-10 Revision 52-09/29/2016 NAPS UFSARTOC-ivNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle Page3A.19Vibration Measurements on Reactor Internals (Safety Guide No. 20). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-113A.20Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Powe r Plants (Regulatory Guide 1.21, Revision 1) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-113A.21Periodic Testing of Protecti on System Actuation Functions (Safety Guide No. 22). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-113A.22Onsite Meteorological Programs (Safety Guide No.
23). . . . . . 3A-123A.23Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Radioactive Gas Storage Tank Failure (Safety Guide No. 24). . . . . . . . . . . . . . . . . . . . . . 3A-123A.24Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel-Handling A ccident in the Fuel Handling and Storage Facility for a Pressurized Water Reactor (Safety Guide No. 25) . . . . . . . . . . . . . . . . . . . . 3A-133A.25Quality Group Classifi cations and Standards (Safety Guide No. 26). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-133A.26Ultimate Heat Si nk (Regulatory Guide 1.27). . . . . . . . . . . . . . . 3A-133A.27Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electrical Equipment (Regulatory Guide 1.30). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-143A.28Use of IEEE Std.
308-1971, "Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations" (Regulatory Guide 1.32) . 3A-143A.29Quality Assurance Program Requi rements (Operation) (Regulatory Guide 1.33). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-143A.30Preoperational Testing of Redundant On-Site Electric Power Systems to Verify Proper Load Group Assi gnments (Regulatory Guide 1.41)3A-143A.31Reactor Coolant Pressure B oundary Leakage De tection Systems (Regulatory Guide 1.45, May 1973). . . . . . . . . . . . . . . . . . . . . . 3A-143A.32Protection Against Pipe Whip Inside Containment (Regulatory Guide 1.46). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-15 Revision 52-09/29/2016 NAPS UFSAR TOC-vNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle Page3A.33Design Limits and Loading Combin ations for Seismic Class I Fluid System Components (Regulatory Guide 1.48). . . . . . . . . . . . . . 3A-183A.34Design, Maintenance, and Testing Criteria for Atmospheric Cleanup System Air Filtration and Adsorp tion Units of Li ght-Water-Cooled Nuclear Power Plants (Regulatory Guide 1.52). . . . . . . . . . . . . 3A-193A.35Qualification of Nu clear Power Plant Inspection, Examination, and Testing Personnel (Regulatory Guide 1.58, Revision 1, 1980) . 3A-193A.36Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Powe r Plants (Regulatory Guide 1.63, Revision 2, July 1978) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-193A.37Nondestructive Examin ation of Tubular Products (Regulatory Guide 1.66). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-203A.38Preoperational and In itial Start-Up Test Pr ograms for Water-Cooled Power Reactors (Regulatory Guide 1.68). . . . . . . . . . . . . . . . . . 3A-223A.39Assumptions for Evaluating the Hab itability of a Nuclear Plant Control Room During a Postulated Hazardous Chemical Release (Regulatory Guide 1.78). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-233A.40Preoperational Testing of Emer gency Core Cooling Systems for Pressurized Water Reacto rs (Regulatory Guide 1.79) . . . . . . . . 3A-233A.41Preoperational Testing of Inst rument Air Systems (Regulatory Guide 1.80). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-243A.42Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release (Regulatory Guide 1.95) . . . . . . . 3A-253A.43Instrumentation for Light-water-c ooled Nuclear Power Plants to Access Plant Conditions During and Follo wing an Accident (Regulatory Guide 1.97). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-253A.44Emergency Planning and Prepare dness for Nuclear Power Reactors (Regulatory Guide 1.101, November 1975). . . . . . . . . . . . . . . . 3A-253A.45Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants (Regulatory Guide 1.108, Revision 1, August 1977). . . . . . . . . 3A-25 Revision 52-09/29/2016 NAPS UFSARTOC-viNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle Page3A.46Calculation of Annual Doses to Ma n from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I (Regulatory Guide 1.109, March 1976) . . . . . . . . . 3A-253A.47Methods for Estimating Atmosphe ric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors (Re gulatory Guide 1.111, March 1976) . . . . . . . . . . . 3A-263A.48Calculation of Releases of Radioa ctive Materials in Gaseous and Liquid Effluents from Light-Water-Cool ed Po wer Reactors (Regulatory Guide 1.112). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-263A.49Inspection of Water-Control Structur es Associated with Nuclear Power Plants (Regulatory Guide 1.127) . . . . . . . . . . . . . . . . . . . . . . . . 3A-263A.50Qualification of Quality Assurance Program Audit Personnel of Nuclear Power Plants (Regulatory Guide 1.146, August 1980) . . . . . . . 3A-263A.51Pre-Earthquake Planning and Immedi ate Nuclear Power Plant Operator Post-Earthquake Actions (Regulatory Guide 1.166, March 1997)3A-263A.52Restart of a Nuclear Power Plant Shut Down By a Seismic Event (Regulatory Guide 1.167, March 1997). . . . . . . . . . . . . . . . . . . 3A-27 Appendix 3BComparison Between Time - History and Frequency Response Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3B-i Appendix 3CEffects of Piping System Br eaks Outside Containment. 3C-i3C.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3C-13C.2Criteria for Pipe Breaks and Analysis . . . . . . . . . . . . . . . . . . . .
3C-33C.3High-Energy Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3C-223C.4Plant Shutdown and Equipment Importa nt to Safety. . . . . . . . . 3C-233C.5Effects of Pipe Breaks and Cracks. . . . . . . . . . . . . . . . . . . . . . .
3C-243C.6Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3C-40 Appendix 3DTesting of Protective Coatings Under Design Basis Accident Conditions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3D-i Appendix 3EGeotechnical Investigations and Soil Sample Testing for the Service Water Reservoir. . . . . . . . . . . . . . . . . . . . . . . . . 3E-i3E.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3E-1 Revision 52-09/29/2016 NAPS UFSARTOC-viiNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle Page3E.2Dike and Foundation Conditions . . . . . . . . . . . . . . . . . . . . . . . . 3E-13E.3Settlement of Pump House for Units 1 and 2. . . . . . . . . . . . . . . 3E-73E.4Seepage Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3E-123E.5Stability Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3E-13 3E.6Liquefaction Potential of Foundation Materials. . . . . . . . . . . . . 3E-14 Appendix 3FSafety-Related Equipmen t Temperature Transients During the Limiting Main Steam Li ne Break. . . . . . . . . 3F-i3F.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3F-1 3F.2Calculational Model. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3F-4 3F.3Safety-Related Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3F-4 3F.4Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3F-6
- VOLUME IV -CHAPTER 4REACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-14.1Summary Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1 4.2Mechanical Design. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
4.2-14.3Nuclear Design. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-1 4.4Thermal and Hydraulic Design . . . . . . . . . . . . . . . . . . . . . . . . . 4.4-1 4.5Advanced Mark-BW Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.5-1CHAPTER 5REACTOR COOLANT SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1-15.1Summary Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1-1 5.2Integrity of the Reactor Coolant System Boundary. . . . . . . . . . 5.2-15.3Thermal-Hydraulic System Design . . . . . . . . . . . . . . . . . . . . . .
5.3-15.4Reactor Vessel and Appurtenances . . . . . . . . . . . . . . . . . . . . . . 5.4-1 5.5Component and Subsystem Design . . . . . . . . . . . . . . . . . . . . . .
5.5-15.6Instrumentation Application. . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.6-1 Revision 52-09/29/2016 NAPS UFSARTOC-viiiNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle PageAppendix 5ADiscussion Between the Nuclear Regulatory Commission and Virginia Electric & Power Company on Steam Generator Lower and Reactor Coolant Pump Supports for North Anna Units No. 1 and 2 . . . . . . . . . . . . . . . . . . . . 5A-i- VOLUME V -CHAPTER 6ENGINEERED SAFETY FEATURES . . . . . . . . . . . . . . . . . . . . . . . 6.1-16.1General. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1-16.2Containment Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.2-1 6.3Emergency Core Cooling System . . . . . . . . . . . . . . . . . . . . . . .
6.3-16.4Habitability Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.4-1 Appendix 6ASingle Failure Capability . . . . . . . . . . . . . . . . . . . . . . . . 6A-i6A.1Definitions of Terms. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6A-1 6A.2Active-Failure Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
6A-16A.3Passive-Failure Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
6A-1CHAPTER 7INSTRUMENTATION AND CONTROLS. . . . . . . . . . . . . . . . . . . .
7.1-17.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.1-17.2Reactor Trip System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.2-17.3Engineered Safety Features Actuation System. . . . . . . . . . . . . . 7.3-17.4Systems Required for Safe Shutdown . . . . . . . . . . . . . . . . . . . .
7.4-17.5Safety-Related Display Instrumentation. . . . . . . . . . . . . . . . . . .
7.5-17.6All Other Systems Required for Safety . . . . . . . . . . . . . . . . . . . 7.6-1 7.7Plant Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.7-1 7.8Emergency Response to Accidents . . . . . . . . . . . . . . . . . . . . . . 7.8-1 7.9Inadequate Core Cooling Monitor (ICCM) System. . . . . . . . . . 7.9-1
- VOLUME VI -CHAPTER 8ELECTRIC POWER SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.1-18.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
8.1-1 Revision 52-09/29/2016 NAPS UFSARTOC-ixNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle Page8.2Offsite Power System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.2-18.3Onsite Power Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.3-1CHAPTER 9AUXILIARY SYSTEMS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.1-19.1Fuel Handling and Storage. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.1-19.2Water Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.2-1 9.3Process Auxiliaries. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.3-1 9.4Air-Conditioning, Heating, Cooling, and Ventilation Systems . 9.4-19.5Other Auxiliary Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.5-1 9.6Control of Heavy Loads. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.6-1 Appendix 9AStructural Analysis of the Spent-Fuel Pool . . . . . . . . . . 9A-i9A.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-1 9A.2Description of the Fuel Building . . . . . . . . . . . . . . . . . . . . . . . . 9A-1 9A.3Description of the Deficiency. . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-2 9A.4Analysis of Safety Implications . . . . . . . . . . . . . . . . . . . . . . . . .
9A-39A.5Corrective Action Taken . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-3 9A.6Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-9 Appendix 9BFuel Pool Separating Wall Design . . . . . . . . . . . . . . . . .
9B-i9B.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-1 9B.2Casks Evaluated . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-1 9B.3Accidents Considered. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-1 9B.4Separating Wall Analysis and Design . . . . . . . . . . . . . . . . . . . .
9B-39B.5Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-6
- VOLUME VII -CHAPTER 10STEAM AND POWER CONVERSION SYSTEM. . . . . . . . . . . . . . 10.1-110.1Summary Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.1-1 10.2Turbine Generator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
10.2-1 Revision 52-09/29/2016 NAPS UFSAR TOC-xNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle Page10.3Main Steam System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.3-110.4Other Features of Steam and Power Conversion System. . . . . . 10.4-1CHAPTER 11RADIOACTIVE WASTE MANAGEMENT. . . . . . . . . . . . . . . . . . . 11.0-111.1Source Terms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.1-111.2Liquid Waste Disposal System. . . . . . . . . . . . . . . . . . . . . . . . . .
11.2-111.3Gaseous Waste Disposal System . . . . . . . . . . . . . . . . . . . . . . . .
11.3-111.4Process and Effluent Radiation Moni toring System . . . . . . . . . 11.4-111.5Solid Waste System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.5-1 11.6Offsite Radiological Monitoring Program . . . . . . . . . . . . . . . . . 11.6-1 Appendix 11ATritium Control. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-i11A.1System Sources. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-1 11A.2Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-2 11A.3Design Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-2 Appendix 11BRadiation Exposure Evaluation for Estimated Radioactive Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-i11B.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-1 11B.2Summary and Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-1 11B.3Radiation Exposure from Gaseous Effl uents. . . . . . . . . . . . . . . 11B-511B.4Radiation Exposure from Liquid Efflue nts . . . . . . . . . . . . . . . . 11B-911B.5Dose Totals and Comparison with Federal Regulations and Natural Background. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-1411B.6Computational Methods for Doses Resulting from Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-1511B.7Computational Methods for Doses Resulting from Liquid Effluents. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-18 Appendix 11CEvaluation of Compliance With Proposed 10 CFR 50, Appendix I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-i11C.1Summary and Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-1 11C.2Doses from Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . .
11C-3 Revision 52-09/29/2016 NAPS UFSARTOC-xiNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle Page11C.3Doses from Gaseous Effluents. . . . . . . . . . . . . . . . . . . . . . . . . . 11C-411C.4Data and Methodology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-611C.5Source-Term Information. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
11C-17CHAPTER 12RADIATION PRO TECTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.0-112.1Shielding. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.1-1 12.2Ventilation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.2-1 12.3Health Physics Program. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.3-1 12.4Radioactive Materials Safety . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.4-1 Appendix 12ADescription of Neutron Supplemen tary Shield. . . . . . . . 12A-i12A.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12A-2 12A.2Neutron Shield Design Criteria . . . . . . . . . . . . . . . . . . . . . . . . .
12A-212A.3Effectiveness of the Supplementary Neutron Shield . . . . . . . . . 12A-312A.4Shield Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12A-4 12A.5Reactor Pressure Vess el Support Integrity Reviews . . . . . . . . . 12A-6CHAPTER 13CONDUCT OF OPERATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.1-113.1Organizational Structure of Virginia Electric and Power Company. . . . . . . . . . . . . . . . . . . .
13.1-113.2Training Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.2-1 13.3Emergency Planning. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.3-1 13.4Review and Audit. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.4-1 13.5Plant Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.5-1 13.6Plant Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.6-1 13.7Industrial Security . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.7-1CHAPTER 14INITIAL TESTS AND OP ERATION . . . . . . . . . . . . . . . . . . . . . . . . 14.0-114.1Test Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.1-1 14.2Augmentation of VEPCO's Staff for Initial Test and Operation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.2-1 Revision 52-09/29/2016 NAPS UFSARTOC-xiiNorth Anna Power Station Updated Final Safety Analysis ReportTable of Contents (continued)SectionTitle PageAppendix 14ANRC Questions and VEPCO's Responses Regarding the North Anna Power Station Unit 2 Modified Startup Physics Testing Program . . . . . . . . . . 14A-i
- VOLUME VIII -CHAPTER 15ACCIDENT ANALYSES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.0-115.1Condition I - Normal Operation and Oper ational Transients. . . 15.1-115.2Condition II - Faults of Moderate Frequency. . . . . . . . . . . . . . . 15.2-115.3Condition III - Loss-of-Coolant Accident (LOCA) Accidents. . 15.3-115.4Condition IV - Limiting Faults. . . . . . . . . . . . . . . . . . . . . . . . . . 15.4-1 Appendix 15ASpent Fuel Cask Drop Analysis . . . . . . . . . . . . . . . . . . . 15A-i15A.1Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-115A.2Arrangement of Spent Fuel Cask Handling System. . . . . . . . . . 15A-115A.3Cask Drop Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-2CHAPTER 16TECHNICAL SPECIFICATIONS AND REQUIREMENTS. . . . . 16.1-116.1Safety and Environmental Technical Specifications . . . . . . . . . 16.1-116.2Technical Requirements. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16.2-1CHAPTER 17QUALITY ASSURANCE PROGRAM . . . . . . . . . . . . . . . . . . . . . . .
17-1CHAPTER 18PROGRAMS AND ACTIVITIES THAT MANAGE THE EFFECTS OF AGING . . . . . . . . . . . . . . . . . . . . . .18-118.1New Aging Management Activities. . . . . . . . . . . . . . . . . . . . . .18-118.2Existing Aging Management Activities. . . . . . . . . . . . . . . . . . .18-518.3Time-Limited Aging Analysis . . . . . . . . . . . . . . . . . . . . . . . . . .
18-2218.4TLAA Supporting Activ ities . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-3118.5References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
18-33 Revision 52-09/29/2016 NAPS UFSAR 1FOREWORD In the May 9, 1980, edition of the Federal Register (45 FR 30614), the NRC published a Final Rule requiring all licensed reactors to pe riodically update their Final Safety Analysis Reports. The purpose of th e Rule was to establish baseline re ference 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 cons titute a licensing action, but is only intended to provide information. The NRC Staff may review the materi al submitted, but does not intend to formally approve it. The NRC intends to us e the updated FSAR in the future for appropriate applications such as reporting of deviations fr om conditions stated in the UFSAR.The Rule became effective July 22, 1980, and established the following basic requirements for VEPCO' s 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 "Su pplementary Information" section of the Final Rule notice clarifies this requirement by stating that no analyses other than those already pr epared or submitted pursuant to NRC requirement s 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 previo usly included in the FSAR may be incorporated in the UFSAR at the option of the licensee. Furtherm ore, specialized studies provided in the original FSAR (e.g., seismology, meteorology) should include the latest information developed in respons e 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 th at 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 maxi mum 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 re flect changes made up to a maximum of six months prior to the date of filing.
Revision 52-09/29/2016 NAPS UFSAR 2*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 au thorized of ficer of VEPCO.*The initial UFSAR should be a clean doc ument without change bars and revision numbers. The subsequent annual revisions sh ould 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 serv ices in April 1981, and NUS began work on the project immediately. The project was accomplished in four basic phases:1.Document Retrieval2.Change Package Development3.FSAR Revision4.Printing*During the initial document retrieval phase in the Spring of 1981, NUS engineers researched the licensing co rrespondence files at VEPCO of fices 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 pha se, NUS engineers periodically visited Richmond and the plant sites to acquire ne wly deve loped information. NUS was also placed on the distribution list for VEPCO/NRC correspondence.
The document retrieval phase continued un til early 1982, at whic h time sufficient information was available to document changes up to the January 31, 1982, cutoff date.*The documentation retrieved dur ing the first phase was reviewed in detail during the second phase to determine the pa rticular "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. Thes e files were defined as "change packages." Development of the change packages co ntinued in parallel with the document retrie val phase, with new information being reviewed and assigned to appropriate change packages. The final change packages became a work product de livered to VEPCO on conclusion of the update effort and are available for tracing th e sources of changes to the original FSARs.*After development of the init ial change packages the materi al 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 52-09/29/2016 NAPS UFSAR 3 The revision phase for most FSAR chapters included two cycles of VEPCO review and comment. These comments became part of th e change packages and were used in the development of the final draft UFSAR.*VEPCO reviewed and approved the final draf t chapters of the U FSARs 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 tr ansmitted under cove r letter supplied to NUS by VEPCO (see the attach ment to this foreword).
The remaining copies were shipped to Richmond and the plant sites.
The following work products we re also delivered to VEPCO by NUS and are available for use in producing subse quent annual updates:*Printer's copy of the UFSARs*Annotated FSARs (2 copies)
- Final Change Packages (2 sets)*Plant Drawing Indexes*Key Word Indexes
- IBM Displaywriter Floppy Disc s (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 ef fective pages, the key word indexes, the plant drawi ng indexes and a record of changes.Further 10 CFR 50.71(e) rulemaking pertaini ng to UFSAR requireme nts for nuclear power stations was promulgated as recently as Ju ly 29, 1996 [61 FR 39278]. In particular , the annual revision requirement has been relaxed to six months after each refuelin g outage provided the interval between successive upda tes does not exceed 24 months.The NRC issued a letter to licensees da ted Oc tober 9, 1996, entitled "Request for Information Pursuant to 10 CFR 50.54(f) Regarding Adequacy and Av ailability of Design Basis Information." The letter required submittal of information that will provide the NRC added confidence and assurance that Virginia Electric and Power Company's nuclear plants are operated and maintained within their desi gn bases and that any deviations are reconciled in a timely manner. The Company's response (Serial N
- o.96-535) dated Februa ry 7, 1997, described previously conducted programm atic 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. Proc ess enhancements to si mplify administrative Revision 52-09/29/2016 NAPS UFSAR 4 controls, to increase acc ountability for technical content, and to improve UFSAR accessibility and usability are promoted by conversion to electronic media.
Under separate cover (Seria l No.97-108) dated May 23, 1997, V irginia Electric and Power Company notified the NRC about its project to ad dress potential regulatory concerns involving the current design and licensing bases for the Surry and North Anna Power Stations. This project scope ex ceeds the level of scruti ny normally applied to the curren t licensing basis through routine surveillance and quality as surance activities. In order to facilitate thorough review, exhaustive validation, and a rigorous corrective action process, the reco mmended conversion to electronic media was implemented in Revision 32 of the North Anna UFSAR. The entire text of the UFSAR was entered into electronic medi
- a. The conversion was accomplish ed 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 co nducted by comparing a printed version of the entire electronic document with current controlle d distribution copies. Thus, the electronic UFSAR was conveyed into service as the quality assuran ce document of record without introducing any substantive, tec hnical, or non-editorial changes.
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Revision 52-09/29/2016 NAPS UFSAR 6 Intentionally Blank Revision 52-09/29/2016 NAPS UFSAR LEP VOLUME I -General Table of Contents (Note: Repeated in each volume)First Page Last PageRevisionTOC-iTOC-xii Revision 52-09/29/2016ForewordFirst Page Last PageRevision 1 6 Revision 52-09/29/2016 List of Effective PagesFirst Page Last PageRevision LEP-1 LEP-8 Revision 52-09/29/2016 Chapter 1 First Page Last PageRevision 1-i 1-iv Revision 52-09/29/2016 1.1-1 1.1-2 Revision 52-09/29/2016 1.2-1 1.2-14 Revision 52-09/29/2016 1.3-1 1.3-24 Revision 52-09/29/2016 1.4-1 1.4-10 Revision 52-09/29/2016 1.5-1 1.5-26 Revision 52-09/29/2016 1.6-1 1.6-4 Revision 52-09/29/2016 Chapter 2 First Page Last PageRevision 2-i 2-xii Revision 52-09/29/2016 2.1-1 2.1-26 Revision 52-09/29/2016 2.2-1 2.2-10 Revision 52-09/29/2016 2.3-1 2.3-74 Revision 52-09/29/2016 2.4-1 2.4-40 Revision 52-09/29/2016 2.5-1 2.5-40 Revision 52-09/29/2016 2A-i 2A-ii Revision 52-09/29/2016 2A-1 2A-38 Revision 52-09/29/2016 2A Att. 1-1 2A Att. 1-22 Revision 52-09/29/2016 2A Att. 2-1 2A Att. 2-74 Revision 52-09/29/2016 2A Att. 3-1 2A Att. 3-60 Revision 52-09/29/2016 2A Att. 4-1 2A Att. 4-48 Revision 52-09/29/2016LIST OF EFFECTIVE PAGES Revision 52-09/29/2016 NAPS UFSAR LEP-2LIST OF EFFECTIVE PAGES (CONTINUED)- VOLUME II -- VOLUME III -
2B-i 2B-ii Revision 52-09/29/2016 2B-1 2B-22 Revision 52-09/29/2016 2C-i 2C-ii Revision 52-09/29/2016 2C-1 2C-52 Revision 52-09/29/2016 Chapter 3 First Page Last PageRevision 3-i 3-xxx Revision 52-09/29/2016 3.1-1 3.1-44 Revision 52-09/29/2016 3.2-1 3.2-26 Revision 52-09/29/2016 3.3-1 3.3-4 Revision 52-09/29/2016 3.4-1 3.4-2 Revision 52-09/29/2016 3.5-1 3.5-12 Revision 52-09/29/2016 3.6-1 3.6-42 Revision 52-09/29/2016 3.7-1 3.7-122 Revision 52-09/29/2016 3.8-1 3.8-224 Revision 52-09/29/2016 3.9-1 3.9-42 Revision 52-09/29/2016 3.10-1 3.10-34 Revision 52-09/29/20163.11-13.11-22 Revision 52-09/29/2016 Chapter 3 (continued)First Page Last PageRevision 3-i 3-xxx Revision 52-09/29/2016 3A-i 3A-ii Revision 52-09/29/2016 3A-1 3A-30 Revision 52-09/29/2016 3B-i 3B-ii Revision 52-09/29/2016 3B-1 3B-20 Revision 52-09/29/2016 3C-i 3C-ii Revision 52-09/29/2016 3C-1 3C-142 Revision 52-09/29/2016 3D-i 3D-ii Revision 52-09/29/2016 3D-1 3D-232 Revision 52-09/29/2016 The Franklin Institute Resear ch Laboratories Technical Report F-C3486, Testing of Protective Coatings under Design Basis Accident Environment , dated April 1973; 232 pages which were taken from original report a nd are not subject to revision.
Chapter 2 (continued)First PageLast PageRevision Revision 52-09/29/2016 NAPS UFSAR LEP-3LIST OF EFFECTIVE PAGES (CONTINUED)- VOLUME IV -
3E-i 3E-ii Revision 52-09/29/2016 3E-13E-116 Revision 52-09/29/2016 3E Att. 1-i 3E Att. 1-ii Revision 52-09/29/2016 3E Att. 1-1 3E Att. 1-24 Revision 52-09/29/2016 3E Att. 2-i 3E Att. 2-ii Revision 52-09/29/2016 3E Att. 2-1 3E Att 2-20 Revision 52-09/29/2016 3E Att. 3-i 3E Att. 3-ii Revision 52-09/29/2016 3E Att. 3-1 3E Att. 3-58 Revision 52-09/29/2016Geotechnical Engineers Inc. Report on Laboratory Soil Testing , dated June 21, 1976; 56 pages which were taken from original report and are not subject to revision.
3E Att. 4-i 3E Att. 4-ii Revision 52-09/29/2016 3E Att. 4-1 3E Att. 4-66 Revision 52-09/29/2016 3E Att. 5-i 3E Att. 5-ii Revision 52-09/29/2016 3E Att. 5-1 3E Att. 5-52 Revision 52-09/29/2016 3F-i 3F-ii Revision 52-09/29/2016 3F-1 3F-40 Revision 52-09/29/2016 Chapter 4 First Page Last PageRevision 4-i 4-x Revision 52-09/29/2016 4-1 4-2 Revision 52-09/29/2016 4.1-1 4.1-16 Revision 52-09/29/2016 4.2-1 4.2-100 Revision 52-09/29/2016 4.3-1 4.3-90 Revision 52-09/29/2016 4.4-1 4.4-84 Revision 52-09/29/2016 4.5-1 4.5-48 Revision 52-09/29/2016 Chapter 5 First Page Last PageRevision 5-i 5-viii Revision 52-09/29/2016 5.1-1 5.1-18 Revision 52-09/29/2016 5.2-1 5.2-94 Revision 52-09/29/2016 5.3-1 5.3-2 Revision 52-09/29/2016 5.4-1 5.4-24 Revision 52-09/29/2016 5.5-1 5.5-88 Revision 52-09/29/2016 Chapter 3 (continued)First PageLast PageRevision Revision 52-09/29/2016 NAPS UFSAR LEP-4LIST OF EFFECTIVE PAGES (CONTINUED)- VOLUME V -
5.6-1 5.6-10 Revision 52-09/29/2016 5A-i 5A-ii Revision 52-09/29/2016 5A-1 5A-164 Revision 52-09/29/2016 Discussion between the Nuclear Regulatory Commission and Virginia Electric & Power Company on Steam Generator Lower and Reac tor Coolant Pump Supports for North Anna Units No. 1 and 2 , Transcript, dated April 13, 1976; co rrected copy of transcript, dated May 18, 1976; 164 pages which were taken from original report and are not s ubject to revision.
5A Att. 1-i5A Att. 1-ii Revision 52-09/29/2016 5A Att. 1-1 5A Att. 1-28 Revision 52-09/29/2016 Chapter 6 First Page Last PageRevision 6-i 6-xiv Revision 52-09/29/2016 6.1-1 6.1-4 Revision 52-09/29/2016 6.2-1 6.2-288 Revision 52-09/29/2016 6.3-1 6.3-70 Revision 52-09/29/2016 6.4-1 6.4-20 Revision 52-09/29/2016 6A-i 6A-ii Revision 52-09/29/2016 6A-1 6A-6 Revision 52-09/29/2016 Chapter 7 First Page Last PageRevision 7-i 7-viii Revision 52-09/29/2016 7.1-1 7.1-14 Revision 52-09/29/2016 7.2-1 7.2-54 Revision 52-09/29/2016 7.3-1 7.3-50 Revision 52-09/29/2016 7.4-1 7.4-8 Revision 52-09/29/2016 7.5-1 7.5-22 Revision 52-09/29/2016 7.6-1 7.6-8 Revision 52-09/29/2016 7.7-1 7.7-46 Revision 52-09/29/2016 7.8-1 7.8-2 Revision 52-09/29/2016 7.9-1 7.9-8 Revision 52-09/29/2016 Chapter 5 (continued)First PageLast PageRevision Revision 52-09/29/2016 NAPS UFSAR LEP-5LIST OF EFFECTIVE PAGES (CONTINUED)- VOLUME VI -- VOLUME VII -
Chapter 8 First Page Last PageRevision 8-i 8-iv Revision 52-09/29/2016 8.1-1 8.1-6 Revision 52-09/29/2016 8.2-1 8.2-12 Revision 52-09/29/2016 8.3-1 8.3-58 Revision 52-09/29/2016 Chapter 9 First Page Last PageRevision 9-i 9-xii Revision 52-09/29/2016 9.1-1 9.1-54 Revision 52-09/29/2016 9.2-1 9.2-62 Revision 52-09/29/2016 9.3-19.3-116 Revision 52-09/29/2016 9.4-1 9.4-38 Revision 52-09/29/2016 9.5-1 9.5-86 Revision 52-09/29/2016 9.6-1 9.6-12 Revision 52-09/29/2016 9A-i 9A-ii Revision 52-09/29/2016 9A-1 9A-22 Revision 52-09/29/2016 9B-i 9B-ii Revision 52-09/29/2016 9B-1 9B-16 Revision 52-09/29/2016 Chapter 10 First Page Last PageRevision 10-i 10-iv Revision 52-09/29/2016 10.1-1 10.1-6 Revision 52-09/29/2016 10.2-1 10.2-20 Revision 52-09/29/2016 10.3-1 10.3-18 Revision 52-09/29/2016 10.4-1 10.4-60 Revision 52-09/29/2016 Chapter 11 First Page Last PageRevision11-i11-xii Revision 52-09/29/201611-111-2 Revision 52-09/29/201611.1-111.1-22 Revision 52-09/29/201611.2-111.2-56 Revision 52-09/29/201611.3-111.3-20 Revision 52-09/29/2016 Revision 52-09/29/2016 NAPS UFSAR LEP-6LIST OF EFFECTIVE PAGES (CONTINUED)11.4-111.4-22 Revision 52-09/29/201611.5-111.5-10 Revision 52-09/29/201611.6-111.6-8 Revision 52-09/29/201611A-i11A-ii Revision 52-09/29/201611A-111A-6 Revision 52-09/29/201611B-i11B-ii Revision 52-09/29/201611B-111B-34 Revision 52-09/29/201611C-i11C-ii Revision 52-09/29/201611C-111C-162 Revision 52-09/29/2016 Chapter 12 First Page Last PageRevision 12-i 12-vi Revision 52-09/29/2016 12-1 12-2 Revision 52-09/29/2016 12.1-1 12.1-44 Revision 52-09/29/2016 12.2-1 12.2-12 Revision 52-09/29/2016 12.3-1 12.3-4 Revision 52-09/29/2016 12.4-1 12.4-2 Revision 52-09/29/2016 12A-i 12A-ii Revision 52-09/29/2016 12A-1 12A-22 Revision 52-09/29/2016 Chapter 13 First Page Last PageRevision 13-i 13-ii Revision 52-09/29/2016 13.1-1 13.1-2 Revision 52-09/29/2016 13.2-1 13.2-4 Revision 52-09/29/2016 13.3-1 13.3-2 Revision 52-09/29/2016 13.4-1 13.4-2 Revision 52-09/29/2016 13.5-1 13.5-2 Revision 52-09/29/2016 13.6-1 13.6-2 Revision 52-09/29/2016 13.7-1 13.7-2 Revision 52-09/29/2016 Chapter 14 First Page Last PageRevision 14-i 14-iv Revision 52-09/29/2016 14.0-1 14.0-4 Revision 52-09/29/2016Chapter 11 (continued)First PageLast PageRevision Revision 52-09/29/2016 NAPS UFSAR LEP-7LIST OF EFFECTIVE PAGES (CONTINUED)- VOLUME VIII -
14.1-1 14.1-52 Revision 52-09/29/2016 14.2-1 14.2-2 Revision 52-09/29/2016 14A-i 14A-ii Revision 52-09/29/2016 14A-1 14A-10 Revision 52-09/29/2016 Chapter 15 First Page Last PageRevision 15-i 15-xviii Revision 52-09/29/2016 15.0-1 15.0-6 Revision 52-09/29/2016 15.1-1 15.1-32 Revision 52-09/29/2016 15.2-115.2-118 Revision 52-09/29/2016 15.3-1 15.3-192 Revision 52-09/29/2016 15.4-1 15.4-158 Revision 52-09/29/2016 15A-i 15A-ii Revision 52-09/29/2016 15A-1 15A-4 Revision 52-09/29/2016 15A Att. 1-i 15A Att. 1-ii Revision 52-09/29/2016 15A Att. 1-1 15A Att. 1-52 Revision 52-09/29/2016 Chapter 16 First Page Last PageRevision 16-i 16-ii Revision 52-09/29/2016 16.1-1 16.1-4 Revision 52-09/29/2016 16.2-1 16.2-2 Revision 52-09/29/2016 Chapter 17 First Page Last PageRevision 17-1 17-2 Revision 52-09/29/2016 Chapter 18 First Page Last PageRevision 18-i 18-iv Revision 52-09/29/2016 18-1 18-42 Revision 52-09/29/2016 Chapter 14 (continued)First PageLast PageRevision Revision 52-09/29/2016 NAPS UFSAR LEP-8 Intentionally Blank