ML17033B480

Redacted Updated Final Safety Analysis Report

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: ML17033B480 ML17033B492 ML17033B500 ML17033B509 ML17033B515 ML17033B518 ML17033B525 ML17033B531 ML17033B533 ML17033B540 ML17033B545 ML17033B550 ML17033B570 ML17033B573 ML17033B575 ML17033B583 ML17033B585 ML17033B590 ML17033B591
References
Download: ML17033B480 (114)

Text

NORTH ANNA POWER STATION UPDATED FINAL SAFETY ANALYSIS REPORT

Intentionally Blank Revision 5209/29/2016 NAPS UFSAR 1 REVISION

SUMMARY

Revision 5209/29/16 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 6.4-1 Updated Table reflects addition of chemicals

[FN-2008-025] for Bearing Cooling System.

Table 7.2-2, 7.3.1.2, Table 7.5-3 Updated the uncertainty value for pressurizer

[NAPS-UCR-2016-012] pressure protection Table 6.4-1 Updated Table to remove zinc chloride which

[NAPS-UCR-2016-016] is no longer stored on site.

Table 15.3-1 Modified to replace reference to appropriate

[NAPS-UCR-2016-017] tables for reactor vessel upflow conversion.

6.3.2.1.1 Modified to reference common figure for

[NAPS-UCR-2016-018] accumulator injection following a large break loss of coolant accident.

9.5.1.1, Table 9.5-7 Update reflects engineering evaluations

[NAPS-UCR-2016-013] completed to address fire 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, Update reflects reactor coolant pump seal 5.5.1.3.11, Table 5.2-3, Table 5.5-1, Table replacement - Unit 2 final configuration.

9.3-4, Figure 5.5-1

[NAPS-UCR-2013-010]

9.5.1.3.1.8 Modified to clarify the fire protection system

[NAPS-UCR-2014-029] use of coating versus wrap.

6.3.3.13, 6.3 References, Table 6.3-8, Update reflects reactor vessel upflow 15.1.8.1, 15.1.8.4, 15.1 References, 15.3.1, conversion Unit 2.

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, 15.4.1.11 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]

5.1.3.1, 5.3, 5.5.1.2, 5.5.1.3.1, 5.5.1.3.5, Update reflects reactor coolant pump seal 5.5.1.3.11, Table 5.2-3, Table 5.5-1, Table replacement - Unit 2 Interim 1A 9.3-4, Figure 5.5-1, Figure 5.5-2 configuration.

[NAPS-UCR-2016-010]

Revision 5209/29/2016 NAPS UFSAR 2 Revision 5209/29/16 (continued)

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

8.1.1, 8.2.1, Figure 8.2-1, Figure 8.2-2 Modified to clarify transmission line number,

[NAPS-UCR-2015-019] 573 name changed to Spotsylvania.

Figure 8.2-1, 8.3.1.1.1, 8.3.1.1.2.3 Update reflects station service bus to

[NAPS-UCR-2013-027] emergency bus cross tie installation.

Table 9.3-3 Update reflects the replacement of the reactor

[NAPS-UCR-2014-027] containment sump pumps.

Figure 10.4-9 (Sheet 1 of 4), (Sheet 3 of 4) Update reflects bearing cooling recirculation

[NAPS-UCR-2015-010] modification - Unit 2.

4.2.2.2, 4.4.3.1.1, 4.5.2.1.3.2.4, 6.3.3.12, Update reflects reactor vessel upflow Figure 6.3-15, Figure 6.3-16, Figure 6.3-17, conversion Unit 2.

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]

18.1.4, 18.2.19, Table 18-1 Update reflects closure of commitments 19

[NAPS-UCR-2015-022] (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) Update reflects Unit 2 Steam Generator

[NAPS-UCR-2015-009] Blowdown Sodium Analyzer Upgrade.

15.2.4.3 Update adds diverse indications available to

[NAPS-UCR-2015-017] the operator for identification and correction of low flow boron dilution events.

11.5.3.4 Update reflects administrative controls related

[NAPS-UCR-2013-025] 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, Update reflects the replacement of the Fuel 9.5.4.1, Figure 9.5-2 Oil Pump House fire detection and

[NAPS-UCR-2015-012] extinguishing system.

7.8 Incorporated editorial changes to the list of

[NAPS-UCR-2015-021] emergency procedures.

9.2.3.1, Table 9.2-10 Update to reflect abandoned domestic water

[FN-2006-016] components.

Revision 5209/29/2016 NAPS UFSAR 3 Revision 5209/29/16 (continued)

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

Table 7.5-3 Changed the Aux Feedwater Flow Available

[NAPS-UCR-2015-014] Indicated Accuracy value on Table 7.5-3 from +/- 15 gpm to -21 to +17 gpm.

Revision 5109/30/15 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

4.1, 4.2.1.2.2, Table 4.2-2, Figure 4.2-4 Reflects implementation of the Westinghouse

[NAPS-UCR-2015-004] integral nozzle design.

9.4.2.2, 9.4.3.2, 9.4.5.2, Table 9.4-3, Update reflects modification of ventilation Figure 9.4-2 (Sh. 1), Figure 9.4-4 system roll filters to box filters.

[FN-2006-026]

12.2.5 Update reflects change to the SCBA Air quality

[NAPS-UCR-2015-003] requirements.

9.3.4.2.1, 9.3.4.2.4.14 Update reflects changes to the Fleet Primary

[NAPS-UCR-2015-011] Resin Strategies.

Table 9.5-1 Reflects the 17-ton CO2 tank replacement.

[NAPS-UCR-2014-007]

2.3.3.2.1, 2.3.3.2.2, 2.3.3.2.3, Table 2.3-15 Reflects replacement of Obsolete Met Tower

[NAPS-UCR-2014-042] Equipment.

18.2.3, 18.2.13, 18.3.2.4, 18.5 Refs, Table 18-1 Updates Chapter 18 to reflect closure of

[NAPS-UCR-2015-007] various licensing commitments in Table 18-1 (Items 12, 24, 30) and reflects changes to Boric Acid Corrosion Surveillance and the Augmented Inspection Program.

9.3.2.1.1, Figure 9.3-2 (Sh. 10 of 12) Reflects Unit 1 Steam Generator Blowdown

[NAPS-UCR-2014-036] Sodium Analyzer Upgrade.

11.4.3, 11.4.3.2 Reflect replacement of Main Steam Radiation

[NAPS-UCR-2011-010] Monitors.

5.1.3.1, Table 5.2-3, 5.3, 5.5.1.2, 5.5.1.3.1, Reflect Reactor Coolant Pump Seal 5.5.1.3.5, 5.5.1.3.11, Table 5.5-1, Figure 5.5-1, Replacement - Unit 1 Interim 1B configuration.

Figure 5.5-2

[NAPS-UCR-2015-008]

4.2.1.2, 4.2.3.1.3, 4.2.3.2, 4.2.3.2.1, Reflects the re-insertion of Secondary Source Figure 4.2-25, 11A.1, 11A.1.3, 11A.3 Assemblies.

[NAPS-UCR-2014-010]

Revision 5209/29/2016 NAPS UFSAR 4 Revision 5109/30/15 (continued)

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

Figure 10.4-3 (Sheet 2 of 4) Removed the restricting orifice (RO) on the

[NAPS-UCR-2014-023] condensate recirculation line to the condenser.

Figure 10.4-4 Removed the restricting orifice (RO) on the

[NAPS-UCR-2014-024] condensate recirculation line to the condenser.

15.1 References, 15.2 References, 15.3.4.2.1, Implements topical report VP-FRD-41, 15.3 References, 15.4 References Rev 0.2.

[NAPS-UCR-2015-005]

9.2.1.2.4 Update reflects removal of internals and

[NAPS-UCR-2013-015] actuators for service water traveling screens spray wash system air operated control valves.

9.5.1.1 Update adds the Beyond Design Basis Clean

[NAPS-UCR-2013-023] 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 Updated to indicate closure of license renewal

[NAPS-UCR-2014-039] commitments 14 (follow industry activities related to reactor vessel internals issues) and 20 (follow industry activities related to Alloy 82/182 weld material).

Table 15.4-19, Figure 15.4-50, Figure 15.4-51, Update reflects the implementation of the Figure 5.4-52, Figure 15.4-53 Control Rod Ejection analysis.

[NAPS-UCR-2014-040]

15.4.3.4.5 Modified reference to indicate the correct table.

[NAPS-UCR-2015-001]

9.5.1.2.1 Update reflects the addition of fire protection

[NAPS-UCR-2014-017] for the security enclosure on Unit 1 turbine deck.

8.3.1.1.2.3 Update reflects Beyond Design Basis

[NAPS-UCR-2014-026] installation of electrical connections.

TOC, 18.2.16, 18.5 References Modified to reflect program name change to

[NAPS-UCR-2014-041] Flow Accelerated Corrosion Program 8.2.1, 8.2.2, Figure 8.2-2 (Sheet 3 of 6) Update reflects replacement of 500/230 kV

[NAPS-UCR-2014-005] transformer #5.

4.2.1.1.1, 4.2.1.2, 4.2.1.3.1, 4.2 References Update reflects new Westinghouse Cladding

[NAPS-UCR-2014-019] Corrosion Model.

6.2.2.2, 6.3.2.2.1, 10.4.3.2 Update reflects Beyond Design Basis

[NAPS-UCR-2014-020] mechanical connections.

Revision 5209/29/2016 NAPS UFSAR 5 Revision 5109/30/15 (continued)

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

5.1.3.1, Table 5.2-3, 5.3, 5.5.1.2, 5.5.1.3.1, Update reflects reactor coolant pump seal 5.5.1.3.5, 5.5.1.3.11, Table 5.5-1, Figure 5.5-1, replacement interim configuration for Unit 2.

Figure 5.5-2

[NAPS-UCR-2014-038]

9.5.5.3, Figure 9.5-6 Update reflects EDG coolant expansion tank

[NAPS-UCR-2012-017] vent valve installation.

5.1.1.8, 5.5.7.2, Table 5.5-15 Update reflects repair of 2-RC-MOV-2593.

[NAPS-UCR-2012-021]

11.4.3, 11.4.3.2 Modified to reflect Unit 2 main steam radiation

[NAPS-UCR-2012-022] monitor replacement.

Table 3.9-1 Update reflects replacement of AOV valves

[NAPS-UCR-2012-031] 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 Update reflects modifications to Fire Protection

[NAPS-UCR-2013-004] and Domestic Water Systems to accommodate Unit 3 excavation area.

9.1.3.5 Update reflects Beyond Design Basis

[NAPS-UCR-2013-011] installation of spent fuel pool instrumentation.

Figure 10.4-3 (Sheet 2 of 4) Update reflects Unit 2 condensate pump

[NAPS-UCR-2014-002] recirculation flow control valve replacement.

Figure 10.4-4 Update reflects Unit 2C feedwater pump

[NAPS-UCR-2014-003] recirculation flow control valve replacement.

6.2.1.1.1.3, 6.2.2.2, 6.2.2.6.2.1, 6.2.2.6.2.2, Update reflects revised NAPS Containment Table 6.2-2, Table 6.2-4, Table 6.2-11, Safety Analysis.

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]

8.3.1.1.2.3 Update reflects Beyond Design Basis

[NAPS-UCR-2014-013] installation of power cables.

Revision 5209/29/2016 NAPS UFSAR 6 Revision 5109/30/15 (continued)

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

4.4.1.1, 4.4.2.3.2.4 (new), 4.4 Refs, Update reflects discussion of the W-3 Alternate Table 4.4-5, 4.5 Refs, 15.0, 15 Refs, 15.2.1.2.1, DNB correlations approved in Appendix D to 15.2.2.2.1, 15.2.7.2.1, 15.2.10.2, 15.2.11.2.1, DOM-NAF-2-P-A.

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]

4.2.1.2, 4.2.3.1.3, 4.2.3.2, 4.2.3.2.1, Update reflects the re-insertion of secondary Figure 4.2-25, 11A.1, 11A.1.3 (new), 11A.3 source assemblies in Unit 2.

[NAPS-UCR-2014-025]

3A.45 Updated reference to Regulatory Guide 1.108

[NAPS-UCR-2014-028] with Regulatory Guide 1.9 9.3.4.2.4.22 Update reflects replacement of flanges for

[NAPS-UCR-2014-031] 2-CH-FT-2113.

9.3.4.1 Update reflects Beyond Design Basis

[NAPS-UCR-2014-032] installation of RCS injection alternate connection.

8.3.1.1.1, 8.3.1.2.1 Update reflects Beyond Design Basis

[NAPS-UCR-2014-033] installation of electrical connections.

Figure 4.4-21 Update reflects abandonment of Unit 2 core

[NAPS-UCR-2014-035] exit thermocouples.

Revision 5009/30/14 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

9.3.3.2 Reference correction.

[NAPS-UCR-2014-030]

Table 15.4-9, Table 15.4-10 Update incorporates the latest assessments

[NAPS-UCR-2014-004] 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 Sections updated to reflect that various testing

[NAPS-UCR-2014-018] frequency is determined by Surveillance Frequency Control Program.

Revision 5209/29/2016 NAPS UFSAR 7 Revision 5009/30/14 (continued)

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

9.5.1.2.1, 9.5 Refs Description updated to reflect beyond design

[NAPS-UCR-2014-008] basis connection to Fire Protection System, which can supply emergency make-up water to the spent fuel pool.

9.5.3 Included the use of light-emitting diodes (LED)

[NAPS-UCR-2013-022] units for emergency lighting in the main control room.

9.3.4.1, 9.3.4.2.4.24, Table 9.3-5, Table 9.3-6, Update reflects the addition of a Unit 2 zinc Figure 9.3-5 injection skid.

[NAPS-UCR-2012-024]

5.2.3.2, 9.3.4.2.4.24 Update reflects that Unit 2 allows zinc

[NAPS-UCR-2012-039] injection.

3.8.2.7.6.1.1 Update removes discussion of temporary

[NAPS-UCR-2013-026] concrete floor repairs to the Unit 1 recirculation spray sump area.

3.3.2, 3.5.4 Modified to clarify that various concrete

[NAPS-UCR-2014-011] thicknesses are allowed that provide missile protection.

6.2.2.2, 6.2.2.8.3, 6.2.4.2, Figure 6.2-48, Update reflects revised low-low level setpoint 7.3.2.12 (new) for the Casing Cooling tank to prevent vortex

[NAPS-UCR-2014-001] inception.

2.4.2.2 Update adds a description of the new Storm

[NAPS-UCR-2013-017] Water Sump Pump System.

Figure 1.2-1 Update adds changes to the site plan associated

[NAPS-UCR-2010-013] with the alternate ISFSI haul route.

Figure 8.2-1, Figure 8.2-2 (Sheet 1 of 6) Update reflects 34.5kV Power Distribution and

[NAPS-UCR-2010-028] Switchyard Modifications.

9.5.2.1.1 Clarified the power source for the public

[NAPS-UCR-2009-027] address system outside the protected area where there is no plant operating equipment.

4.3.2.4, 4.3.2.4.9 (deleted) Updated description of shutdown margin

[NAPS-UCR-2013-018] (SDM) uncertainty.

Figure 9.3-2 (Sheet 9 of 12) Updated to reflect the removal of both Unit 1

[NAPS-UCR-2013-019] and Unit 2 A Main Steam Sodium Analyzers.

4.5.3.2.4.9 (deleted) Fuel analytical section modified to remove an

[NAPS-UCR-2013-028] outdated reference.

Revision 5209/29/2016 NAPS UFSAR 8 Revision 5009/30/14 (continued)

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

Table 8.3-8 Update added panels to table, which lists

[NAPS-UCR-2012-030] enclosures with more than one field run color-coded cable.

9.2.3.2.1 Reverse Osmosis System updated to reflect

[NAPS-UCR-2012-001] replacement of Reverse Osmosis Water Supply Pump.

Sections 3.1, 3.1.11, 3.1.16, 3.1.17, 3.1.20, Update includes removal of reactor trip on 5.2.2.1, 7.1.3, 7.2.1.1.5, 7.2.1.8, 7.2.2.2.1, steam generator water-low coincident with 7.2.2.2.1.5, 7.2.2.3.5, 7.7.2.1, 10.4.3.3, steam flow/feedwater flow mismatch and 15.2.8.1, 15.4.2.2.1; Tables 7.2-1, 7.2-2, 7.2-4, addition of median signal selection circuitry to 7.2-5, 7.5-1, 7.5-2, 7.5-3; and Figures 7.2-2, the feedwater control system.

7.2-7, 7.7-8, 7.7-11

[NAPS-UCR-2010-005]

Sections 5.1.1.8, 5.5.7.2; and Table 5.5-15 Update reflects the reinstallation of the valve

[NAPS-UCR-2012-034] internals on 1-RC-MOV-1595.

Sections 5.1.3.1, 5.3, 5.5.1.2, 5.5.1.3.1, Update reflects installation of Flowserve 5.5.1.3.5, 5.5.1.3.11; Tables 5.2-3, 5.5-1, 9.3-4; N-9000 seals on 1-RC-P-1A.

and Figure 5.5-1

[NAPS-UCR-2013-009]

Table 6.2-9 Modified to correct exponential term associated

[NAPS-UCR-2013-020] with the tabular mass flow rate data.

Tables 15.4-9, 15.4-10, 15.4-32 Update incorporates the latest assessments

[NAPS-UCR-2013-021] allocated to the peak cladding temperature Analyses of Record for the AREVA realistic large break loss-of-coolant accident analyses and the Westinghouse large break loss-of-coolant accident analyses.

Revision 4909/30/13 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

8.2.1, 8.2.2, Figure 8.2.2 (Sh. 4), Update reflects the replacement of a switchyard Figure 8.2.2 (Sh. 6) transformer.

[NAPS-UCR-2012-037]

Table 9.3-1 Table updated to reflect replacement of the

[NAPS-UCR-2013-006] service air compressor aftercooler.

Revision 5209/29/2016 NAPS UFSAR 9 Revision 4909/30/13 (continued)

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

Table 15.4-19, Figure 15.4-50, Figure 15.4-51, Update reflects revised control rod ejection Figure 15.4-52, Figure 15.4-53 event analysis.

[NAPS-UCR-2013-014]

9.3.4.1, 9.3.4.2.4.24 (new), Table 9.3-5, Update reflects the addition of a Unit 1 zinc Table 9.3-6, Figure 9.3-5 (Sheet 2) injection skid.

[NAPS-UCR-2012-023]

5.2.3.2, 9.3.4.2.4.24 Update reflects that Unit 1 allows zinc

[NAPS-UCR-2012-038] injection.

3.11.3, 9.5.1.1, Figure 9.5-1 Update reflects changes associated with the

[NAPS-UCR-2013-007] underground fire protection piping replacement project.

3.1, 3.1.11.2, 3.1.16.2, 3.1.17.2, 3.1.20.2, Update reflects removal of the Unit 2 reactor 5.2.2.1, 7.1.3.2.3, 7.1.3.3.3, 7.2.1.1.5, 7.2.1.8, trip on steam generator water low coincident 7.2.2.2.1, 7.2.2.2.1.5, 7.2.2.3.5, Table 7.2-1, with steam flow/feedwater flow mismatch.

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]

Table 15.1-2, 15.4.3.1, 15.4.3.2.3, 15.4.3.4, Update reflects reanalyzed steam generator 15.4.3.4.3, 15.4.3.4.4, 15.4.3.4.5, tube rupture event.

Table 15.4-34, Table 15.4-36, Table 15.4-37, Table 15.4-41, Figure 15.4-42

[NAPS-UCR-2012-028]

Table 8.3-8 Table reflects addition of electrical panel for

[NAPS-UCR-2013-008] electrical distribution system cable replacement.

Figure 9.5-6 Figure updated to reflect replacement of the

[NAPS-UCR-2009-028] emergency diesel generator jacket coolant expansion tank, gauge, and alarm switch.

Table 8.3-8 Table updated to reflect alternate power supply

[NAPS-UCR-2012-008] to the spent fuel pool cooling pumps.

[NAPS-UCR-2012-012]

11.3.3.2 Discussion updated to reflect replacement of

[NAPS-UCR-2012-035] the hydrogen analyzer with an oxygen analyzer.

Revision 5209/29/2016 NAPS UFSAR 10 Revision 4909/30/13 (continued)

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

3.7.8 (new section), 3.7 Refs Section added for August 2011 earthquake

[NAPS-UCR-2013-005] discussion on the evaluation and results of analyses that were performed.

LEP, Appendix 3D cover, Table 4.3-6, Effective pages modified to be consistent with Appendix 5A cover, 10.2.1.1 the relocation of Appendices Table of Contents,

[NAPS-UCR-2013-002] corrected FQ value and corrected reference number.

Table 1.3-12, Table 3C-3, 9.2.2.1.2, 9.2.2.2.2, Updated to reflect the removal of the Catalytic 9.2.2.3.2, 9.5.10.2, 9.5.10.3, 11.3.2, Recombiner from the plant.

Table 11.3-1

[NAPS-UCR-2010-015]

6.3.2.1.2.1, 6.3.3.1, 6.3.4.2, Figure 6.3-4 Removed the original LHSI pump performance

[NAPS-UCR-2012-033] curve and added descriptions 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 Removed discussion related to the old Seismic

[NAPS-UCR-2013-001] 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, Seismic discussion updated to reflect seismic 3.7.4.6, References 84 (new), Reference 85 monitoring instrumentation upgrade.

(new), Reference 86 (new), 3A.51, 3A.52

[NAPS-UCR-2012-018]

Table 15.4-32 Table updated to latest assessments allocated to

[NAPS-UCR-2012-032] the peak cladding temperature analyses of record for the AREVA realistic large break loss-of-coolant accident analyses.

3.8.1.1.5 Service Building description modified for

[NAPS-UCR-2012-026] clarification.

12A, 12A.1, 12A.2, 12A.3, 12A.4.1, 12A.4.2, Reactor vessel supplementary neutron 12A.4.3, 12A.4.4, 12A.4.5, 12A.4.6, shielding description updated to reflect Table 12A-6 (new), Table 12A-7 (new), removal of the saddle assembly and Figure 12A-3, Figure 12A-6, Figure 12A-8 replacement of the insulation.

(new)

[NAPS-UCR-2010-029]

Revision 5209/29/2016 NAPS UFSAR 11 Revision 4809/27/12 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

12.3.2 Modified description of health physics facility

[NAPS-UCR-2012-016] to clarify location of the health physics change out area.

3.7.4.1, 3.7.4.2, 3.7.4.5, 3.7.4.6 Seismic discussion updated to reflect seismic

[NAPS-UCR-2012-003] monitoring instrumentation upgrade.

Table 4.4-2y Table modified to correct thermal hydraulic

[NAPS-UCR-2012-019] design parameter.

Table 4.1-2, 4.2.1.1. 4.2.1.1.1, 4.2.1.1.2, Various sections have been updated to reflect 4.2.1.2, 4.2.1.2.1, 4.2.1.2.2, 4.2.1.3.1, 4.2.1.3.2, addition of Westinghouse Robust Fuel 4.2.1.4.2, 4.2.1.4.3, 4.2.2.2, 4.2.3.1.3, 4.2.3.2.1, Assembly 2 (RFA-2) fuel design, Optimized 4.2.3.3.1, 4.2 Refs, Table 4.2-2, Figure 4.2-1, ZIRLO fuel cladding, wet annular burnable Figure 4.2-3x (new), Figure 4.2-7y (new), absorber (WABA) assembly, and integral fuel Figure 4.2-7z (new), Figure 4.2-19, 4.3.1.2, burnable absorber (IFBA). Descriptions of 4.3.1.3, 4.3.1.4, 4.3.2.1, 4.3.2.2.6, 4.3.2.3.1, analyses have been updated on RFA-2 fuel 4.3.2.3.2, 4.3.2.5, 4.3.2.5.4, 4.3.2.5.7, 4.3.2.7, design including transition cycles containing 4.3.3 (deleted), 4.3 Refs, Table 4.3-6 (deleted), AREVA Advanced Mark-BW fuel.

Table 4.3-7 (deleted), Table 4.3-8 (deleted), Descriptions of Low Parasitic fuel (LOPAR)

Table 4.3-9 (deleted), 4.4.1.1, 4.4.1.5, 4.4.2.1, and North Anna Improved fuel (NAIF) have 4.4.2.2.2, 4.4.2.2.6, 4.4.2.3.2.3, 4.4.2.3.4.2, been updated to reflect the safety analyses for 4.4.2.7.2, 4.4.2.8.3, 4.4.2.9, 4.4.2.10.1, these products do NOT support implementation 4.4.2.10.7, 4.4.3.1.1, 4.4.3.1.3, 4.4.3.2.2, of the AECL containment sump strainer or the 4.4.3.4.1, 4.4.3.4.2, 4.4.3.5, 4.4.3.6, 4.4.3.11, measurement uncertainty recapture power 4.4 Refs, Table 4.4-2y (new), Table 4.4-3x uprate and will no longer be used in the reactor (new), Table 4.4-4, 4.5.2.1.2, 4.5.3.3 (deleted), cores.

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]

Revision 5209/29/2016 NAPS UFSAR 12 Revision 4809/27/12 (continued)

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

Table 15.1-2, Table 15.1-3, 15.2.1.2.1, (continued) 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 (Sheet 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, 3ff, 3fg, 3fh, 3ga, 3gb, 3gc, 3gd, 3ge, 3gh, 3ha, 3hb, 3hc, 3hd, 3he, 3hf, 3hg, 3ia, 3ib, 3ic, 3id, 3ie, 3if, 3ig, 3ja, 3jb, 3jc, 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]

Revision 5209/29/2016 NAPS UFSAR 13 Revision 4809/27/12 (continued)

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

Tables 15.4-1, 2, 3, 4 & 5 (deleted), (new) (continued)

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]

Table 6.4-1 Chemical storage table updated to reflect

[NAPS-UCR-2010-020] chemical changes from IONICS to the GE trailers for Reverse Osmosis.

Figure 8.2-1, Figure 8.2-2 (Sheet 5) 230 kV switchyard drawings updated to reflect

[NAPS-UCR-2011-002] the addition of breakers and a variable shunt reactor.

1.2.7, Figure 10.1-1, 10.2, 10.2.1, Turbine generator discussion updated to reflect sections 10.2.1.2 through 10.2.1.6 (deleted), installation of the HP turbine and retrofit of the 10.2.1.7, 10.2.1.8, 10.2 Refs, Tables 10.2-2 LP turbines for Unit 1.

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]

9.2.2.5.1 Reactor coolant pump thermal barrier cooling

[NAPS-UCR-2012-007] coil leak discussion updated to reflect changes to the header trip valves and relief valves.

Table 5.2-25, 11A.1.2 Reactor coolant water chemistry specification

[NAPS-UCR-2012-009] updated to reflect change in pH control agent.

5.1.1.8, 5.5.7.2, Table 5.5-15 Reactor coolant system updated to reflect the

[NAPS-UCR-2012-011] removal of the internals on Unit 1C cold leg loop stop valve.

Table 9.2-4 Service Water System component data

[NAPS-UCR-2012-013] modified to restore units for submergence value.

15.4.1.18 Large break loss-of-coolant accident core

[NAPS-UCR-2012-015] geometry discussion updated to reflect current AREVA grid deformation analysis.

Revision 5209/29/2016 NAPS UFSAR 14 Revision 4809/27/12 (continued)

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

3.8.4.5.4.5 Service water expansion joint discussion

[NAPS-UCR-2012-002] corrected to reflect appropriate unit of measure and revised properties of the rubber expansion joint.

8.3.1.1.1 Emergency diesel generator discussion updated

[NAPS-UCR-2012-004] to reflect replacement of the Woodward governor motor operated potentiometer with a digital reference unit.

Table 6.4.1 Table updated to reflect chemicals stored at the

[NAPS-UCR-2012-005] 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 Seismic discussion updated to record the (new), 2.5 Refs), 3.7.7. 3.7 Refs August 23, 2011 seismic event.

[NAPS-UCR-2012-010]

9.5.3 Lighting System description updated to reflect

[NAPS-UCR-2010-018] use of incandescent lighting in auxiliary and decontamination buildings.

Table 7.2-2, Table 7.5-3 Reactor trip system accuracies and ranges

[NAPS-UCR-2011-016] updated to reflect use of RFA-2 fuel.

9.5.1.1, 9.5.1.2.4.1, 9.5 Refs Fire Protection System updated to reflect

[NAPS-UCR-2010-037] Unit 2 compliance with Regulatory Guide 1.189.

8.2.2, 8.2, Figure 8.2.2 Switchyard description updated to reflect

[NAPS-UCR-2011-012] installation of a passive lightning protection system.

Table 8.3.8 Table updated to include junction boxes

[NAPS-UCR-2010-032] installed that contain two separate color-coded electrical trains.

6.3.2.1.4 Valve description updated to include reverse

[NAPS-UCR-2010-034] flow configuration.

Table 3.9-2, Table 3.11-1 Tables updated to reflect change in type of

[NAPS-UCR-2010-035] valve.

Table 15.4-26 Table updated to latest assessments allocated to

[NAPS-UCR-2011-008] the peak cladding temperature analyses of record for the AREVA realistic large break loss-of-coolant accident analyses.

Revision 5209/29/2016 NAPS UFSAR 15 Revision 4809/27/12 (continued)

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

6.2.4.2 Containment isolation valve design bases

[NAPS-UCR-2011-009] updated to reflect that timing for fast acting valves of the engineered safety features is based on the accident analyses requirements.

8.3.1.1.1 Transformer description updated to reflect

[NAPS-UCR-2011-014] removal of the sudden pressure rise trip.

Revision 4709/29/11 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 6.2-40 Update to Containment Depressurization

[FN 2005-003] System design data reflects replacement of the refueling water refrigeration units.

15.1.4 Update to secondary power calorimetric

[FN 2008-009] measurement reflects installation of Unit 2 ultrasonic flowmeter.

15.1.4 Update to secondary power calorimetric

[FN 2008-013] measurement reflects installation of Unit 1 ultrasonic flowmeter.

10.4.5.2, Figure 10.4-7 Update reflects replacement of Unit 1 Bowser

[FN 2008-032] lubrication oil conditioner.

9.4.8.1 Update reflects modification to the Emergency

[FN 2008-033] Core Cooling System pump room exhaust air cleanup subsystem bypass and filter dampers.

10.2, 10.4.7.2 Update reflects electrical rating and cooling

[NAPS-UCR-2009-009] requirements of the U1 generator.

5.2.5.1 Reference to the ISI Plan modified.

[NAPS-UCR-2011-011]

9.3.2.1.2; Figure 9.3.2 (Sheets 7 of 12, 9 of 12, Updated to reflect steam generator feedwater and12 of 12) chemistry is monitored in the mechanical

[NAPS-UCR-2009-002] equipment room.

6.3.2.1.4.2 Class 152 piping updated with an exception for

[NAPS-UCR-2010-036] valve 2-CC-229.

5.2.4.1.1, 5.2 Refs A discussion about the approved

[NAPS-UCR-2011-001] leak-before-break analysis that eliminates the augmented inspections on the RCS bypass lines was added.

Revision 5209/29/2016 NAPS UFSAR 16 Revision 4709/29/11 (continued)

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

9.2.2.4.2 Description of check valves updated to reflect a

[NAPS-UCR-2011-006] 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, Updated sections to reflect North Anna has 9.1 Refs chosen to comply with the requirements of

[NAPS-UCR-2010-033] 10 CFR 50.68(b) with respect to spent fuel pool criticality prevention.

10.2 Turbine generator discussion updated to reflect

[NAPS-UCR-2009-008] Unit 1 main generator exciter upgrade.

10.4.7.2 Bearing cooling water design flow to the Unit 2

[FN 2006-027] isolated phase bus duct air coolers updated.

1.2.7, 10.2, 10.2.1, 10.2.1.1, 10.2.1.2, 10.2.1.3, Turbine generator discussion updated to reflect 10.2.1.4, 10.2.1.5, 10.2.1.6, 10.2.1.7, 10.2.1.8, installation of the HP turbine and retrofit of the 10.2 Refs, Table 10.2-2, Table 10.2-3, LP turbines for Unit 2.

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]

Table 9.2-4 Service Water pump component data updated

[NAPS-UCR-2009-032] to reflect the modified impellar.

5.5.10.2 ASME Class applicable to U1 and U2 reactor

[NAPS-UCR-2010-030] head and pressurizer vent solenoid operated valves corrected.

9.5.1.2.3, 9.5.1.3.4 Fire protection discussion updated to reflect

[NAPS-UCR-2009-020] replacement of Unit 1 station service transformers rate compensated heat detectors with a linear detector.

6.2.2.2 Inconsistency in the discussion on quench

[NAPS-UCR-2010-038] spray injection into recirculation spray suction was corrected.

3C.2.7.9, Figure 3C-11 Leak detection discussion updated to reflect

[FN 2008-012] Unit 1 leak detection annunciator removed.

Table 3.9-2, Table 3.11-1, Table 5.2-23, Tables updated to reflect valve replacements Table 6.2-47 for MOV/JOG program.

[NAPS-UCR-2010-021]

Revision 5209/29/2016 NAPS UFSAR 17 Revision 4709/29/11 (continued)

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

Table 6.2-52, Table 6.2-53 Tables updated to reflect an increase in the

[NAPS-UCR-2010-024] minimum number of containment temperature detectors.

9.1.4.4.4, 9.1.4.6.1.1 Discussion on the manipulator crane fuel mast

[NAPS-UCR-2010-002] updated to reflect the installation of AREVA in-mast sipping system for Unit 1.

5.5.1.3.12 Reactor coolant pump updated to reflect the

[NAPS-UCR-2010-008] installation of an oil collection assembly on the reactor coolant pump stator motor coolers.

5.1.1.8, 5.5.7.2, Table 5.5-15 Reactor coolant system updated to reflect the

[NAPS-UCR-2010-012] removal of the internals on Unit 2B cold leg loop stop valve.

12.2.5, 12.2 Refs Radiation protection ventilation operating

[NAPS-UCR-2010-017] procedures updated to reflect use of the MSA Model Firehawk M7 SCBA.

5.2.5.4, 5.5.1.2 Reactor coolant pump vibration monitoring

[NAPS-UCR-2010-025] system updated to reflect new proximity probe system.

Revision 4609/30/10 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

3C.2.7.9, Figure 3C-11 Leak detection discussion updated to reflect

[FN 2008-010] Unit 2 leak detection annunciator removed.

Table 6.4-1 Table modified to reflect phased

[NAPS-UCR-2010-023] implementation of new corrosion inhibitor in the Bearing Cooling System.

Table 6.4-1 Table updated to remove chemicals no longer

[NAPS-UCR-2010-022] stored on-site and reflect current use of Dianodic DN2472.

Table of Contents, List of Tables, List of Table of Contents modified to include the Figures for following chapters: 2, 3, 6, 9, 11, Appendices Table of Contents.

12, 14, & 15

[NAPS-UCR-2010-019]

9.5.1.2.3, 9.5.1.3.4 Updated to reflect replacement of Unit 2 station

[FN 2008-029] service transformers rate compensated heat detectors with a linear heat detector.

Revision 5209/29/2016 NAPS UFSAR 18 Revision 4609/30/10 (continued)

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

10.2 Update reflects Unit 2 Main Generator Exciter

[NAPS-UCR-2009-007] upgrade.

3.7.3.2.2.4, 3.7 Refs Deleted reference to Technical Report CE-0076

[NAPS-UCR-2010-016] 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, Update reflects the MUR power uprate to a 4.3.2.2.6, Figure 4.3-22, 4.4.2.1, 4.4.2.1, core thermal output of 2940 MWt (NSSS 4.4 Refs, Table 4.4-2, 4.5.3.2.2.6, Table 4.5-3, power of 2952 MWt).

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, 11.1.1.2, 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]

10.4.5.3, Figure 10.4-7 Update reflects replacement of Unit 2 Bowser

[NAPS-UCR-2009-014] lubrication oil conditioner.

Revision 5209/29/2016 NAPS UFSAR 19 Revision 4609/30/10 (continued)

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

6.2.1.3.2.6, Table 6.3-8 Update reflects installation of permanent loop

[NAPS-UCR-2009-026] room scaffold.

5.4.2 Update adds a description of the canopy seal

[NAPS-UCR-2010-014] clamp assembly added to spare CRDM nozzle penetration.

9.1.4.4.4, 9.1.4.6.1.1 The Unit 2 manipulator crane fuel mast

[NAPS-UCR-2009-024] discussion was updated to include the installation of the AREVA in-mast sipping system.

3.3.2 Modified description for tornado-resistant

[NAPS-UCR-2010-003] structures to include both types of doors as originally installed.

Table 1.5-1, Table 1.5-2, Figure 1.5-1, Labeled tables and figures associated with Figure 1.5-2, 1.6, 4.5.3.1.1, 4.5.3.1.2, 4.5.3.1.3, original design testing as historical. Changed 4.5.3.1.4, 4.5.3.1.5, 4.5.3.1.6, 4.5.3.1.7, title for WCAPs to general references. Clarified 4.5.3.2.2, 4.5.3.2.2.1, 4.5.3.2.2.2, 4.5.3.2.2.3, various sections to indicate they are applicable 4.5.3.2.2.4, 4.5.3.2.2.7, 4.5.3.2.2.8, 4.5.3.2.2.9, to Advanced Mark-BW fuel. Corrected 4.5.3.2.3, 4.5.3.2.3.1, 4.5.3.2.3.2, 4.5.3.2.3.3, typographical errors and clarified location 4.5.3.2.3.4, 4.5.3.2.3.5, 4.5.3.2.4, 4.5.3.2.4.1, terminology.

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]

9.5.1.2.2.1, 9.5.1.2.2.2, 9.5.1.2.3, 9.5.4.2 The fire detection computer system description

[FN 2008-035] was updated to reflect the new system installed for the Fire Detection System Replacement Project.

9.3.3.2 Description of the Unit 1 air handling room

[NAPS-UCR-2009-018] floor drains was updated to reflect the removal of the backflow preventers.

Revision 5209/29/2016 NAPS UFSAR 20 Revision 4609/30/10 (continued)

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

3.8.2.2 Containment air partial pressure and maximum

[NAPS-UCR-2009-036] containment bulk air temperature discussion was modified to reflect current technical specification limits.

4.5.3.2.2.6.2, 4.5.4.2.2.6, 4.5 Refs, Table 4.5-3 The linear heat rate to fuel melt for AREVA

[NAPS-UCR-2010-004] fuel was updated to reflect code error correction.

6.3.3.12 A discussion on containment pressure

[NAPS-UCR-2010-011] information was modified to note it is historical.

Table 3C-2 Updated the high-energy steam generator

[NAPS-UCR-2010-001] blowdown lines.

4.3.2.7, 4.5.3.2.7 Text updated to reflect that the spent fuel pool

[NAPS-UCR-2009-037] 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 Text updated to reflect auxiliary building

[NAPS-UCR-2009-033] 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, Revised description to reflect removal of 9.2.1.2.4.2 expansion joints from Service Water tie-in

[NAPS-UCR-2009-013] vault and valve house. Allowable settlement value revised to reflect pipe stress and pipe support analyses.

Table 9.2-4 Service Water pump data updated to reflect

[NAPS-UCR-2009-031] change in impeller.

9.5.1.2.3 Updates the table of containment heat detector

[NAPS-UCR-2009-034] setpoints to reflect new heat detectors in Unit 1.

2.3.4.3 Updates the Meteorological Information Dose

[NAPS-UCR-2009-035] Assessment System information and how the plant computer processes that data.

Figure 8.2-1 Revised figures to reflect replacement of

[FN 2007-027] switchyard transformers.

Table 11.2-1 Liquid Waste Disposal Equipment Design

[FN 2007-036] Table updated to reflect removal of powdered resin recirculation pump powdered resin holdup tank and water return pump.

Revision 5209/29/2016 NAPS UFSAR 21 Revision 4609/30/10 (continued)

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

11.4.2.1, Table 11.4-1 Updated to incorporate replacement of letdown

[FN 2007-034] radiation monitors with new GM tube monitors.

7.1.4, 7.1 Refs Updated to incorporate TRM Section 3.3.9 as a

[FN 2008-008] new reference for RG 1.97 instrument functionality, reportability, and alternate indications.

3.8.2.1.4.1 Clarified components that qualify as secondary

[NAPS-UCR-2009-004] overload protection associated with Unit 2 containment electrical penetrations.

18.3.5.6 Updated discussion on reactor coolant pump

[NAPS-UCR-2009-019] and ASME code case N-481.

Table 15.3-24, Table 15.4-26 Incorporated the latest assessments allocated to

[NAPS-UCR-2009-025] the peak cladding temperature analysis of record for the AREVA small break loss-of-coolant accident and AREVA realistic large break loss-of-coolant accident analyses.

Revision 4509/30/09 Changes Made under the provisions of 10 CFR 50.59 Section except where indicated in brackets.

KWI Removes the key word index.

[NAPS-UCR-2009-023]

11.2.2.2 Reflects replacement of the ion exchange

[FN 2008-002] filtration system.

6.4.1.1, 6.4.1.2, 6.4.1.3, 6.4.1.3.1, 6.4.1.4, Incorporates technical specification change to 6.4.1.5, 7.7.1.12.1, 9.4.1.1, 9.4.1.2, 9.4.1.3, remove requirements for the control room 9.4.1.5, Table 9.4-2, 12.1.2.10, 15.4.1.7, bottled air system.

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]

11.4.2, 11.4.2.15 Corrected description of the reactor coolant

[NAPS-UCR-2009-021] letdown radiation detection equipment.

6.2.2.2, 6.3.2.1.6 Reflects the installation of the seal closure

[FN 2008-026] frames on the containment sump strainer for Unit 1.

Revision 5209/29/2016 NAPS UFSAR 22 Revision 4509/30/09 (continued)

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

9.3.2.1.2, 9.3.2.1.3, Figure 9.3-2 (Sheets 7, 9, Reflects modification os online chemistry

&12) monitoring system for Unit 1 steam generator

[FN 2008-039] feedwater chemistry.

9.2.2.3.1 Changed the pH range for the chromated

[NAPS-UCR-2009-010] component cooling water.

12.3.3 Added Effective Dose Equivalent to the types

[NAPS-UCR-2009-012] of exposure that are determined by Thermoluminescent Dosimetry badges.

9.5.2.1.3 Corrected location of the communications

[NAPS-UCR-2009-015] tower.

Figure 10.1-1, Table 10.4-2 Updated the design information for the 6th

[FN 2008-004] point feedwater heaters.

5.2.5.4 Replaced the reactor coolant pump vibration

[FN 2007-032] monitoring system.

Figure 8.2-2 Updated figure to reflect modifications made to

[FN 2008-015] the switchyard buses.

7.7.2.6 Corrected section on safety injection actuation

[NAPS-UCR-2009-006] input logic to align it with actual signal inputs for low pressurizer pressure.

9.6.1, 9.6.5, 9.6 Refs Updated Heavy Loads discussion to include

[FN 2008-036] reactor vessel head drop analysis.

8.2.2 Clarifies the backup sources of power to the

[FN 2006-007] battery charger for the dc system in the 230kV Control House in the Switchyard.

9.5.1.2.3 An interim update of setpoints of the Unit 2

[FN 2007-009] containment heat detectors installed under the Fire Detection Replacement Project. Relocated setpoints from note to list of detectors.

Figure 10.1-2, Table 10.4-2 Updates design information for the Unit 2 sixth

[FN 2007-028] point feedwater heaters and Unit 2 power heat balance figure.

Figure 6.2-38 Corrects snubber figure to be consistent with

[FN 2008-034] plant configuration.

Table 10.4-4, Table 15.1-2, Table 15.4-35 Corrects tables to be consistent with the

[NAPS-UCR-2009-001] accident analysis of record calculations.

Revision 5209/29/2016 NAPS UFSAR 23 Revision 4509/30/09 (continued)

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

10.2, 10.4.7.2 Updated electrical ratings and cooling water

[FN 2008-005] requirements of the U2 generator. Corrected the U1 generator rating.

6.2.2.2, 6.3.2.1.6 Added description of the containment sump

[FN 2008-017] strainer seal frames.

18.2.1, 18.2.11, Table 18-1 Revised to indicate closure of license renewal

[FN 2008-021] commitments 2 (addition of inspection of pressurizer surge 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, Designated original plant shielding zone Figure 12.1.2, Figure 12.1.3, Figure 12.1.4, criteria as historical.

Figure 12.1.5

[FN 2008-031]

18.5 Refs. Updated references associated with the Steam

[FN 2008-037] Generator Program.

6.2.2.2, 6.2.2.3, 6.2.2.4, 6.2.2.5, 6.2.2.6, Updated various sections to reflect compliance 6.2.3.1.1, 6.2 Refs, Table 6.2-38, Table 6.2-39, with GSI-191 for the strainer assembly.

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]

Table 15.1-3,15.2.7.2.2, Table 15.2-1, Updated the loss of load event figures and Figure 15.2-19, Figure 15.2-20, tables to reflect current analysis of record.

Figure 15.2-21, Figure 15.2-22, Changed the safety analysis limit on High Figure 15.2-23, Figure 15.2-24, Pressurizer Pressure.

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]

2.1.3, Figure 2.1-4, Figure 2.1-5, Figure 2.1-6, Designated section on Population and Figure 2.1-7, Figure 2.1-8, Figure 2.1-9, associated figures as historical.

Figure 2.1-10, Figure 2.1-11, Figure 2.1-12, Figure 2.1-13, Figure 2.1-14

[FN 2008-020]

Revision 5209/29/2016 NAPS UFSAR 24 Revision 4509/30/09 (continued)

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

Table 5.2-25, 11A.1.2 Increased RCS pH (300C) from the current

[FN 2008-022] 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 Incorporated the new spent filter cask spreader

[FN 2008-024] beams and new filter casks.

Table 6.4-1 Updated quantity of chemicals stored on site

[FN 2008-027] and in the warehouse to reflect current system configuration.

KWI, 13.3, 13.3 Refs Reflects use of emergency action levels in

[FN 2008-028] accordance with NEI 99-01, Rev.4.

Revision 4409/30/08 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

8.3.1.1.1, 9.5.1.2.3 Corrected a note for the temperature detecting

[FN 2008-016] sensors and added additional temperature-detecting sensor setpoints.

Clarified the discussion on Unit 1 main generator breaker.

6.3.2.2.5 Updates the description of the limiting LHSI

[FN 2008-019] pump NPSHa case.

5.5.1.3.11 Amends the discussion on RCP seal-water

[FN 2008-014] injection filter size.

Figure 1.2-2, 9.2.3.2.1 Reflects changes to the reverse osmosis system

[FN 2007-002] and removal of the domestic water tank.

9.4.4.5 Changes the method of controlling the Turbine

[FN 2007-022] Building ventilation supply dampers from auto to manual.

15.3.1.13, 15.3 Refs, Table 15.3-24, 15.4.1.18, Incorporates the latest assessments allocated to 15.4 Refs, Table 15.4-27 the peak clad temperature analysis of record for

[FN 2008-011] the AREVA small break LOCA and large break LOCA.

Revision 5209/29/2016 NAPS UFSAR 25 Revision 4409/30/08 (continued)

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

2.4.3.4, Figure 2.4-3, Figure 2.4-6, Corrects the radial gate description regarding Figure 2.4-8, 2.A.2.3.1, Figure 2A-2, the maximum radial gate opening at the Figure 2A-8 spillway.

[FN 2005-046]

Table 9.5-1 Incorporates changes associated with fire

[FN 2006-021] protection system upgrade.

9.5.1.2.2.1 Corrects the CO2 system description to reflect

[FN 2007-021] that the total flooding extinguishment is provided by one-shot.

15A.3.1 Updates the site boundary dose for postulated

[FN 2008-006] cask drop accidents.

3.8.2.1.4.2, Figure 3.8-11, 9.2.2.1.1, 9.2.2.3.1 Updated the description of the hot pipe

[FN 2007-017] containment penetration coolers (Unit 1) 12.3.1, 13.4 Incorporates changes in titles to the Quality

[FN 2007-024] Assurance Program Description (QAPD) and Facility Safety Review Committee (FSRC).

3.8.2.7.6.3, Table 3.8-10, Table 3.8-11, Added discussion of GSI-191 coatings review Table 3.8-19, Table 3.8-20, Table 3.8-21 and qualified and unqualified coating tables.

[FN 2007-033]

Figure 8.2-1 Revised figure to reflect new type of

[FN 2008-003] disconnect for H204M.

9.5.9.2 Added description of vacuum drying system

[FN 2005-045] that facilitates the dry shielded canister in the decontamination facility.

3.8.2.7.6.1.1 Added description for restoration of

[FN 2007-026] recirculation spray sump trench floor.

Revision 5209/29/2016 NAPS UFSAR 26 Revision 4409/30/08 (continued)

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

KWI, 6.1, 6.2.1.1.1, 6.2.1.1.1.1, 6.2.1.1.1.2, Performed containment analyses and LOCA 6.2.1.1.1.3, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.1.3.1.2, alternate source term analyses to support 6.2.1.3.1.2.1, 6.2.1.3.1.2.2, 6.2.1.3.1.3, 6.2.2.1, GSI-191 modifications Unit 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, 6.2-11, 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, 6.3-11, 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]

6.2.1.3.2.3, 6.2.2.2, 6.2.2.3.2.2, 12.1.2.1, Added the Unit 1 incore sump room drain to Table 12.1-2, Figure 12.1-8 support GSI-191 containment sump

[FN 2006-020] modifications.

Table 3.2-1, Figure 6.1-1, 6.2.2.2, 6.2.2.3, Completed partial installation of Unit 1 6.2.2.4.3, 6.2.2.4.4, 6.2.3.3, 6.2 Refs, containment sump strainers to support GSI 191 Table 6.2-38, Table 6.2-40, Figure 6.2-55, modifications.

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]

6.2.2.2, 6.2.2.3.2.1, 6.2.3.1.1, Table 6.2-2, Incorporates reduction in the minimum IRS Table 6.2-12, Figures 6.2-63, 64, 65, 66, 67, 68, and OSR safety analysis pump flow rates and 69, 70, 71, 72, & 73, Figures 6.3-7, 8, 9, & 10, updates the LOCA alternate source term Table 15.4-7 analysis.

[FN 2007-020]

Revision 5209/29/2016 NAPS UFSAR 27 Revision 4409/30/08 (continued)

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

9.1.4.9, 9.1.4.9.1, 9.1.4.9.2, 9B.2, 15A.1, Replaces detailed information about cask 15A.2, 15A.3.1 loading and unloading with references to the

[FN 2007-029] 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, Editorial changes; Clarifies final markups for Table 6.2-41, 15.4.1.8.7, 15.4.5.2, Table 15.4-7, GSI-191 multiple packages.

Table 15.4-14

[FN 2008-001]

9.5.1.2.2.2 Replaced ionization type smoke detectors with

[FN 2007-012] Photoelectric type detectors.

7.3.1.3.2, 7.3.1.3.2.2, 7.3.1.3.3.2, 7.3.2.11, Updated the description of the RWST level-low Table 7.3-2 engineered safety features actuation system

[FN 2007-016] (ESFAS) function to include Unit 1 GSI-191 modification.

Figures 8.2-1 & 8.2-2 Switchyard figures were modified to reflect the

[FN 2006-015] upgrade on buses 3, 4, and 5 in the switchyard.

Table 5.2-22 Updated the description of the steam generator

[FN 2007-025] secondary side closure bolting material.

6.2.1.2.20 Provided for use and storage of a manbasket

[FN 2007-018] inside the containment.

7.2.1, 7.2.1.2, 7.2.2.2.1.7, 7.2 Refs, 15.1.3 Updated the description of reactor trip system

[FN 2007-010] response time testing and verification.

9.5.2.2.4 Corrected the description of the emergency

[FN 2007-006] notification system.

10.2 Modified the turbine overspeed protection

[FN 2007-004] control circuitry.

15.4.1.5.3, Table 15.4-5 Incorporated the peak clad temperature

[FN 2007-014] penalties and benefits for the large break LOCA. [10 CFR 50.46]

18.2.11, 18.2.13, 18.2.15 Clarified the description of developing and

[FN 2007-023] submitting the Inservice Inspection Plan.

Revision 5209/29/2016 NAPS UFSAR 28 Revision 4309/27/07 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 6.1, 6.2.1.1.1, 6.2.1.1.1.1, 6.2.1.1.1.2, Performed containment analyses and LOCA 6.2.1.1.1.3, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.1.3.1.2, alternate source term analyses to support 6.2.1.3.1.2.1, 6.2.1.3.1.2.2, 6.2.1.3.1.3, 6.2.2.1, GSI 191 modifications.

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, 6.2-11, 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, 6.3-11, 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]

Table 3.2-1, 4.1, Figure 6.1-1, 6.2.2.2, 6.2.2.3, Completed partial installation of Unit 2 6.2.2.4.3, 6.2.2.4.4, 6.2.3.3, 6.2 Refs, containment sump strainers to support GSI 191 Tables 6.2-40 & 6.2-42, Figures 6.2-57, 6.2-58, modifications.

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]

3.8.2.1.4.2, 3.8.2.1.4.5 Increased the temperature limitation for

[FN 2006-028] containment penetrations from 150°F to 200°F.

3.8.2.1.4.2, Figures 3.8-11 & 3.8-15 Removed the outside cooler on hot pipe

[FN 2007-001] containment penetrations (except installed spares).

3.8.2.1.4.2, Figures 3.8-11, & 3.8-15, 9.2.2.1.1, Updated the description of the hot pipe 9.2.2.3.1 containment penetration coolers.

[FN 2007-003]

Revision 5209/29/2016 NAPS UFSAR 29 Revision 4309/27/07 (continued)

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

4.1, 4.4.1.6, 4.5.2.1.2, 4.5.3.2.1, 4.5.4.1.6, Updated the reconstitution methodology for 4.5 Refs, Tables 4.5-1, 4.5-2, 4.5-3, 15.4.1.9, AREVA Advanced Mark-BW fuel.

15.4 Refs

[FN 2005-043]

Table 4.1-2, 4.5.4.1.1, 4.5.4.1.5, 4.5.4.2.1, Incorporated use of the VIPRE-D/BWU 4.5.4.2.3.1, 4.5.4.2.3.4.2, 4.5.4.2.3.4.3, computer code to perform thermal-hydraulic 4.5.4.2.5, 4.5.4.2.6, 4.5.4.2.8.1, 4.5.4.2.8.3, evaluations of AREVA Advanced Mark-BW 4.5.4.2.10.4, 4.5.4.2.10.5, 4.5.4.3.1.3, fuel. [10 CFR 50.90 License Amendment]

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]

Table 5.2-22 Updated the description of the pressurizer

[FN 2006-031] closure bolting material.

6.2.1.3.2.3, 6.2.2.2, 6.2.2.3.2.6, 12.1.2.1, Added the Unit 2 incore sump room drain to Table 12.1-2, Figure 12.1-8 support GSI 191 containment sump

[FN 2006-011] modifications.

6.2.2.2 Corrected the description of debris generation

[FN 2007-007] 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, Modified the Unit 2 refueling water storage Table 7.3-2 tank engineered safety features actuation

[FN 2006-035] 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, Modified the terminology associated with 9.3.1.2, 9.3.2.1.3, 9.3.2.2.3, 9.3.4.2.1, 9.3.4.3.1, determinations of operability and functionality 9.5.1.2.3, 9.5.1.3.4, 9.5.1.4.2, 9.5.1.6, 9.5.1.6.1, in accordance with Regulatory Issue 9.5.1.6.2, 9.5.2.1.1, 9.5.6.2, 10.3.4, 10.4.1.4, Summary 2005-20.

10.4.7.4, 11.4.5, 12.1.4.1

[FN 2007-011]

9.2.1.2.2 Reduced the frequency of monitoring the

[FN 2006-013] service water reservoir sludge depth from annually to once per five years.

9.2.2.5.1 Clarified the description of system operation

[FN 2007-015] following a reactor coolant pump thermal barrier coil leak.

Table 9.2-4 Replaced auxiliary service water pump,

[FN 2006-032] 1-SW-P-4.

Revision 5209/29/2016 NAPS UFSAR 30 Revision 4309/27/07 (continued)

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

9.5.1.2.2.2, 9.5.1.2.3 Replaced heat and smoke detectors in the

[FN 2006-009] Training Center records vault.

15.3.1.6, 15.3 Refs, Table 15.3-4 Incorporated the peak clad temperature

[FN 2007-013] 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, Incorporated the peak clad temperature 15.4 Refs, Table 15.4-26 penalties and benefits for the Westinghouse

[FN 2006-022] SBLOCA and AREVA RLBLOCA.

[10 CFR 50.46]

15.4.2.1.3.2, 15.4.3.4.2, 15.4.4.3.2 Revised the description of steam generator

[FN 2005-047] leakage. [10 CFR 50.90 License Amendment]

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

[FN 2006-033] Commitment Item Nos. 16, 18, and 28.

Revision 5209/29/2016 NAPS UFSAR 31 Revision 4209/29/06 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 1.2.9, 2.1.3.4, 2.3.4.1, 2.3.4.2, Implemented an alternate source term from Table 2.3-18, 3.1.15.1, 3.1.15.2, 3.6.1, 3.7.3.2, NUREG-1465 as the design basis source term.

6.2.1.3.1, 6.2.2.1, 6.2.3.1, 6.2.3.1.1, 6.2.3.2, [10 CFR 50.90 License Amendment]

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 & FN 2004-021]

3.8.2.1.4.2, Figures 3.8-11 & 3.8-15 Isolated ten Unit 2 containment penetrations

[FN 2005-038 & FN 2005-042] 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 Isolated ten Unit 1 containment penetrations

[FN 2006-002] outer cooler component cooling supply and return by seal plate or plug.

Table 3F-8 Revised the emergency diesel generator rooms

[FN 2006-025] maximum temperature.

4.4.3.2.1, 4.4 Refs, 4.5.4.2.2.6 Provided a generic formula for nuclear N

[FN 2006-005] enthalpy rise hot channel factor, F H , and referred to the Core operating Limits Report for N

current values of F H and the total heat flux hot-channel factor, FQ.

Revision 5209/29/2016 NAPS UFSAR 32 Revision 4209/29/06 (continued)

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

4.5.3.2.2.6.4 Modified the discussion of Unit 1 peaking

[FN 2005-018] factor uncertainty.

4.5.3.2.2.6.4 Modified the discussion of Unit 2 peaking

[FN 2005-019] factor uncertainty.

Table 4.5-3 Reflected the increase in core pressure drop

[FN 2006-008] due to use of the Advanced Mark-BW one-quarter turn quick disconnect top nozzle.

Tables 5.1-1 & 5.5-17 Corrected the description of pressurizer spray

[FN 2006-023] flow rate.

5.2.2.2, 5.2 Refs, Tables 5.2-20 and 5.2-21, Revised the reactor coolant system 5.4.1.2, 5.4 Refs pressure-temperature limits, LTOPS setpoints,

[FN 2003-053] LTOPS Tenable 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, Updated the surveillance capsule withdrawal Tables 5.4-2 & 5.4-3 schedules to incorporate the renewed operating

[FN 2005-005 & FN 2005-041] licenses for both units. [10 CFR 50, Appendix H]

5.2 Refs, 18.2.12 Removed specific interval and ASME XI

[FN 2005-037] edition and addenda references to allow required periodic update.

Table 5.2-3 Clarified that the narrow range RTD

[FN 2006-003] 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 Updated the description of the design code for

[FN 2004-041 & FN 2004-043] the RWST cooling subsystem.

6.2.2.3 Clarified the description of the layup condition

[FN 2005-021] of the recirculation spray heat exchangers.

6.4.1.3, 7.7.1.13, 9.4.1.3 Installed Unit 1 and Unit 2 carbon dioxide

[FN 2006-019] monitors in the control rooms.

8.1.1, 8.2.2, Figures 8.2-1 & 8.2-2 Replaced feeder cables to reserve station

[FN 2005-030] service transformers A, B, & C, and installed an additional 500 kVA transformer.

8.2.3.1, Figure 8.2-1 Relocated and replaced switchyard breakers.

[FN 2005-048]

Revision 5209/29/2016 NAPS UFSAR 33 Revision 4209/29/06 (continued)

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

Figure 8.2-1, 8.3.1.1.2.3, 8.3.1.2.1, 8.3.1.2.2.4, Replaced vital bus inverters 2-III & 2-IV and Table 8.3-8 added an additional bypass transformer.

[FN 2005-011]

Figure 8.2-1, 8.3.1.1.2.3, 8.3.1.2.1, 8.3.1.2.2.4, Replaced vital bus inverters 1-III & 1-IV and Table 8.3-8 added a new bypass switch.

[FN 2005-031]

9.1.3.1, 9.1.3.3.1, Table 9.1-2 Provided for offload of fuel from the reactor

[FN 2005-028] vessel to the spent fuel pool as early as 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown.

Figure 9.1-8 Removed an electrical cable reel from the fuel

[FN 2005-016] handling bridge crane.

9.2.3.1, Table 9.2-10 Replaced domestic water Well No. 3 with Well

[FN 2003-048] No. 7.

9.3.3.2, 10.4.2.3 Installed backflow preventers in the floor

[FN 2006-017] drains of the Unit 1 & 2 air conditioning rooms.

Table 9.3-2, 10.4.7.2, Table 10.4-2 Increased the design flow for the Unit 1

[FN 2006-001] isolated phase bus duct air coolers and abandoned in place certain flash evaporator system components.

Tables 9.3-2 & 10.4-2 Corrected the description of Unit 1 flash

[FN 2006-024] evaporator system components previously abandoned in place.

Table 9.3-7 Corrected the description of boron recovery

[FN 2006-004] system equipment.

9.4.6.3 Updated the description of the safeguards

[FN 2005-036] supply fans noting that the high speed function is disabled.

9.4.9.3 Updated the description of containment

[FN 2004-050] isolation during refueling to include the hi-hi radiation signal from the manipulator crane radiation monitor.

9.5.1.2.3, 9.5.1.3.4 Replaced the heat detectors on the Unit 2 main

[FN 2005-017] transformers.

10.2, 10.2.1.1.2, 10.2 Refs Reduced the frequency of main turbine and

[FN 2006-014] governor valves surveillance testing from once per three months to once every six months.

Revision 5209/29/2016 NAPS UFSAR 34 Revision 4209/29/06 (continued)

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

10.3.1 Clarified the description of the steam generator

[FN 2005-034] PORVs design function and control cables.

10.4.2.3 Reanalyzed the maximum flooding elevation of

[FN 2005-035] the Turbine Building due to a failure of a condenser outlet expansion joint.

10.4.7.1 Replaced the bearing cooling tower chemical

[FN 2005-013] addition system.

11.4.2.1, 12.1.4.1 Updated the description of radiation monitor

[FN 2005-026] recorders.

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

[QA 2004-002 & FN 2004-017] description of and reference to the recently implemented Topical Report DOM-QA-1. The Dominion Nuclear Facility Quality Assurance Program Description is based on ANSI/ASME NQA-1-1994 and will be maintained as a separate, single document for Dominion facilities.

[10 CFR 50.54(a)]

Revision 4109/30/05 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

2.4.11.1, 2.4.11.2, 2.4.11.3, 2.4.11.5, 2.4.11.6, Corrected the extreme low water level value 2.4.14, Table 2.4-6 and clarified its basis. Provided revised values

[FN 2004-002] for the auxiliary service water pumps and the reverse osmosis water pumps minimum operating level, required submergence, and actual submergence.

3.1.37.2, 3.11.2.5, Table 3.11-2, 3A.7, 6.1, Incorporated license amendments on 6.2.5.1, 6.2.5.2, 6.2.5.3, 6.2 Refs, Table 6.2-55 elimination of requirements for hydrogen

& 6.2-62, Figures 6.2-91, 6.2-92, 6.2-96, recombiners and hydrogen monitors using the 6.2-97, 6.2-98, & 6.2-99 Consolidated Line Item Improvement Process.

[FN 2005-004] [10 CFR 50.44]

Table 3.5-5, 9.2.3.2.1 Reflected the removal of the use of hydrogen,

[FN 2005-022] the hydrogen storage facility, and the de-oxygenation trailer for the reverse osmosis system.

Revision 5209/29/2016 NAPS UFSAR 35 Revision 4109/30/05 (continued)

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

3.8.1.4.7, 3.8 Refs Provided clarification to the description of

[FN 2004-042] masonry block walls.

4.4.2.3.4.2, 4.4 Refs, 4.5.3.2.2.6.4 Described the overall peaking factor

[FN 2004-045] uncertainty associated with the Framatome ANP Advanced Mark BW fuel product.

[10 CFR 50.90 License Amendment]

5.2 Updated the code description of the pressurizer

[FN 2005-024] safety valves.

5.2.5, 5.2.5.1, 7.3.1.2, Tables 15.4-16, 15.4-23, Incorporated editorial corrections to improve

& 15.4-26 readability, corrected spelling, and incorporated

[FN 2005-006] changes omitted from previously implemented UFSAR changes.

5.5.10.4, 6.2.2.4.2, Table 6.3-1 Changed the ASME Code reference for

[FN 2004-049] 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, Revised the safety analysis flow rate for 6.3.4.4 maximum low head safety injection

[FN 2004-018] recirculation mode flow rate for the LHSI pump net positive suction head analysis.

6.3.2.1.4.2 Allowed that check valves 1-CH-240 and

[FN 2005-027] 2-CH-155 can be fitted with or without a spring.

6.4.1.2, Tables 11.4-1 & 12.1-4 Reflected consistent mark number format for

[FN 2005-033] the radiation monitoring system.

6.4.1.3.3, Table 6.4-1 Updated the concentration of ethanolamine up

[FN 2004-031] to 85%.

Tables 7.2-2, 7.5-1, 7.5-2, & 7.5-3 Updated the indicated accuracy for the

[FN 2004-040] 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 Updated the indicated accuracy for the steam

[FN 2005-001] generator water level.

Tables 7.2-2 & 7.5-3 Updated the indicated accuracy for

[FN 2005-002] overtemperature T and overpower T.

Revision 5209/29/2016 NAPS UFSAR 36 Revision 4109/30/05 (continued)

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

7.3.1.3.5, 8.3.1.1.2.3, Table 8.3-8, 9.2.1.1, Modified the Unit 1 service water spray array 9.2.1.2.2, 9.2.1.2.5 motor-operated valve safety injection signal

[FN 2003-012] actuation cross-tie.

Table 7.5-2 Updated the indicated accuracy for the

[FN 2005-014] refueling water storage tank water level.

8.3.1.1.1, Table 8.3-1, Figures 8.2-1 & 8.2-2 Removed the 34.5-kV shunt reactor banks from

[FN 2001-040] the switchyard.

9.1.4.4.5, Figures 9.1-8 & 9.1-12 Modified the fuel handling bridge crane

[FN 2004-019 & FN 2005-007] controls with a programmable logic controller and adjustable speed drives.

9.2.1.1 Incorporated editorial changes to

[FN 2005-020] cross-reference and be consistent with the Section 9.2.1.2.5 description of service water pump auto start.

9.2.1.6 Provided for the continued use of corrosion rate

[FN 2002-024] test specimens instead of the probe monitoring system in the service water system.

Table 9.2-10 Incorporated Well No. 6 into the domestic

[FN 2004-033] water supply component design data.

9.3.2.1.2, 9.3.2.1.5, Figure 9.3-2 Corrected the description of the sampling

[FN 2005-025] system.

9.5.1.1, 9.5.1.2.1, Figure 9.5-1, Table 10.4-6 Replaced the cooling tower for the Bearing

[FN 2004-044] Cooling System.

9.5.1.2.3 Replaced the heat detectors on the Unit 1 main

[FN 2004-013] transformers.

9.5.1.6.2 Reduced the time allowed to establish a backup

[FN 2005-015] 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 Replaced the 2J emergency diesel generator

[FN 2004-046] lube oil and jacket coolant temperature switches with a temperature converter system.

10.4.3, 15.4.1.5.1 Incorporated editorial spelling correction and

[FN 2004-047] corrected typographical error in reference document number.

Table 11.4-2 Updated the isotopic response factors for Kr-85

[FN 2005-008] and Xe-133 for the condenser air ejector radiation monitors.

Revision 5209/29/2016 NAPS UFSAR 37 Revision 4109/30/05 (continued)

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

15.1 Refs, 15.2 Refs, 15.3 Refs, 15.4 Refs Updated the RETRAN Topical Report

[FN 2004-038] references.

15.3.1,8, 15.3.1.13, 15.3 Refs, Table 15.3-24 Incorporated the peak clad temperature

[FN 2005-009] 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 Reflected the completion of License Renewal

[FN 2004-048] Commitment Item Nos. 3, 4, 5, 7, 8, 15, and 29.

Revision 4009/30/04 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

Table 2.4-6 Provided revised values for bearing lubricating

[FN 2002-047] water pump 1-BL-P-1B minimum operating level, required submergence, and actual submergence.

Table 2.4-6 Modified the minimum operating level and

[FN 2003-027] actual submergence of one safety-related circulating water screen wash pump.

Table 2.4-6 Provided revised (1-BL-P-1A) and corrected

[FN 2003-044] (1-BL-P-1B) values for 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 Replaced metal expansion joints with rubber

[FN 2003-011] 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 Deleted the description of pressure balanced

[FN 2004-011] 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 Clarified non-destructive test personnel

[FN 2000-011] compliance with Regulatory Guide 1.58.

Revision 5209/29/2016 NAPS UFSAR 38 Revision 4009/30/04 (continued)

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

3C.1.1, 3C.2.7, 3C.2.7.9, 3C.5.1.2.2, Replaced the main steam and feedwater line 3C.5.1.8.2, 3C.5.2.2.2, 3C.5.2.8.2, Table 3C-1 leak detection system function with daily

[FN 2003-051] operator inspections in the mechanical equipment rooms.

Table 3C-3, 8.3.1.1.2.3, Table 8.3-8 Incorporated editorial corrections to vital bus

[FN 2004-027] panel board mark numbers.

4.1, 4.1 Refs, Table 4.1-2, 4.5 All, 5.1.2.1.2, Added the description of the Framatome ANP 6.3.3.12, 6.3.3.13, 6.3 Refs, 7.2.1, 11A.1.1, Advanced Mark BW fuel product.

11A Refs, 15, 15.1.2.2, 15.1.9.7, 15.1 Refs, [10 CFR 50.90 License Amendment]

Tables 15.1-2 & 15.1-3, 15.3.1, 15.3.1.8, 15.3.1.9, 15.3.1.10, 15.3.1.11, 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, 15.4.1.11, 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, FN 2004-008, FN 2004-025 &

FN 2004-036]

Table 4.1-2, 4.3.2.2.6, 4.3.2.3.1, 4.3.3, 4.3.4, Added the description of the Studsvik Core 4.3.4.1, 4.3.4.2, 4.3.4.2.1, 4.3.4.3, 4.3 Refs, Management System computational model for Tables 4.3-6 & 4.3-10, 15.1 Refs, 15.3 Refs reactor physics analyses.

[FN 2003-035]

4.2.1.4.2, 4.2.3.4.1 Updated the feed fuel and burnable poison rod

[FN 2004-035] vendor specifications to no longer require ultrasonic or x-ray testing on these components.

Tables 5.1-1 & 5.5-17 Corrected the description of pressurizer spray

[FN 2004-009] flow rate.

Revision 5209/29/2016 NAPS UFSAR 39 Revision 4009/30/04 (continued)

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

5.2.3.4 Corrected typographical and grammatical

[FN 2004-004] errors.

Table 5.2-22, 18.2.3 Corrected the description of reactor lower head

[FN 2004-001] instrumentation material. Clarified criteria for maintenance and corrective action due to evidence of borated water leakage.

Tables 5.2-22 Provided for another type of material for

[FN 2004-020] pressurizer safety valve forgings.

5.5.1.3.11 Incorporated a filter size range for the reactor

[FN 2003-040] coolant pump shaft seal-water injection filters.

6.2.1.2.19, Table 6.2-62 Added storage boxes for scaffolding materials

[FN 2004-012] in the annulus area of containment.

6.3 Refs, 15.4.1.14.1, Table 15.4-22, 15.4-23, Incorporated a change to the Unit 1 summary 15.4-24, 15.4-28, Figures 15.4-86, 15.4-87, of peak clad temperature penalties and benefits 15.4-88, 15.4-89, 15.4-90, 15.4-91, 15.4-92, for the large break LOCA. [10 CFR 50.46]

15.4-93, 15.4-94, 15.4-95, 15.4-96, 15.4-97

[FN 2004-037]

Table 6.4-1 Removed chemical storage tank 1-WT-TK-18.

[FN 2002-040]

Table 6.4-1 Replaced the bearing cooling biocide product

[FN 2004-007] name with the generic chemical compound.

Table 7.2-4, 15.4.2.2.2.1, 15.4 Refs Provided analysis results that smaller feedline

[FN 2004-005] 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, Modified the Unit 2 service water spray array 9.2.1.2.2 motor-operated valve safety injection signal

[FN 2002-056] actuation cross-tie.

8.2.2 Clarified the requirements for switchyard

[FN 2002-021] stability.

8.2.2 Replaced switchyard protective relays.

[FN 2003-025]

8.3.1.1.2.6, 8.3 Refs Provided for the use of UL 910 fire propagation

[FN 2003-047] testing for non-safety related and non-Appendix R applications.

Revision 5209/29/2016 NAPS UFSAR 40 Revision 4009/30/04 (continued)

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

8.3.1.2.1 Introduced compensatory measures that will be

[FN 2004-023] 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 Established the requirement that the service

[FN 2003-049] water spray array supply valves be secured in the accident position (open) with power removed from the operators in order to change the number of spray arrays required for loop operability from three to two.

9.2.2.2.2, 9.2.2.3.2, Table 9.2-6 Converted the mechanical chilled water unit

[FN 2003-001] refrigerant from R-12 to R-134a.

Table 9.2-4 Replaced auxiliary service water pump,

[FN 2004-014] 2-SW-P-4.

9.3.4.2.4.21 Provided a new packing configuration for

[FN 2004-003] charging system modulating valves that have no leakoff line.

9.4.1.2, Table 9.4-2 Corrected the description of the control and

[FN 2003-037] relay room air supply and exhaust flow rates.

9.5.5.2, 9.5.7.2, Figures 9.5-6 & 9.5-8 Replaced the 1H emergency diesel generator

[FN 2003-026] 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 Replaced the 2H emergency diesel generator

[FN 2003-045] lube oil and jacket coolant temperature switches with a temperature converter system.

10.4.8.5 Modified the conductivity monitoring function

[FN 2004-015] for the condensate polishing system.

Table 10.4-2 Incorporated editorial correction to properly

[FN 2004-022] 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, Replaced the Process Vent, Vent A, and Vent B 12.2.4 radiation monitors.

[FN 2003-031]

12.2.2.1, 12.2 Ref Dwgs Restored the 12.2 Reference Drawings section.

[FN 2002-043]

Revision 5209/29/2016 NAPS UFSAR 41 Revision 4009/30/04 (continued)

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

15.2.4.2.2 Corrected the description of valves required to

[FN 2004-032] be locked in order to provide isolation of primary grade makeup water from the reactor coolant system.

15.2.4.2.3 Corrected typographical error in reference

[FN 2004-010] document number.

15.4.1, 15.4.1.1, 15.4.1.4, 15.4.1.5.2, Revised the large break loss-of-coolant 15.4.1.5.6, 15.4 Refs, Table 15.4-1, 15.4-2, accident analyses.

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]

15.4.1.14.2, Table 15.4-25, 15.4-26, 15.4-27, Incorporated a change to the Unit 2 summary

& 15.4-28, Figures 15.4-98, 15.4-99, 15.4-100, of peak clad temperature penalties and benefits 15.4-101, 15.4-102, 15.4-103, 15.4-104, for the large break LOCA. [10 CFR 50.46]

15.4-105, 15.4-106, 15.4-107, 15.4-108, 15.4-109

[FN 2004-026]

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

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

17.2.2.8 Updated terminology to the current naming

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

[10 CFR 50.54(a)(3)]

17.2.10 Updated the description of qualification

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

[10 CFR 50.54(a)(3)]

Revision 5209/29/2016 NAPS UFSAR 42 Revision 4009/30/04 (continued)

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

18.3.2.4, 18 Refs, Table 18-1 Completed evaluation of and eliminated

[FN 2003-052] enhanced inspections for safety injection accumulator nozzles and charging line nozzles environmentally-assisted fatigue.

Revision 3909/30/03 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 3.6.2.4, Table 3.7-3, 3.11.2.9, 3A.46.1, Incorporated editorial corrections of a key 5.2.2.4, 6.2 Refs, 13.2.1 word index reference, misspelled words, and a

[FN 2003-041] table footnote.

1.1, 2.1.3.1, Table 3.8-7, 3.11.2.2, 3E.3.4, 4.0, Reflected the increased operating life basis 4.2.3.1.4, 5.1, Tables 5.1-1, 5.2-20, 5.2-21, from 40 to 60 years and added Chapter 18 5.4-2, & 5.4-3, 5.5.2.3.4, 6.1, 7.1, 8.1, 9.1, [10 CFR 54.21] to describe the programs and 10.1, 11.0, 18.0, 18.1, 18.1.1, 18.1.2, 18.1.3, activities that manage the effects of aging 18.1.4, 18.2, 18.2.1, 18.2.2, 18.2.3, 18.2.4, materials during the extended operation period 18.2.5, 18.2.6, 18.2.7, 18.2.8, 18.2.9, 18.2.10, associated with license renewal.

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]

2.3.3.2.5.1, 2.3.4.3, Tables 2.3-15 & 2.3-16, Replaced the emergency response facilities Table 7.5-2, 7.7.1.10 computer systems.

[FN 2002-011]

Table 2.4-6 Modified the submergence of one auxiliary

[FN 2003-030] flash evaporator pump and three screen wash pumps.

3.1.36.2, 6.2.2.3, 6.2.2.4.1 Revised the frequency of inspection for the

[FN 2002-004] quench spray and recirculation spray nozzles.

[10 CFR 50.90 License Amendment]

Revision 5209/29/2016 NAPS UFSAR 43 Revision 3909/30/03 (continued)

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

3.1.53.1, 6.2.2.2, 6.2.3.1.1, Table 6.2-40, Revised the boron concentration limits for the 6.3.3.4, Tables 6.3-1 & 6.3-5, 9.1.4.5, refueling water storage tank, casing cooling 9.3.4.2.4.8, 15.2.13.2.2 tank, safety injection accumulators, and the

[FN 2000-027 & FN 2000-027B] spent fuel pool in accordance with the Technical Specifications. [10 CFR 50.90 License Amendment]

Table 3.2-1, 6.4.1.3 Accurately reflected control room dose limits,

[FN 2003-021] auxiliary shutdown panel plant status, and refueling procedures. Deleted reference to the guide tube cover handling 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, Replaced the Unit 2 reactor vessel closure 3.7.2.7.3.4, 3.7.2.7.3.5, 3.7.3.1.3.7, 3.7 Refs, head.

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]

3.7.2.7.3, 3.7.2.7.3.1, 3.7.3.1.4, 4.1, 4.2.3.2.2, Replaced the Unit 1 reactor vessel closure Table 5.1-1, 5.2.3.1, 5.2.3.1.1, 5.2.3.3.1, head.

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]

3.8.1.5.1, 3.8.1.5.2, 3.8.1.5.2.1, 3.8.1.5.3, 3.8.2, Completed the restoration of construction 3.8.2.1.2.3, 3.8.2.1.2.4, 3.8.2.3, 3.8.2.7, opening in the containment structure for the 3.8.2.7.1, 3.8.2.7.2, 3.8.2.7.3, 3.8.2.9, 3.8.2.9.1, Unit 2 reactor pressure vessel head 3.8.2.9.2, 3.8.2.9.3, 3.8.2.9.4, 3.8.2.9.5, replacement.

3.8 Refs, 3A.10, 3A.15, 3A.18, 3A.19

[FN 2002-051 & FN 2003-005]

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

[FN 2002-050] temporary opening in the containment due to reactor vessel head replacement.

[10 CFR 50.54(a)(3)]

Revision 5209/29/2016 NAPS UFSAR 44 Revision 3909/30/03 (continued)

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

3.8.2.9, 3.8.2.9.2, 3.8.2.9.4, 3.8.2.9.5 Completed the restoration of construction

[FN 2003-007 & FN 2003-019] opening in the containment 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 Replaced service water discharge piping

& 3.8-43 mechanical (metal) expansion joints with

[FN 2002-022 & FN 2002-029] rubber expansion joints.

Figure 3.8-4, 5.1.1.9 Corrected spelling and typographical errors.

[FN 2002-055]

4.2.1.1.2, 4.2 Refs Included description of the consideration of

[FN 2002-057] 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, Incorporated small dimensional changes for Table 4.2-2 fuel assemblies and accurately reflected

[FN 2002-049] burnable poison assembly design.

4.2.3.4.2 Eliminated the seismic allowance in the control

[FN 2002-044] rod drop time surveillance requirement.

Figure 4.4-21, 7.9.2.1, Table 7.9-1 Described that Unit 2 incore instrumentation

[FN 2003-006] 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, Modified the service structure, cooling air Table 6.3-8, 9.1.4.4.2, Figures 9.1-5 & 9.1-6, shroud and shroud support, insulation, and 9.6.4.4, Table 9.6-1 intermediate lift ring for the Unit 2 reactor

[FN 2002-052] vessel head replacement.

5.1.1.9, 5.2.3.4, 5.2 Refs, 6.2.1.2.15, Modified the service structure, cooling air Table 6.3-8, 9.1.4.4.2, Figures 9.1-5 & 9.1-6, shroud and shroud support, insulation, and 9.6.4.4, 9.6 Refs, Table 9.6-1 intermediate lift ring for the Unit 1 reactor

[FN 2003-009] vessel head replacement.

5.2.2.2 Reflected Low Temperature Overpressure

[FN 2003-003] Protection System (LTOPS) bistable settings that were changed to preserve LTOPS setpoints.

5.5.3.2.1, Table 5.5-6 Removed a thermal sleeve from the Unit 1

[FN 2003-018] accumulator safety injection line to reactor coolant loop 2.

Revision 5209/29/2016 NAPS UFSAR 45 Revision 3909/30/03 (continued)

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

Unit 2 only: 6.1, 6.2.1.1.1.1, 6.2.1.1.1.2, Implemented the Unit 2 revised LOCA 6.2.1.1.1.3, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.2.2, containment integrity analysis. [10 CFR 50.90 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.4, 6.2.2.3.2.6, License Amendment]

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, 6.3-11, 6.3-12, & 6.3-13

[FN 2002-046]

6.1, 6.2.1.1.1.1, 6.2.1.1.1.2, 6.2.1.1.1.3, Implemented the Unit 1 revised LOCA 6.2.1.3.1, 6.2.1.3.1.1, 6.2.2.2, 6.2.2.3.2.1, containment integrity analysis. [10 CFR 50.90 6.2.2.3.2.2, 6.2.2.3.2.4, 6.2.2.3.2.6, 6.2.2.3.3, License Amendment]

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, 6.3-11, 6.3-12, & 6.3-13

[FN 2000-042 & FN 2002-015]

6.2.1.4.4, Table 6.2-37 & 6.2-53 Removed water-filled penetrations from the

[FN 2002-030] 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, Installed two new control room bottled air 9.4.1.3, 9.4.1.5, Table 9.4-2 trains to provide a total of four trains supplying

[FN 2001-029] breathing air and pressurization.

7.2.1.1.2, Figure 7.2-4 Reformatted the equations describing

[FN 2003-014] overtemperature delta T and overpower delta T setpoints.

8.1.2 Eliminated the battery charger for the spillway

[FN 2002-023] gate supervisory control system batteries.

8.2.1, Figures 8.2-1 & 8.2-2 Installed an additional 500/230 kV transformer

[FN 2003-024] and rearranged the 230 kV bus in the switchyard.

Figure 8.2-1 Replaced vital bus inverters 2-I & 2-II and

[FN 2003-020] added an additional bypass transformer for each unit.

8.3.1.1.2.3, 8.3.1.2.1, 8.3.1.2.2.4, Table 8.3-8 Replaced vital bus inverters 1-I & 1-II.

[FN 2003-004]

Revision 5209/29/2016 NAPS UFSAR 46 Revision 3909/30/03 (continued)

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

8.3.1.1.2.3, 8.3.1.4.1.4, 8.3.1.2.2.4, Table 8.3-8 Installed replacement vital bus inverters 2-I

[FN 2002-017] and 2-II.

9.1.4.9.1, 9.1.4.9.2, 9A.2, 9B.2, 9B.3, 15A.1 Placed a cask pedestal in the cask loading area

[FN 2003-029] of the spent fuel storage pool.

9.2.3.1, Table 9.2-10 Refurbished Well 4 of the domestic water

[FN 2003-034] system.

9.3.1.3.2 Provided cross-reference to UFSAR

[FN 2002-041] Section 3.1.19.2.

9.3.4.2.4.20, Table 9.3-5, 12.1.6.2 Corrected the description of the operation of

[FN 2003-015] the primary ion exchangers.

9.5.1.3.1.3 Corrected the description of the auxiliary

[FN 2003-033] feedwater pump rooms as 10 CFR 50 Appendix R areas.

9.5.2.1.1 Allowed the public address system to be

[FN 2003-017] 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 Replaced the 1J emergency diesel generator

[FN 2003-013] lube oil and jacket coolant temperature switches with a temperature converter system.

10.2 Clarified the operating pressure limit for high

[FN 2002-035] pressure turbine gland steam header pressure.

10.4.2.2 Provided a clarified description of the function

[FN 2002-039] of the circulating water vacuum priming system to remove noncondensable gases.

10.4.8.2, 10.4.8.4, 10.4.8.5 Upgraded the Unit 1 and Unit 2 condensate

[FN 2002-012 & FN 2002-048] 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, Replaced the Process Vent, Vent A, and Vent B 11.4.3, 11.4.3.1.1, 11.4.3.1.2, 11.4.3.1.3, radiation monitors.

11.4.3.2, 11.4.5, Table 11.4-1 & 11.4-2

[FN 2003-038]

15.1.2.3 Provided an enhanced text description of rod

[FN 2002-031] cluster control assembly bank operability consistent with the Technical Specifications.

15.4 Refs, Table 15.4-5 Incorporated a change to the summary of peak

[FN 2003-028] clad temperature penalties and benefits for the large break LOCA. [10 CFR 50.46]

Revision 5209/29/2016 NAPS UFSAR 47 Revision 3909/30/03 (continued)

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

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

[FN 2003-023]

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

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

[FN 2003-016]

17.2.1.2 Assigned responsibility for maintenance of

[FN 2003-010] plant equipment history to the Manager Nuclear Maintenance. [10 CFR 50.54(a)(3)]

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

[FN 2002-008] Nuclear Oversight Board.

[10 CFR 50.54(a)(4)]

2.3.4.3 Updates the Meteorological Information Dose

[FN 2002-037] Assessment System (MIDAS) information and how the plant computer processes the data.

Revision 3809/03/02 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI Deleted Hypochlorite Treatment from the

[FN 2002-026] Key Word Index listing for the domestic water system.

Figure 1.2-1 Added the Independent Spent Fuel Storage

[FN 96-021] Installation to the Site Plan.

Revision 5209/29/2016 NAPS UFSAR 48 Revision 3809/03/02 (continued)

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

2.4.3, 2.4.14, 2A.4, 2A.5, 3.1.7.2, 3.8.4.5.2, Implemented the conversion to Improved 3.8.4.5.3, 3.8.4.6, 3.8.4.8, Table 3.8-15, 3A.13, Technical Specifications including the 3A.16, 4.3.1.3, 4.3.1.5, 4.3.2.2.6, 4.3.2.4, relocation of requirements to the UFSAR.

4.3.2.5.2, 4.3.2.5.6, 4.4.5.3, 5.1.3.1, 5.2.1.2, [10 CFR 50.90 License Amendment]

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]

2.4.10, 2.5.5, 2A.3, 2A.4, Table 3.2-1, 3.8.6, Provided description of the flood protection 3.8.6.1, 3.8.6.2, Figure 3.8-61 dike.

[FN 2001-006]

2.4.11.4 Included reservoir discharge flow reductions

[FN 2000-040] 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, Established spent fuel pool soluble boron 4.3 Refs, 9.1.2, Table 15.3-1 concentration and fuel assembly loading

[FN 2000-037] 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 5209/29/2016 NAPS UFSAR 49 Revision 3809/03/02 (continued)

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

3.1.53.2, 6.2.2.2, 6.2.3.1.1, 6.2.3.3, Increased the boron concentration in the spent Table 6.2-40, Figures 6.2-76 & 6.2-77, 6.3.3.4, fuel pool and Unit 1 refueling water storage Tables 6.3-1 & 6.3-5, 9.1.4.5, 9.3.4.2.4.8, tank, casing cooling storage tank, and safety 15.2.13.2.2, Table 15.2-1 injection accumulators. [10 CFR 50.90 License

[FN 2001-041] Amendment]

3.8.2.1.4.1, 4.3.2.7, Table 5.5-17, 15.4.5.3 Corrected typographical and editorial errors.

[FN 2002-036]

3C.3.3, 3C.5.4.6.2, & 10.4.6.5 Provided discussion of the auxiliary building

[FN 2001-038] ambient temperature monitoring 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, Supplemented the fuel rod design criteria 4.4 Refs, 15.4 Refs references to new fuel performance models.

[FN 2002-028]

5.2.5.1, 5.2 Refs Updated references to the current inservice

[FN 2001-039] inspection interval.

6.2.2.1, 7.1.3.2.4, Table 7.5-3, 8.3.2.1, Incorporated technical and editorial corrections 9.5.1.3.1.4 and clarifications related to containment

[FN 2001-022] depressurization systems, environmental requirements of the reactor trip system, control room indicators, and dc power system.

6.2.2.3.2.1 Updated the containment analysis NPSH

[FN 2001-016] 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 Indicated that the maximum relative humidity

[FN 2001-025] 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, Reanalyzed hydrogen concentration in Figures 6.2-80, 6.2-81, 6.2-82, 6.2-86, 6.2-87, containment following a LOCA.

6.2-88, 6.2-89, 6.2-90, & 6.2-91

[FN 2002-016]

6.2 Refs, 6.4.1.3.3, Table 6.4-1 Corrected a typographical error and

[FN 2001-033] incorporated changes omitted from a previously implemented UFSAR change.

Revision 5209/29/2016 NAPS UFSAR 50 Revision 3809/03/02 (continued)

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

Tables 6.2-44 & 6.2-45, 6.3.2.2.6, 6.3.4.4 Revised the safety analysis flow rate for

[FN 2002-005] 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 Clarified that auxiliary building central exhaust

[FN 2000-038] is manually aligned to the filters rather than automatically.

6.4.1.3.3, Table 6.4-1 Deleted the product name for zinc chloride and

[FN 2001-035] revised its storage tank capacity.

6.4.1.3.3, Table 6.4-1 Updated the description of potentially

[FN 2002-013] 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 Updated the figure representations of the

[FN 2001-026] pressurizer pressure and level control and pressurizer heater control systems to agree with the text description.

Figure 8.2-1 Corrected a minor error in the figure

[FN 2001-034] 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 Removed terminology associated with the

[FN 2001-032] former 10 CFR 50.59 regulation and incorporated wording from the current rule.

9.2.1.2.1, 9.2.1.4.1 Clarified the two-valve isolation from the

[FN 2000-012] 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 Reconfigured the service water supply and

[FN 2000-036] 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 Replaced the service water air system

[FN 2001-020] compressor, dryer, and receiver tank.

9.2.2.3.1 Clarified the component cooling system

[FN 2001-028] thermal relief requirements.

Revision 5209/29/2016 NAPS UFSAR 51 Revision 3809/03/02 (continued)

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

9.3.2.1.2, 9.3.2.1.3, Figure 9.3-2 Corrected the description of the steam

[FN 2001-031] generator on-line chemistry monitoring system.

9.3.2.2, 9.3 Refs Clarified the status of the High Radiation

[FN 2002-007] Sampling System - Post-Accident.

[10 CFR 50.90 License Amendment]

9.5.1 Clarified the description of the low pressure

[FN 2002-009] carbon dioxide system zone isolation.

9.5.1.1 Identified fire protection systems that are not

[FN 2001-036] required to satisfy regulatory requirements.

[10 CFR 50.48]

9.5.1.1 Identified fire protection systems that are not

[FN 2002-003] required to satisfy regulatory requirements.

[10 CFR 50.48]

Figure 15.2-44, 15.4.6.2.3.4 Corrected a typographical error and

[FN 2002-019] incorporated a change omitted from a previously implemented UFSAR change.

15.4.2.2.2.2, 15.4 Refs Incorporated the evaluation of steam generator

[FN 2002-020] 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, Modified organizational titles and realigned 17.2.1-2, & 17.2.1-3 certain reporting relationships within the

[FN 2002-006] Nuclear Business Unit. [10 CFR 50.54(a)(3)]

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

[FN 2001-037] organization 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, Relocated North Anna Power Station current 17.2.15, 17.2.16, 17.2.18, 17.2 Refs, technical specification requirements for the Table 17.2-0, Appendix C Management Safety Review Committee,

[FN 2001-021] Station Nuclear Safety and Operating Committee, and Station Nuclear Safety to the QA Topical Report. [10 CFR 50.90 License Amendment]

17.2.7 Updated the description of the organizational

[FN 2002-032] 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 5209/29/2016 NAPS UFSAR 52 Revision 3709/04/01 Changes Made under the provisions of 10 CFR 50.59 except Section 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, Incorporated technical and editorial corrections 1.5.1.3, 1.5.1.4, 1.5.1.5, 1.5.1.6, 1.5.2, 1.5.2.1, and clarifications related to miscellaneous 1.5.2.2.1, 1.5.2.2.2, 1.5.2.2.3, 1.5.2.2.4, portions of the reactor design.

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, 11A.1.3, 11A.3, 11A Refs, Table 11A-1, & Table 14.1-1

[FN 2000-022]

2.1.3.3, 3.9.1.2.3, Table 6.4-1, 9.1.4.5 Corrected typographical, administrative, and

[FN 2001-023] format errors.

2A, 3.8 Refs Corrected typographical and editorial errors.

[FN 2000-045]

Table 3.5-5, 9.5.1.2.1, 9.5.1.2.4.4, 9.5.1.3.1.2, Updated the description of fire protection and 9.5.1.4.1.2 fire fighting equipment.

[FN 2001-011]

3.7.2.5, 3.7.3, 3.7.3.2, 3.7.3.2.2.3, 3.7.3.2.2.4, Incorporated the criteria and methodology of 3.7.3.3.5, 3.7 Refs, 3.9.1.3, 3.10.1, 3.10.2, the generic implementation procedure for 3.10.3, 3.10 Refs seismic design and equipment verification.

[FN 2001-007] [Unresolved Safety Issue A-46]

3.8.1.1.6, 9.1.4.4.12, 9.5.9.1, 9.5.9.2 Installed Helium and Vacuum Drying System

[FN 96-024] equipment that supports loading of Independent Spent Fuel Storage Installation casks. Updated the cask trolley description.

Figure 3.8-31 Deleted pump house gate and fence symbols

[FN 2000-033] 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 Corrected typographical spelling errors and

[FN 2001-009] electronic scanning discrepancies, and incorporated a phrase omitted from a previously implemented UFSAR change.

Revision 5209/29/2016 NAPS UFSAR 53 Revision 3709/04/01 (continued)

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

Table 3C-2 Revised operating pressure and temperature,

[FN 2001-001] line size, seismic class, 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 Incorporated technical and editorial corrections

& 4.3-39, 6.2.1.3.1.1, 6.2.1.3.1.3, 6.2 Refs, and clarifications related to plant safety 6.3.2.2.1, Figures 6.4-2 & 6.4-3, 7.2.2.1.2.1, analyses.

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]

4.2.1.2.2 Changed the material of the fuel assembly

[FN 2001-004] hold-down spring bolts that attach the springs to the top nozzle.

Revision 5209/29/2016 NAPS UFSAR 54 Revision 3709/04/01 (continued)

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

4.3.1.1, 4.3.1.3, 4.3.1.5, 4.3.2.1, 4.3.2.2, Incorporated technical and editorial corrections 4.3.2.2.3, 4.3.2.2.4, 4.3.2.2.5, 4.3.2.2.6, and clarifications related to reactor design 4.3.2.2.7, 4.3.2.3.1, 4.2.3.2.3, 4.3.2.3.4, 4.3.2.4, nuclear.

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]

4.4.1.1, 4.4.1.5, 4.4.2.1, 4.4.2.2, 4.4.2.2.1, Incorporated technical and editorial corrections 4.4.2.2.2, 4.4.2.2.3, 4.4.2.2.5, 4.4.2.2.6, 4.4.2.3, and clarifications related to thermal-hydraulic 4.4.2.3.1, 4.4.2.3.2.1, 4.4.2.3.2.2, 4.4.2.3.3, reactor design.

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, 4.4.2.11, 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]

5.2.2.2 Updated the calculation of the LTOPS enabling

[FN 2001-019] temperature.

5.2.2.2, 5.2.3.3.1, 5.2 Refs, Tables 5.2-20 Revised the analysis basis for reactor coolant

& 5.2-21, 5.4.3.6, 5.4.3.6.1, 5.4.3.6.3.2, system pressure/temperature operating limits, 5.4 Refs, Tables 5.4-2 & 5.4-3 LTOPS setpoints, and LTOPS enable

[FN 2000-048] temperatures. [10 CFR 50.90 License Amendment]

5.2 Refs, & Table 5.2-21 Revised the Pressurized Thermal Shock

[FN 2001-013] screening calculation result for Unit 2 vessel weld 05A. [10 CFR 50.61]

Revision 5209/29/2016 NAPS UFSAR 55 Revision 3709/04/01 (continued)

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

6.2.4.1, 6.2 Refs Documented the evaluation of isolated

[FN 99-016] water-filled containment 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 Provided additional description of the fuel

[FN 99-076] transfer tube design, the function of its isolation valve, and associated test requirements.

6.2.5.3, Table 6.2-59 Updated the description of the containment

[FN 2001-010] hydrogen generation analysis.

Table 6.2-51, 9.4.8.1 Clarified the description of testing of the

[FN 99-054] safety-related charcoal filters installed in the auxiliary building and control room ventilation exhaust systems. [Generic Letter 99-02 and 10 CFR 50.90 License Amendment]

Table 6.2-53 Corrected a typographical error.

[FN 2000-050]

6.3.3.10, 6.3 Refs Incorporated the revised cold-to-hot leg

[FN 2000-027A] recirculation switchover time associated with increased boron concentration. [10 CFR 50.90 License Amendment]

Table 6.3-3, Table 9.3-53 Revised the description of the charging/high

[FN 2000-006] head safety injection pumps material construction.

Table 6.4-1 Changed the bearing cooling tower biocide to

[FN 2001-002] Isothiazolin.

8.3.1.1.1 Provided discussion allowing the reserve

[FN 2000-046] station service load shed circuit to be defeated for short periods to support maintenance activities.

9.1.3.3.1, Table 9.1-2 Updated the maximum spent fuel pit heat load

[FN 2001-018] 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 Clearly defined the number of service water

[FN 2000-049] system reservoir spray arrays that are required to be operable to meet minimum design basis requirements.

9.2.1.2.2, Figure 9.2-1 Implemented periodic blowdown of the service

[FN 99-032] water reservoir to reduce concentration of chlorides and other contaminants.

Revision 5209/29/2016 NAPS UFSAR 56 Revision 3709/04/01 (continued)

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

9.6.4.1 Deleted the requirement for Station Nuclear

[FN 2000-044] Safety and Operating Committee review and approval of safe load path and exclusion area procedure changes prior to use.

9.6.4.4 Listed the reactor vessel head stud racks and

[FN 2000-043] 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, Modified organizational titles and reporting 17.2.2.1, 17.2.2.5, 17.2.3, 17.2.7, 17.2.10, relationships associated with the entire Nuclear 17.2.15, 17.2.16.2, 17.2.17, 17.2.18, Business Unit. [10 CFR 50.54(a)(3)]

Figures 17.2.1-1, 17.2.1-2, & 17.2.1-3, Table 17.2-0

[FN 2001-015]

15.2.6, 15.2.6.1, 15.2.6.1.1, 15.2.6.1.2, Reflected the current design bases that credit 15.2.6.2, 15.2.6.2.1, 15.2.6.2.1.2, 15.2.6.2.2, Technical Specification controls with 15.2.6.2.2.2, 15.2.6.2.3, 15.2.6.2.3.2, 15.2.6.3, precluding the preconditions for significant and 15.2.6.3.1, 15.2.6.3.2, 15.2.6.4 uncontrolled reactivity insertion during the

[FN 2000-047] 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, Updated the analysis of the Loss of External 15.2-21, 15.2-22, 15.2-23, 15.2-24, 15.2-25, Electric Load and/or Turbine Trip transient.

15.2-26, 15.2-27, 15.2-28, 15.2-29, 15.2-30,

& 15.2-31

[FN 2001-005]

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

[FN 99-075] description of the retention of quality assurance records in electronic media.

[10 CFR 50.54(a)(4)]

Table 17.2-0 Clarified the provision for substitution of

[FN 2001-017] experience for a bachelors degree.

[10 CFR 50.54(a)(3)]

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

[FN 2000-004] consistent with ANSI N45.2.9 or applicable regulations. [10 CFR 50.54(a)(4)]

Revision 5209/29/2016 NAPS UFSAR 57 Revision 3609/01/00 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 1.2.2, 1.2 RefDwgs, Ch 2, Tbl 2.1-2, Incorporated technical and editorial corrections 2.3.4.1, 2.4.1.2, 2.4.2.2, 2.4.3, 2.4.3.1, 2.4.3.2, and clarifications related to civil, structural, 2.4.3.3, 2.4.3.4, 2.4.3.5, 2.4.3.6, 2.4.8, and seismic topics.

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]

Revision 5209/29/2016 NAPS UFSAR 58 Revision 3609/01/00 (continued)

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

KWI, 2.3.3.1.2, Table 3.2-1, 3.7.2.1, Corrected cross-references, typographical and 3.7.2.6.1.7, 3.7.3.1.1, 3.7.3.1.2.3, 3.7.3.1.2.4, editorial errors, and electronic scanning 3.7.3.1.2.5.1, 3.7.3.1.3.2, 3.7.3.2.2.2, 3.8.5, discrepancies and standardized equation and Figure 3.8-32, 4.3.2.2.6, 4.3.2.8.2, 5.5.9.3.3, footnote notations.

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]

1.1, 1.2.7, 1.2.11, 1.4, 1.4.1, 1.4.2, 1.4.3, Incorporated technical and editorial corrections 1.4.3.1, 1.4.3.2, 1.4.4, 1.4.4.1, 1.4.4.2, and clarifications related to the bearing cooling Table 1.4-1, 3.2.2, 3.9.2.1, Table 3.11-3, 3A, and condensate systems.

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]

1.2.5, 2.1.1.3, 2.1.2.1, 3.1.51.2, 6.3.3.5, 9.3.5.1, Incorporated technical and editorial corrections 9.3.5.2, Tables 9.3-7 & 9.3-8, Figure 9.3-6, and clarifications related to boron recovery and Chapter 11, 11.2.1, 11.2.2, 11.2.2.2, 11.2.3, waste disposal systems.

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]

1.2.8, 8.1.1, 8.1.2, 8.2.1, 8.2.2, 8.2 RefDwgs, Incorporated technical and editorial corrections Table 8.2-1, Figures 8.2-1 through 8.2-15, 8.3, and clarifications related to vital bus and 8.3.1.1.1, 8.3.1.1.2.3, 8.3.1.2, 8.3.1.2.1, station service systems.

8.3.1.2.2.3

[FN 99-042]

Revision 5209/29/2016 NAPS UFSAR 59 Revision 3609/01/00 (continued)

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

1.2.11, Tables 3.2-1 & 3.9-2, 3.11.1.1, Incorporated technical and editorial corrections Tables 3.11-1 & 3C-3, 5.2.3.2, Table 5.2-19, and clarifications related to Chemical and 6.3.2.1.2, 9.3.4.1, 9.3.4.1.2, 9.3.4.2.1, Volume Control System.

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]

Figure 1.2-2, 9.1.4.4.12 Added the Fuel Building trolley enclosure.

[FN 99-025]

2.3.2.2.1.3, 2.3.3.2.1, 2.3.3.2.2, 2.3.3.2.4, Incorporated technical and editorial corrections 2.3.3.2.5.1, Table 2.3-15, 3.11.2.10, 7.7.1.4 and clarifications related to the electrical

[FN 2000-019] instrumentation system.

2.4 Update the description of the service water

[FN 99-049] reservoir spray array freeze protection.

3.1.15.2, 3.11.1.2, 3A.13, 3A.97, Table 3C-3, Incorporated technical and editorial corrections 6.2.2.3, 6.2.3.2, Tables 6.2-48, 6.2-49, and clarifications related to the ventilation

& 6.2-51, 6.3.2.1.4.1, 6.4.1.1, 6.4.1.2, 6.4.1.3, system.

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]

3.1.42.2, Table 3.9-1, 9.2.2.1.3, 9.2.2.2.1, Incorporated technical and editorial corrections 9.2.2.2.4, 9.2.2.3.1, 9.2.2.3.3, 9.2.2.5.1, and clarifications related to component cooling Tables 9.2-5, 9.2-8, & 9.2-9, Figures 9.2-2 water system.

& 9.2-3

[FN 99-053]

Revision 5209/29/2016 NAPS UFSAR 60 Revision 3609/01/00 (continued)

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

3.1.46.2, 3.1.47.2, 3.1.48.2, 3.11.2.3, 5.2.4.1.1, Incorporated technical and editorial corrections 6.1, 6.2.1.1.1.1, 6.2.1.2.6, 6.2.1.2.9, 6.2.1.2.13, and clarifications related to containment 6.2.1.3.1.1, 6.2.1.3.2.1, 6.2.1.3.2.3, 6.2.1.3.2.4, systems.

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]

3.1.53.2, 4.2.1.4.1, 4.2.1.4.2, 6.2.2.2, 9.1.1, Incorporated technical and editorial corrections 9.1.2, 9.1.4.2, 9.1.4.3.1, 9.1.4.4.1, 9.1.4.4.4, and clarifications related to the fuel handling 9.1.4.4.6, 9.1.4.4.8, 9.1.4.4.10, 9.1.4.4.12, system.

9.1.4.5, 9.1.4.6.6.1, 9.1.4.7, Figure 9.1-4

[FN 99-067]

3.6.2.3 Revised the list of piping runs subject to

[FN 96-038] 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, Incorporated technical and editorial corrections 3.6.3.3, 3.6 Refs, 3C.1.1, 3C.1.2, 3C.1.3, and clarifications related to the high energy line 3C.2.7, 3C.2.7.1, 3C.2.7.2, 3C.2.7.3, 3C.2.7.9, break report.

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]

3.8.2.1.4 Incorporated a description of the containment

[FN 99-059] liner repair procedure for through-wall defects.

Revision 5209/29/2016 NAPS UFSAR 61 Revision 3609/01/00 (continued)

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

3.8.2.1.4.1, 5.5.4.3.1, 5.6.2.1, 6.4.1.3.2, Incorporated technical and editorial corrections 7.2.2.3.2, 7.2.2.3.4, 8.3.1.1.2.6, Table 9.2-10, and clarifications related to the fire protection 9.3.3.2, 9.4.8.5, 9.5.1, 9.5.1.1, 9.5.1.2.2.1, system.

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, 9.5.1.3.1.11, 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]

3.8.4.8 Updated description of the methodology of

[FN 2000-029] calculating service water reservoir losses.

Table 3.8-17, Figure 3.8-33 Reincorporated individual piezometer

[FN 97-053A] 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, Incorporated editorial changes consisting of 10.2-7, & 10.2-8, 15.2.10.3.2, Tables 15.4-5 grammatical enhancement, correction of

& 15.4-6 typographical errors and cross-references, and

[FN 2000-005] consistent use of terminology, capitalization, and punctuation.

3.9.2.1, 10.3.1 Clarified the design code for the main steam

[FN 99-056] safety system valves.

Table 3.9-1, 5.5.2.2, 9.2.3.2, 9.2.3.2.2, 10.1, Incorporated technical and editorial corrections 10.4.3.2, 10.4.4.3, 10.4.6.2, 10.4.6.3, 10.4.6.5, and clarifications related to feedwater, 10.4.8.2, 10.4 Refs, Tables 10.4-2 & 10.4-4, condensate, steam generator blowdown, and Figure 10.4-4 condensate polishing systems.

[FN 99-021]

3.11.1.3.1, 3.11.1.3.2, 3.11.1.3.3, 3.11.2.2, Incorporated technical and editorial corrections 4.2.3.5, 5.5.1.3.9, 7.2.2.3.2, 7.5.1, 7.5.2, and clarifications related to nuclear control Tables 7.5-1 through 7.5-3, 7.7.1.3.3, 7.7.1.4.2, system.

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]

Table 3.11-2, 6.1, 6.2.5.2 Incorporated technical and editorial corrections

[FN 99-061] and clarifications related to containment atmosphere cleanup system.

Revision 5209/29/2016 NAPS UFSAR 62 Revision 3609/01/00 (continued)

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

3C.5.1.6.1, 3C.5.1.6.2 Added a description of the environmental

[FN 2000-010] 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 Incorporated technical and editorial corrections

[FN 2000-025] and clarifications related to main steam line break feedwater isolation.

Chapter 4, 4.1, 4.4 Refs, Tables 4.1-1 & 4.1-2, Incorporated technical and editorial corrections 4.2.1.1.1, 4.2.1.1.2, 4.2.1.2, 4.2.1.2.1, 4.2.1.2.2, and clarifications related to the reactor design 4.2.1.3.1, 4.2.1.3.2, 4.2.1.4.2, 4.2.1.4.4, 4.2.2.1, (mechanical).

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]

4.2.1.4.3 Updated the new fuel and insert component

[FN 2000-001] inspection requirements to apply to either preshipment or postshipment inspections.

4.2.3.4.2 Incorporated a discussion of the allowance,

[FN 99-046] 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, Incorporated technical and editorial corrections 5.5.4.2.1.3, 5.5.4.2.2.1, 5.5.4.2.2.3, 5.5.7.2, and clarifications related to residual heat 5.6.1, 7.6.2.1 removal system.

[FN 99-045]

Tables 5.4-2 & 5.4-2 Updated the surveillance capsule withdrawal

[FN 98-049] schedules for both units. [10 CFR 50, Appendix H]

5.5.1.2, 5.5 Refs Updated the design description of the reactor

[FN 2000-007] coolant pump thermal barrier heat exchanger.

5.5.10.2, 5.5.10.3 Modified the reactor head vent line to provide

[FN 2000-015] clearance for reactor cavity seal ring installation and removal.

6.2.1.2.5 Corrected the description of the structural

[FN 2000-031] integrity of the neutron shield surge tank.

Revision 5209/29/2016 NAPS UFSAR 63 Revision 3609/01/00 (continued)

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

6.2.1.3.2.5, 6.2.2.2 Corrected the description of materials used in

[FN 2000-021] containment subcompartment blowout panels, reactor cavity drain, and containment sump screen.

Table 6.2-51 Corrected typographical, administrative, and

[FN 2000-039] format errors.

6.4.1.3.3, Table 6.4-1 Updated the description of potentially

[FN 99-071] 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 Revised the description of the plant computer

[FN 97-020] 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, Incorporated technical and editorial corrections 9.5.2.1.2, 9.5.2.1.3, 9.5.2.1.4, 9.5.2.2.1, and clarifications related to the electrical and 9.5.2.2.2, 9.5.2.2.3, 9.5.2.2.4, 10.2 communication systems.

[FN 2000-002]

9.1.3.2, Table 9.1-1, 9.3.4.2.2.3, Table 9.3-5 Added descriptions of the administrative

[FN 99-074] 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. Incorporated modifications to the on-line 4.7.2 chemistry monitoring system.

[FN 97-055]

9.2.2.1.2, 9.2.2.2.2, 9.2.2.3.1, 9.2.2.3.2 Added notes reflecting that some steam

[FN 97-010] 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 Incorporated a plant modification that allows

[FN 99-023] the Unit 1 isolated phase bus duct air cooler to be supplied by chilled water as an alternative to bearing cooling.

Table 9.2-5 Revised the design code and tube material for

[FN 97-050] the component cooling water 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, Incorporated technical and editorial corrections Table 9.3-1, Figure 9.3-1, 9.5.10.3, 10.3.2 and clarifications related to instrument air

[FN 2000-003] system.

Revision 5209/29/2016 NAPS UFSAR 64 Revision 3609/01/00 (continued)

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

9.3.2.1.1, 9.3.2.1.2, 9.3.2.2.3, 9.3.3.2, Incorporated technical and editorial corrections Tables 9.3-3 & 9.3-10, Figures 9.3-2 & 9.3-3, and clarifications related to feedwater, 10.4.8.4 condensate, steam generator blowdown, and

[FN 99-051] condensate polishing systems.

9.3.2.1.2 Add a discussion of the on-line chemistry

[FN 98-042] monitoring system.

9.3.2.1.5 Clarified the use of the on-line chemistry

[FN 99-068] monitoring system panel.

9.3.4.2.4.7 Augmented the description of purging gases

[FN 2000-009] from the volume control tank.

9.4.1.4 Corrected a typographical error.

[FN 2000-035]

9.5.1.2.2.2, 9.5 Refs Adds a description of the design basis for the

[FN 99-033] emergency switchgear room halon system.

Table 10.4-1 Revised an existing description of the Unit 1

[FN 99-052] auxiliary feedwater system design basis to reflect the bases for both Units 1 & 2.

Table 10.4-2 Revised design data to reflect the replacement

[FN 96-074] & FN 99-035] 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, Incorporated changes resulting from the revised 15.2.8.3, 15.2.9.1, 15.2.9.2.1, 15.2.9.2.2, loss of normal feedwater accident analysis.

Table 15.2-1, Figures 15.2-28 through 15.2-35

[FN 99-047]

13.2.1, 16.1 Corrected reference from Environmental

[FN 2000-028] Technical Specifications to Environmental Protection Plan.

13.4 Updated the name of the subcommittee

[FN 2000-024] responsible for Management Safety Review Committee independent reviews.

15.2.10.1 Corrected the description of feedwater pump

[FN 99-041] discharge 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, Incorporates a summary of the peak clad 15.4.1.5.3, 15.4 Refs, Table 15.4-5 temperature penalties and benefits for the small

[FN 99-070] and large break LOCA which are reported per 10 CFR 50.46 requirements.

Revision 5209/29/2016 NAPS UFSAR 65 Revision 3609/01/00 (continued)

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

15.3.5.2 Corrected the values of total activity assumed

[FN 99-055] 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 Modified organizational titles and reporting

[FN 2000-032] relationships associated with information technology.

17.2.1.2, 17.2.2.6, Figure 17.2.2-1 Updated organizational description to reflect

[FN 2000-008] Supply Chain Management (Generation) titles.

17.2.1.2, Figure 17.2.1-2 Modified organizational titles and reporting

[FN 2000-017] relationships associated with records management.

17.2.1.2, Figure 17.2.1-2 Modified organizational titles and reporting

[FN 2000-034] relationships associated with the radwaste facility.

Revision 5209/29/2016 NAPS UFSAR 66 Revision 3509/01/99 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 1.2.12, 2.1.1.1, 2.1.1.2, 2.1.2.1, 2.1.2.2, Incorporated technical and editorial corrections 2.1.3.3, Table 2.1-2, 2.2.1.3, 2.2.1.5, 2.3.2.2.1, and clarifications related to the service water 2.3.2.4, 2.4.1.1, 2.4.1.2, 2.4.2.2, 2.4.3, 2.4.4, system.

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]

KWI, 1.2.3, 4.2.3.5, 5.5.2.3.5, 6.2.4.1, 6.2.4.2, Incorporated technical and editorial corrections 7.3.1.3.5.4, Table 7.5-3, 7.7.1.8, 7.7.1.8.1, 10.1, and clarifications related to the main steam Figures 10.1-1 and 10.1-2, 10.2, 10.3.1, 10.3.2, system.

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]

KWI, 2.3.5.1, 2.4.11.5, Table 3.2-1, 3.4, Corrected references, spelling, and format.

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]

Revision 5209/29/2016 NAPS UFSAR 67 Revision 3509/01/99 (continued)

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

KWI, Ref Dwgs: 1.2, 2.4, 2.5, 3.6, 3.8, 3C, 5.1, Corrected a Key Word Index reference, 5.5, 5.6, 6.2, 6.3, 6.4, 7.1, 7.3, 7.7, 8.1, 8.2, 8.3, supplemented the reference drawings lists, and 9.1, 9.2, 9.3, 9.4, 9.5, 9A, 10.2, 10.3, 10.4, 11.2, corrected text citations of reference drawings.

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]

KWI, Table 3.5-1, Table 6.2-46, 6.3.2.1.1, Corrected cross-references, typographical 6.3.2.1.4.6, 6.3.3.12, 6.3.5.3.2, 7.1, 7.1.3.1, errors, and electronic scanning discrepancies; 7.2.2.2.2, 7.2.2.2.3, 7.2.2.2.4, 7.2.2.2.5, improved consistency of exponent, numerical, 7.2.2.2.6, 7.2.2.2.8, 7.2.2.2.9, 7.3.2.1, 7.5.2, and Greek letter notation; improved 7.6.2.2, 7.6.3.2, 7.6.5, 7.6 Refs, 7.9.1, 7.9 Refs, consistency of abbreviations; and incorporated 9.2.3.2.1, Table 9.2-3, 11.3.5.4, Table 12.1-4, two tables omitted from a previous UFSAR 12.2.6, 15.2.6.2.2.2, 15.2.13.2.2, Table 15.4-5, change.

Table 15.4-6

[FN 99-012]

1.2.10, 2.4.11.5, 2.4.11.6, Table 2.4-7, 10.4.2.3, Incorporated technical and editorial corrections Figures 10.4-1 and 10.4-2 and clarifications related to the circulating

[FN 99-027] water system.

Ref Dwgs: 1.2, 2.4, 2.5, 3.6, 3.8, 3C, 5.1, 5.5, Clarified the reference drawings lists by 5.6, 6.2, 6.3, 6.4, 7.1, 7.3, 7.7, 8.1, 8.2, 8.3, 9.1, spelling out words abbreviated in the titles and 9.2, 9.3, 9.4, 9.5, 9A, 10.2, 10.3, 10.4, 11.2, using consistent punctuation.

11.3, 11.4, 11.5, 11C, 12.1, 12.2, 12.3, 14.1, 15, 15.4

[FN 99-009]

1.3, 1.3.1.1, 1.3.1.2, 1.3.1.3, 1.3.1.4, 1.3.1.4.1, Incorporated technical and editorial corrections 1.3.1.4.2, 1.3.1.5, 1.3.1.6, 1.3.2, Tables 1.3-1 and clarifications related to the emergency through 1.3-13, 7.7.1.13.2, 8.1.2, 8.1 RefDwg, power system.

8.3.1.1.1, 8.3.1.1.2.2, 8.3 Ref Dwg

[FN 99-002]

Revision 5209/29/2016 NAPS UFSAR 68 Revision 3509/01/99 (continued)

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

Table 1.3-1, 3.8.4.1, Tables 3.9-1 & 3, 3.11.2.2, Corrected cross-references, typographical Figure 4.3-6, 5.1.2.1.3, Figure 5.1-2, 5.2.3.3.1, errors, and electronic scanning discrepancies; 5.2.5.1, Tables 5.2-12, 22, & 28, Figures 5.2-5, improved consistency of upper and lower case 6, 9, & 10, 5.4.3.6.1, 5.4.3.6.2, 5.4 Refs, and listing notation; improved superscript and 5.6.2.3, Figure 6.2-66, 7.7.1.5, 11.4.3.1.1, subscript notation; and incorporated a list 15.4.1.7.2, 15.4.1.7.3 omitted from a previous UFSAR change.

[FN 99-001]

Table 1.3-2, 3.1.33.2, Tables 3.9-2 & 3.11-1, Incorporated technical and editorial corrections 3A.1.2, 6.3.2.1.1, 6.3.2.1.4.1, 6.3.2.1.4.2, and clarifications related to the safety injection 6.3.2.1.4.4, 6.3.2.1.4.5, 6.3.2.1.4.6, 6.3.2.1.5, system.

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]

Table 1.3-2, 3.1.36.2, Table 3.9-1, 3.11.22, Incorporated technical and editorial corrections 3A.1.2, 6.2.2.2, 6.2.2.2.2, 6.2.2.2.3, 6.2.2.2.4, and clarifications related to the recirculation 6.2.2.3.2.1, 6.2.2.3.2.6, 6.2.2.4.2, 6.2.3.1.1, spray system.

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]

Tables 1.3-8, 1.3-9, & 1.3-10, 3.1.55.2, 5.2.4.2, Incorporated technical and editorial corrections 7.7.1.12.2, 9.3.2.1.3, 11.2.3, 11.4.1, 11.4.2, and clarifications related to the radiation 11.4.2.1, 11.4.2.13, 11.4.2.14, 11.4.2.14.1, monitoring system.

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]

Table 1.3-12, 11.3.5.1, Table 11.3-1, 11C.4.1.5 Revised the catalytic hydrogen recombiner

[FN 95-031] description to reflect that it is no longer used.

Revision 5209/29/2016 NAPS UFSAR 69 Revision 3509/01/99 (continued)

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

2.1.3.4, 2.4.13.4, 3.1.52.2, 3A.4, 3A.21, Incorporated technical and editorial corrections 3A.111, 3A.113, 11.1, 11.1.1.3, 11.1.1.4, and clarifications related to the radiation Tables 11.1-7, 11.1-9, 11.1-11, & 11.1-12, protection system.

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, 12.1.2.11, 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]

Table 2.2-3, 6.4.1.3.3, Table 6.4-1 Updated the descriptions and of potentially

[FN 99-015] hazardous chemicals found on-site 2.3.1.1, 2.3.2.1, Figure 2.3-23, 3.10.1, 3.11.2.8, Corrected cross-references, typographical 3A.32, 3A TOC, 3F.4, Table 3F-8, 5.6.2.1, errors, and electronic scanning discrepancies; 6.2.2.2, Figure 6.2-65, 7.9 References, Tables improved consistency of upper and lower case 8.3-6 & 7, Table 9.2-3, 11.1.1.3, 15.1.2.3, and listing notation; and incorporated a title 17.2.16.2 change.

[FN 98-060]

2.3.5.1, 3.1.3.2, Table 3C-3, Figure 5.2-13, Incorporated technical and editorial corrections 9.5.10.3, 11.3.2, 11.3.3, 11.3.3.2, 11.3.5.2, and clarifications related to the gaseous waste 11.3.5.3, 11.3.5.6, 11.3.5.10, Table 11.3-1, system.

Figure 11.3-1, 11.4.4.2, Table 11.4-1, 12.2.4, 15.4.7.2.4.2

[FN 99-028]

2A.2.3.1, 2A.2.3.2, 2A.2.3.3, 2A.2.4.1.1, Corrected text cross-references.

2A.2.4.1.3, 2A.2.5.1, 2A.2.8

[FN 99-050]

Revision 5209/29/2016 NAPS UFSAR 70 Revision 3509/01/99 (continued)

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

3.1, 3.1.11.2, 3.1.16.2, 3.1.17.2, 3.1.20.2, Incorporated technical and editorial corrections Table 3.11-2, 4.3.1.7, 7.1.1, 7.1.3.2.3, and clarifications related to the reactor 7.1.3.3.1.2, 7.1.3.3.3, 7.1.4, 7.1 Refs, protection system.

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, 7.3.2.1.5.11, 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]

3.1.9.2, 3.1.26.2, 3A.2, 5.1, 5.1.1.9, 5.1.2.1, Incorporated technical and editorial corrections 5.1.2.1.1, 5.1.2.1.2, 5.1.2.1.3, 5.1.2.2, 5.1.2.3, and clarifications related to the Reactor 5.1.2.4, 5.1.3.1, 5.1.3.3, 5.1 Ref Dwgs, Coolant System.

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]

3.1.53.2, 9.1.1, 9.1 Refs Added clarification that criticality monitors are

[FN 97-060] 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, Corrected errors associated with table App. 3E Att. 4, App. 3E Att. 5, 5.5.9.3.1, formatting, text cross-references, typographical 5.5.9.3.2, 9.2.1.4.1, Table 9.3-7, Table 10.4-2. entries, implementation of a previous update,

[FN 99-038] and punctuation.

3.8.2.7.6.2.4, Table 3.8-11 Clarified the description of unqualified

[FN 98-053] coatings in containment.

Revision 5209/29/2016 NAPS UFSAR 71 Revision 3509/01/99 (continued)

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

3.8.4.7.7, 3.8.4.8, 3.8 Refs, Table 3.8-17, Incorporated new piezometers locations and Figures 3.8-32, 3.8-33, and 3.8-61 editorial corrections.

[FN 97-053]

Table 3.8-12, Figure 3.8-24 Updated the locations of piezometers at the

[FN 98-051] main dam.

Table 3.8-14 Corrected the factors of safety applicable to the

[FN 97-041] service water reservoir dikes.

Table 3.11-2, 6.2.2.3, Table 6.2-37, 6.3.3.12, Corrected spelling and typographical errors, 6.4.1.3.3, Table 6.4-1, 7.2.2.1.2, 7.2.2.1.2.1, eliminated duplicate phrases, updated text Table 11.1-11, 11.2.8, 11B.2.1, 11B.2.2, 11B.4, figure references, corrected punctuation, 11B.4.1.1, 11B.4.1.4, 11B.4.2.2, Tables 11B-4, spelled out a non-standard acronym, 11B-6, & 11B-7, 12.1.2.11 standardized a system title, and capitalized the

[FN 99-022] titles of computer codes.

3A, 7.4, 8.1, 8.3, 9.5, 14.1 Incorporated technical and editorial corrections

[FN 98-045] and clarifications related to the Emergency Diesel Generator System.

3A.22, 4.4.5.1, 4.4.5.2, Figures 4.4-20 Incorporated technical and editorial corrections and 4.4-21, 7.1, 7.2.3.4, Figure 7.2-5, and clarifications related to the nuclear 7.3.2.1.5.10, Figure 7.3-9 instrumentation system.

[FN 99-024]

3C.1.1, 3C.2.7, 3C.2.7.1, 3C.5.1.2.2, Reduced the number of weld inspections 3C.5.1.8.2, 3C.5.2.8.2, 3C Refs required to be performed on high energy piping

[FN 96-007] 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 Incorporated changes to reflect removal of the

[FN 98-041] Unit 2 part-length control rod drive mechanisms.

4.3.2.2.6, 4.3.2.7, 4.3 Refs Reflected changes to reload design

[FN 96-046] calculations, corrected a reference, and correctly stated initial fuel enrichment.

Figures 4.4-20 and 4.4-21 Modified the figure description of the incore

[FN 97-030] thermocouples.

Revision 5209/29/2016 NAPS UFSAR 72 Revision 3509/01/99 (continued)

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

5.2.1.1, 5.2.1.2, 5.2.2.1, 5.2.2.2, 5.2.2.4, Incorporated technical and editorial corrections 5.2.3.1, 5.2.3.1.1, 5.2.3.1.2, 5.2.3.1.3, 5.2.3.1.4, and clarifications related to the Reactor 5.2.3.1.5, 5.2.3.1.6, 5.2.3.1.7, 5.2.3.1.8, Coolant System.

5.2.3.1.9, 5.2.3.1.10, 5.2.3.1.11, 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]

5.4.2, 5.4.3.6, 5.4.3.6.1, 5.4.3.6.2, 5.4.3.6.3.1, Incorporated technical and editorial corrections 5.4.3.6.3.2, 5.4.3.7, 5.4 References, and clarifications related to the Reactor Table 5.4-1, Figure 5.4-4, 5.5.1.3.1, 5.5.1.3.3, Coolant System.

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]

5.5.1.3.4 Clarified reactor coolant pump bearing

[FN 96-090] 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 Removed the description of automatic closure

[FN 97-023] of RHR MOVs.

5.5.8.2, 5.5.8.3 Added a description of the surveillance criteria

[FN 95-032] and function of the nitrogen reserve tanks for the pressurizer power-operated relief valves.

[10 CFR 50.90 License Amendment]

5.5.8.2 Revised the description of the function of the

[FN 97-012] pressurizer power-operated relief valve nitrogen reserve tanks.

5.5.9.3.3, Figures 5.5-16, 5.5-17, & 5.5-18 Removed vendor specific information from the

[FN 97-038] description of snubbers.

6.2.1.4.3 Revised the description of the Type B test

[FN 97-028] equipment, deleted a reference to Type C penetrations, and incorporated editorial changes.

6.2.2.2.5, Table 9.2-3 Revised the chloride concentration in the

[FN 96-059] Service Water Reservoir and corrected a reference in the text.

Revision 5209/29/2016 NAPS UFSAR 73 Revision 3509/01/99 (continued)

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

6.2.2.2 Clarified encapsulation of insulation inside

[FN 98-055] containment.

6.2.4.2 Corrected the description of the hydrogen

[FN 99-036] recombiner suction piping connection.

6.2.6.3 Reverted the description of containment

[FN 92-161A] vacuum pumps to wording from the original FSAR.

Table 6.2-54 Revised the description of the outside

[FN 97-035] recirculation spray containment penetrations.

6.3.2.1.1 Added clarification on the applicability of the

[FN 99-007] minimum boron concentration requirement to the SI piping.

6.3.2.1.1, Table 6.3-4 Incorporated changes to the safety injection

[FN 97-043] 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 Incorporated revised ECCS analyses.

[FN 97-007 & FN 97-007A]

6.3.2.1.4.1, 6.3 Refs Added a description of design features that

[FN 96-089] prevent valve-bonnet pressure locking of containment sump isolation valves and added a reference to Generic Letter 95-07.

6.3.3.1.4 Incorporated clarification to the effect of LHSI

[FN 97-013] valve misfunction on ECCS flow discussion.

6.3.4.4 Reverted description of routine periodic testing

[FN 92-125A] of ECCS components to that which preceded the present wording supported by an inadequate safety evaluation.

6.3.5.2.3 Added description of pressure taps for

[FN 97-026] checking proper seating of the Unit 1 accumulator check valves.

6.3.5.2.3 Changed the description of provisions for

[FN 97-027] testing accumulator check valve seating to pressure taps from pressure indicators.

Tables 6.3-1 & 5 Reverted description of accumulator minimum

[FN 92-127A] pressure to that which preceded the present value supported by an inadequate safety evaluation.

Revision 5209/29/2016 NAPS UFSAR 74 Revision 3509/01/99 (continued)

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

Table 6.3-5, 8.3.1.1.1 Updated to reflect new charging pump

[FN 96-017] interlocks.

6.4.1.2 Added requirements if the fuel pit bridge

[FN 97-058] radiation monitor is out of service.

6A.3.2, 12.1.2.10, 15.4.1.7, 15.4.1.7.2, Revised the control whole body dose resulting Table 15.4-7 from a LOCA.

[FN 98-056]

7.1, 7.2.1, 7.2 Refs, 7.3.1.3.2, 7.3.1.3.5, Incorporated clarifications and editorial 7.3.1.3.5.4, 7.3 Refs corrections and added a reference to the

[FN 99-006] instrumentation section.

Table 7.2-2 Corrected the reactor trip system over

[FN 99-029] temperature delta T range description.

8.1.2, 8.3.2.1, 8.3.2.2.4 Revised the description of the role of the

[FN 95-039] station battery swing chargers.

8.3.1.1.2.1 Revised the description of the emergency diesel

[FN 98-023] generator operation during transients or disconnection. [10 CFR 50.90 License Amendment]

8.3.1.1.2.6 Added a description of the long term tests

[FN 96-053] results on Dow Corning foam and eliminated the required testing of penetrations sealed with this foam.

8.3.2.1, 8.3.2.2.2, 8.3.2.2.3 Incorporated technical and editorial corrections

[FN 99-031] and clarifications related to the 125V dc (emergency diesel) system.

9.1.1 Revised the description of new fuel container

[FN 96-064] 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 Provided for moving the spent fuel pool gates

[FN 97-002] over irradiated fuel in accordance with Technical Specifications. [10 CFR 50.90 License Amendment]

9.1.3.1 Clarified the seismic classification and

[FN 98-039] associated contingency actions for refueling purification piping and equipment.

9.1.3.2 Added a description of the administrative

[FN 96-043] controls for isolation of the non-seismic portions of the refueling purification system.

Revision 5209/29/2016 NAPS UFSAR 75 Revision 3509/01/99 (continued)

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

9.1.4.4.4 Added a description of the manipulator crane

[FN 96-014] in-mast sipping system.

Figure 9.1-9 Changed the fuel transfer system drive to cable

[FN 96-048] from an air motor.

9.2.1.2.2 Added an analysis of the impact of

[FN 96-076A] accumulation of organic matter in the Service Water Reservoir.

9.2.1.2.4, 9.2.1.3, Table 9.2-4 Added the performance specifications for new

[FN 96-023] service water pumps and clarified NPSH requirements.

9.2.1.3.1 Clarified the description of isolation of service

[FN 96-067] water flow to the containment recirculation air cooling coils in the event of loss of instrument air.

9.2.1.5 Revised the description of the corrosion

[FN 97-015] coupons in the service water piping.

9.2.2.5.1 Revised the description of how the component

[FN 97-008] 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 Revised the description of the water treatment

[FN 94-053] system to say that the flash evaporator is obsolete and no longer used.

Table 9.2-5 Revised the component cooling heat exchanger

[FN 97-025] tube material description.

9.3.1.2 Enhanced the description of the operation of

[FN 97-017] the instrument air compressors regarding in-service and standby lineups and staggered setpoints.

9.3.2.2.1, 9.3.2.2.2.6 Added a description of high radiation sampling

[FN 96-071] system, post-accident required sample times.

9.3.2.2.2 Revised the description of the high radiation

[FN 97-019] 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, Added descriptions of hydrogen peroxide user 9.3.4.3.2 during refueling shutdown, clarified the

[FN 97-047] potential effects of demineralizer overheating, and incorporated editorial changes.

Revision 5209/29/2016 NAPS UFSAR 76 Revision 3509/01/99 (continued)

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

9.3.4.2.4.11 Added a description of hydrogen-form cation

[FN 98-022] resin use in mixed-bed demineralizers.

9.3.4.2.4.21.6 Revised the description of the capacity of the

[FN 96-083] seal-water return line relief valve.

9.4.4.2 Allowed blocking Turbine Building grating

[FN 97-006] ventilation path provided compensatory actions are in place to monitor temperature.

9.4.5.1, 9.4.5.5 Added a description of when the Fuel Building

[FN 96-063] ventilation system can be secured.

9.5.1.2.3 Corrected the heat detector temperature rating

[FN 98-058] for the main and station service transformers.

10.2 Revised the throttle and governor valve stem

[FN 99-019] freedom test frequency in accordance with Tech Spec Amend 210/191. [10 CFR 50.90 License Amendment]

10.3.2, 10.3.3, 10.3.4, 15.4.3.2.2 Added descriptions of atmospheric steam dump

[FN 98-004] valve use during steam generator tube rupture events and revised the valve description.

10.3.2 Revised the normal relieving pressure of the

[FN 97-014] atmospheric steam dump valves.

10.4.3.3.1 Removed the auxiliary feedwater system from

[FN 98-052] the 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 Revised the volume control tank analysis of

[FN 99-011] effects and consequences.

11.3.2, 11.3.3, 11.3.3.2, 11.3.5.2 Revised the gaseous waste system description

[FN 97-036] to reflect that the 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 Corrected errors introduced in a previously

[FN 92-094A] implemented change package.

11.4.3.1.1 Corrected the calibration sources used for

[FN 97-022] effluent gas monitors.

Revision 5209/29/2016 NAPS UFSAR 77 Revision 3509/01/99 (continued)

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

15.1.6, Table 15.1-2, Figure 15.1-3 Updated the Doppler reactivity coefficients to

[FN 99-040] be consistent with the accident analysis basis.

15.1.6, Table 15.1-2, 15.2.2.1, 15.2.2.2.1, Updated the results for the transient analysis of 15.2.2.2.2, 15.2.2.4, Table 15.2-1, the uncontrolled rod cluster control assembly Figures 15.2-6 through 15.2-13 withdrawal at power (RWAP) accident.

[FN 99-034]

15.1.2.3, Table 15.1-3 Added current trip setpoint and response time

[FN 95-044] 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, Revised the description of the uncontrolled rod 15.2.4.1, 15.2.4.2.1, 15.2.4.2.2, 15.2.4.2.3, withdrawal from subcritical and uncontrolled Table 15.2-1, Figures 15.2-1 through 15.2-5 boron dilution transients to reflect current

[FN 97-037] analyses of record. [10 CFR 50.90 License Amendment]

15.2.1.1 Revised the description of the setpoint for the

[FN 97-051] intermediate range high neutron flux reactor trip.

15.2.6.1.2 Modified the description of the loop stop valve

[FN 96-062] 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 Incorporated the results of a sensitivity analysis

[FN 99-039] 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, Reflected the current analysis of record for a 15.4.7.2.4.4, Tables 15.4-16 thru 15.4.18 fuel handling accident inside containment

[FN 98-048] regarding containment purge, exhaust valve closure times, and radiation detector response times.

17.2.2.5 Clarified the qualification requirements of key

[FN 98-059] Nuclear Oversight personnel.

Table 17.2-0 Revised the description to indicate the both

[FN 98-047] Innsbrook record vaults meet ANSI requirements.

Revision 5209/29/2016 NAPS UFSAR 78 Revision 349/01/98 Changes Made under the provisions of 10 CFR 50.59 except Section where indicated in brackets.

KWI, 1.5.2.1, 1.6, 2.5.2.5, 3.1.37.2, 3.1.43.2, Corrected references and typographical errors, 3.8.2.1.4.1, Figures 3E-18 thru 3E-24, 4.3.2.7, and clarified word spelling and illegible text.

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]

1.2.6, 9.1, App. 9B & App. 15A Updated descriptions of cask loading and

[FN 98-014] 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 offsite dose estimate for TN-32 cask drop.

1.3.1 & Table 1.3-7 Added statements to clarify applicability of

[FN 97-054] turbine-driven AFW pump auto-start data.

Figure 2.1-3 Added ISFSI to site boundary and unrestricted

[FN 98-020] areas map.

Table 2.4-7, 9.2.3.2.1, 10.4.2.2 Added raw lake water pumping system that

[FN 95-059] 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, Incorporated technical and editorial corrections 3.11.2.1, 3.11 Refs, Table 3C-3, 6.2.2.2, and clarifications related to the Quench Spray 6.2.2.3.2.1, 6.2.2.4.1, 6.2.2.5.1, 6.2.3.4, System.

Tables 6.2-40 & 6.2-42, Figure 6.3-8

[FN 97-057]

3.1.40.2, 3.1.42.1, & 3.1.42.2 Added AFW system to GDC 44, 45, and 46

[FN 97-054] 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, Updated containment analysis to reflect revised 6.2.2.3.2, 6.2.2.3.2.1, 6.2.2.3.2.6, 6.2.2.3.2.8, flowrates for QS, IRS, ORS, and SW.

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]

3.8.4.5.4.6 Updated service water pump tilt measurement

[FN 98-030] methodology.

3.11.3 Clarified description of the cathodic protection

[FN 97-046] system for underground piping.

Revision 5209/29/2016 NAPS UFSAR 79 Revision 349/01/98 (continued)

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

3.C.5.3, Table 3C-2, 9.2.3.2.2, 10.4.6.2, Added high-capacity steam generator Figures 11.2-3 & 11.2-4, 11.3.5.9, Table 11.4-1, blowdown system.

15.4.3.1

[FN 95-009]

6.2.1.3.1.2, 6.2.2.2, 6.2.3.3, 6.2.3.1.1, Revised quench spray start times and annotated Tables 6.2-44 & 6.3-9 derivative information.

[FN 98-001]

6.2.1.3.1.2, Table 6.2-18, & Table 10.4-4 Clarified AFW pump flow sensitivity analysis.

[FN 97-056]

6.2.3.1, 6.2.3.1.1, 6.2.3.3, 6.2 References Incorporated updated LOCA dose calculations.

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]

6.2.3.1.1 Revised post-LOCA containment sump pH.

[FN 97-061]

6.2.4.2, 6.2 References, Table 6.2-37 Provided for partial draining of several

[FN 97-039] containment penetrations which are isolated during normal power operation.

6.2.5.3, 6.2 Refs, Tables 6.2-66 & 6.2-71, Revised calculation of post-LOCA containment Figures 6.2-98 thru 6.2-111 hydrogen concentration.

[FN 96-008]

7.2.1.1.5, 7.2.1.1.6, 7.2.2.3.5, 7.7.1.14, 7.7 Refs Clarified design and licensing basis for

[FN 98-019] AMSAC C-20 arming setpoint.

7.2.2.2.1.7 Revised testing sequence for reactor trip

[FN 98-005] breakers and reactor trip bypass breakers.

[10 CFR 50.90 License Amendment]

7.2.2.3.4, Figure 7.2-11 Updated description of pressurizer water level

[FN 97-021] measurement system.

7.3 & 10.4 Reformatted mark numbers throughout to

[FN 97-054] conform with standard format (system-component-id).

7.3.1.3.5.3 Expanded discussion about motor-driven AFW

[FN 97-054] pump interlocks and turbine-driven AFW pump interlocks. Changed AFW MOV pushbutton to switch.

Revision 5209/29/2016 NAPS UFSAR 80 Revision 349/01/98 (continued)

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

7.3.1.3.5.3 Rewrote description of AFW autostart

[FN 97-054] interlocks. Rewrote description of Control Room AFW flow indication qualifications.

7.6.7 Clarified pressurizer relief valve flow

[FN 96-002] indication environmental and seismic qualification.

8.3.1.1.1 Corrected typographical errors.

[FN 96-070]

9.1.3.1 & 9.1.3.3 Added case for full core offload, demonstrating

[FN 96-050] 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 Deleted references to the charging pump seal

[FN 96-092] coolers that were removed from the Service Water system.

9.2.1.4.1 Incorporated provision for the use of high

[FN 98-011] corrosion resistant alloy steel in Service Water piping of ten-inch diameter and smaller.

9.2.2.3 Updated component cooling chemistry

[FN 98-027] specifications for chromate concentration and pH.

9.3.4.2.4.1 Deleted description that charging pump seals

[FN 98-034] have leakoffs to collect seal leakage before it can leak to the atmosphere.

9.3.4.2.5.2 Clarified acceptable methods for adding boron

[FN 97-004] to the reactor coolant system.

9.5.1.2 Added reference to fire protection system

[FN 97-054] connections in description of feedwater system.

9.6 Included the Fuel Building Trolley in the

[FN 98-029] NUREG-0612 Heavy Loads Program.

10.2.1.1.2 Added new section on the effect of extending

[FN 97-049] turbine throttle and governor valve test interval.

[10 CFR 50.90 License Amendment]

10.4.3.1 Updated referenced BTP to Auxiliary System

[FN 97-054] Branch (ASB). Deleted statement specifying Terry Turbine nominal speed.

Revision 5209/29/2016 NAPS UFSAR 81 Revision 349/01/98 (continued)

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

10.4.3.2 Clarified discussion of SG water level

[FN 97-054] management when there is a leaky SG tube.

Corrected description of SOV redundant power source. Corrected reference to PCV air line/air storage descriptions. Corrected mark numbers and clarified that discussion applies to normal lineup. Rewrote to explain intent behind design of time delays.

10.4.3.3 Clarified coincidence and actuations of

[FN 97-054] 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. Clarified suction line pressure transmitter function. Clarified statement regarding conditions 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 Deleted discussion of vital bus diversity.

[FN 97-054]

Table 10.4-3 Clarified peak reactor coolant system pressure

[FN 97-054] criterion.

Table 10.4-4 Corrected initial SG inventories. Corrected

[FN 97-054] main steam line break reference for decay heat.

Added clarification footnote to main steam line break reference for AFW pump design pressure.

Table 12.1-4 Changed an area radiation monitor location and

[FN 98-018] range.

13.1.1.2.1, 17.2, & KWI Updated Station Manager title to Site Vice

[FN 98-008] President and Assistant Station Managers titles to Manager-Station O&M and Manager-Station S&L. [10 CFR 50.90 License Amendment]

Revision 5209/29/2016 NAPS UFSAR 82 Revision 349/01/98 (continued)

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

15.1.2.2 Reflected revised safety analyses that support

[FN 95-055] an increased Reactor Coolant System total flow rate. [10 CFR 50.90 License Amendment]

15.1.4 & Table 15.1-4 Clarified the assumed calorimetric error in core

[FN 98-024] thermal power determination from secondary plant measurements.

15.2.8.1 Deleted parenthetical statement of

[FN 97-054] turbine-driven AFW pump capacity. Deleted outdated statement related to AFW pump capacity determination.

15.2.10 Updated feedwater temperature reduction event

[FN 98-015] description.

15A, TOC Clarified spent fuel cask lift height restrictions.

[FN 98-028]

16.2 Included the Technical Requirements Manual

[FN 98-040] (TRM) in the UFSAR by listing the technical requirements.

17.2.1.2.B.1 Identified the Site Vice President as the station

[FN 98-037] position fulfilling the Plant Manager position identified in the ISFSI Technical Specifications.

17.2.3 Revised to reflect replacement of A/E

[FN 98-021] Instruction Manual with an Engineering Standard.

Revision 3303/31/98 Section Changes 17.2, 17.2.1.2, 17.2.2.1, 17.2.3, 17.2.4, 17.2.5, Deleted reference to the Nuclear Operations Figure 17.2.1-1, & Table 17.2-0 Department Standards and replace with

[FN 97-029] Nuclear Business Unit Standard. Added position of Project Manager (Configuration Management).

17.2.1.1 and 17.2.1.2 Clarified organizational position descriptions

[FN 98-010] by noting responsibilities for the ISFSI as they already exist.

Revision 5209/29/2016 NAPS UFSAR 83 Revision 3303/31/98 (continued)

Section Changes 17.2.1.2, Figures 17.2.1-2 & 17.2.1-3 Deleted the position of Supervisor

[FN 98-013] Administrative Services in the Nuclear Management organization and assigned duties and responsibilities to other positions.

17.2.2.6 and 17.2.2.8 Provided clarification of Quality Inspection

[FN 97-048] Coordinator qualifications.

17.2.17, Tables 17.2-2 & 17.2-3 Added Generic Letter 88-18 commitment

[FN 97-044] regarding storage of quality assurance records on optical disk media.

Table 17.2.0 Added provision for storage of quality

[FN 96-069] assurance records in an approved offsite facility.

Table 17.2-0 Provided an additional alternative to

[FN 97-052] ANSI/ANS 3.1.

Tables 17.2-2 & 17.2-3 Clarified the description of onsite and offsite

[FN 98-016] nuclear safety review committees.

Revision 3202/11/98 Section Changes Foreword Updated to reflect recent NRC initiatives

[FN 96-055] regarding UFSAR submittal requirements, and adequacy and consistency of design basis information; and to note Virginia Powers adoption of electronic methods to enhance UFSAR maintenance, and UFSAR distribution in both hardcopy and electronic media.

Tables 3.9-1 & 3.9-2 Updated to reflect current plant configuration.

[FN 97-042]

3.10.2 & 3.10.3 Deleted references to Virginia Power

[FN 96-049] Engineering standards STD-CEN-0020, STD-CEN-0026, and STD-GN-0038 4.1 Revised to indicate that fuel assemblies may be

[FN 96-051] used that differ from those described in the UFSARwith an NRC-approved exemption or license condition.

4.2.3 Revised to reflect removal of secondary

[FN 97-032] neutron sources starting with the Unit 1 Cycle 13 reload core; secondary source replacement in future reloads is optional.

Revision 5209/29/2016 NAPS UFSAR 84 Revision 3202/11/98 (continued)

Section Changes 5.2.4.1.1 Eliminated seismic qualification requirements

[FN 96-061] for the Containment Gaseous and Particulate Radiation Monitoring System. Added procedural requirements for system operability verification after a seismic event.

6.2.1.2.18 New section to describe lead blanket shielding

[FN 96-027] storage boxes, explain why they are not designated Seismic Category I, and provide references to drawings that depict storage box locations.

7.2.2.2.1.7 Revised reactor trip breaker test procedure.

[FN 96-084]

7.2.2.3.5 Added discussion of IEEE-279 control and

[FN 92-005] protection interaction criteria as they apply to steam generator low level/high steam-feed flow mismatch trip channels.

8.3.1.1 Clarified the C containment air recirculation

[FN 97-001] cooler fans operating description.

9.3.4.2.2.3 Clarified that the mixed-bed demineralizer may

[FN 96-065] be removed from service if primary coolant activity is within normal limits.

9.5.3 Added High Pressure Sodium among types of

[FN 96-036] non-containment normal lighting.

9.5.4.2 Revised duration of full-load operation with

[FN 97-018] minimum allowed day tank inventory.

13.7 Deleted references to Regulatory Guide 1.17

[FN 97-003] and Section 2.790. Added references to 10 CFR 73, Sections 21, 55, 56, 57, and Appendices B & C.

15.2.12 Revised to reflect reanalysis to support Virginia

[FN 96-034] Powers Accident Analysis Design Basis Document project.

15.2.14 Revised to reflect the results of an extended

[FN 96-005] Virginia Power evaluation of the Spurious Operation of the Safety Injection System at Power event.

15.4.3.1 Deleted paragraphs that referred to the

[FN 97-011] configuration of steam generators just before the repair project that included replacement of the tube bundles.

Revision 5209/29/2016 NAPS UFSAR 85 Revision 3202/11/98 (continued)

Section Changes Table 17.2.0 Deleted reference to the Surry Training Center

[FN 96-060] records vault.

Tables 17.2-2 & 17.2-3 Corrected typos.

[FN 97-045] Clarified record retention requirements.

All

• Consolidated 17 volumes to 8 volumes (no change bars)

• Referenced Station Drawings previously

[FN 96-055 & FN 96-056] included in UFSAR; inserted simplified diagrams

• Removed notations associated with previously deleted material and renumbered sequentially

• Renumbered previously inserted items that had suffixes (e.g., 4A, 4B)

• Applied consistent typeface and page layouts

• Improved consistency of measurement notation (e.g., time, mass, velocity),

including abbreviations

Revision 5209/29/2016 NAPS UFSAR 86 Intentionally Blank

Volume I Assignment Sheet General Table of Contents Revision 5209/29/2016 NAPS UFSAR TOC-i North Anna Power Station Updated Final Safety Analysis Report Table of Contents Section Title Page VOLUME I Assignment Sheet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . TOC-i General Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . TOC-i Foreword . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 List of Effective Pages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . LEP-1 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 1.1-1 1.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.2 General Plant Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.2-1 1.3 Comparison Tables. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.3-1 1.4 Identification of Agents and Contractors . . . . . . . . . . . . . . . . . . 1.4-1 1.5 Requirements for Further Technical Information. . . . . . . . . . . . 1.5-1 1.6 General ReferencesWestinghouse Topical Reports . . . . . . . . 1.6-1 CHAPTER 2 SITE CHARACTERISTICS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-1 2.1 Geography and Demography . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-1 2.2 Nearby Industrial, Transportation, and Military Facilities. . . . . 2.2-1 2.3 Meteorology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1 2.4 Hydrology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.5 Geology and Seismology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 Appendix 2A Revised Analysis, Probable Maximum Flood, North Anna Units 1 and 2, Virginia Electric and Power Company June 18, 1976 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-i 2A.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-1 2A.2 Flood Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-1 2A.3 Safety Implications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-9 2A.4 Corrective Action Implemented . . . . . . . . . . . . . . . . . . . . . . . . . 2A-10 2A.5 Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2A-10

Revision 5209/29/2016 NAPS UFSAR TOC-ii North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page Appendix 2B Seismic 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 2C Report on Foundation Studies for the Proposed North Anna Power Station in Louisa County, Virginia . 2C-i VOLUME II CHAPTER 3 DESIGN CRITERIA - STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1 3.1 Conformance with Atomic Energy Commission (AEC)

General Design Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1 3.2 Classification of Structures, Components, and Systems . . . . . . 3.2-1 3.3 Wind and Tornado Design Criteria . . . . . . . . . . . . . . . . . . . . . . 3.3-1 3.4 Water Level (Flood) Design Criteria . . . . . . . . . . . . . . . . . . . . . 3.4-1 3.5 Missile Protection Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-1 3.6 Criteria for Protection Against Dynamic Effects Associated with a Loss-of-Coolant Accident . . . . . . . . . . . . . . . 3.6-1 3.7 Seismic Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.7-1 3.8 Design of Seismic Class I Structures . . . . . . . . . . . . . . . . . . . . . 3.8-1 3.9 Mechanical Systems and Components . . . . . . . . . . . . . . . . . . . . 3.9-1 3.10 Seismic Design of Class I Instrumentation and Electrical Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.10-1 3.11 Environmental Design of Mechanical and Electrical Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.11-1 VOLUME III Appendix 3A Compliance with Safety Guides . . . . . . . . . . . . . . . . . . . 3A-i 3A.1 Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps (Safety Guide No. 1) 3A-1

Revision 5209/29/2016 NAPS UFSAR TOC-iii North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page 3A.2 Thermal Shock to Reactor Pressure Vessels (Safety Guide No. 2). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-2 3A.3 Assumptions Used for Evaluating the Potential Radiological Consequences of a LOCA for Boiling Water Reactors (Safety Guide No. 3) . . . . . 3A-3 3A.4 Assumptions Used for Evaluating the Potential Radiological Consequences of a LOCA for Pressurized Water Reactors (Safety Guide No. 4) . . 3A-3 3A.5 Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam-Line Break for Boiling Water Reactors (Safety Guide No. 5). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-3 3A.6 Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide No. 6) . . . . 3A-4 3A.7 Personnel Selection and Training (Safety Guide No. 8) . . . . . . 3A-4 3A.8 Selection of Diesel-Generator Set Capacity for Standby Power Sources (Safety Guide No. 9). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-4 3A.9 Mechanical (Cadweld) Splices in Reinforcing Bars of Concrete Containments (Safety Guide No. 10) . . . . . . . . . . . . . . . . . . . . . 3A-5 3A.10 Instrument Lines Penetrating Primary Reactor Containment (Safety Guide No. 11) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-6 3A.11 Nuclear Power Plant Instrumentation for Earthquakes (Regulatory Guide 1.12) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-7 3A.12 Fuel Storage Facility Design Basis (Safety Guide No. 13) . . . . 3A-7 3A.13 Reactor Coolant Pump Flywheel Integrity (Safety Guide No. 14) 3A-7 3A.14 Testing of Reinforcing Bars for Concrete Structures (Safety Guide No. 15). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-8 3A.15 Reporting of Operating Information. . . . . . . . . . . . . . . . . . . . . . 3A-8 3A.16 Protection Against Industrial Sabotage (Safety Guide No. 17) . 3A-8 3A.17 Structural Acceptance Test for Concrete Primary Reactor Containment (Safety Guide No. 18). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-9 3A.18 Nondestructive Examination of Primary Containment Liners (Safety Guide No. 19) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-10

Revision 5209/29/2016 NAPS UFSAR TOC-iv North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page 3A.19 Vibration Measurements on Reactor Internals (Safety Guide No. 20). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-11 3A.20 Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants (Regulatory Guide 1.21, Revision 1) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-11 3A.21 Periodic Testing of Protection System Actuation Functions (Safety Guide No. 22). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-11 3A.22 Onsite Meteorological Programs (Safety Guide No. 23) . . . . . . 3A-12 3A.23 Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Radioactive Gas Storage Tank Failure (Safety Guide No. 24) . . . . . . . . . . . . . . . . . . . . . . 3A-12 3A.24 Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel-Handling Accident in the Fuel Handling and Storage Facility for a Pressurized Water Reactor (Safety Guide No. 25) . . . . . . . . . . . . . . . . . . . . 3A-13 3A.25 Quality Group Classifications and Standards (Safety Guide No. 26). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-13 3A.26 Ultimate Heat Sink (Regulatory Guide 1.27) . . . . . . . . . . . . . . . 3A-13 3A.27 Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electrical Equipment (Regulatory Guide 1.30) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-14 3A.28 Use of IEEE Std. 308-1971, Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations (Regulatory Guide 1.32) . 3A-14 3A.29 Quality Assurance Program Requirements (Operation) (Regulatory Guide 1.33) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-14 3A.30 Preoperational Testing of Redundant On-Site Electric Power Systems to Verify Proper Load Group Assignments (Regulatory Guide 1.41) 3A-14 3A.31 Reactor Coolant Pressure Boundary Leakage Detection Systems (Regulatory Guide 1.45, May 1973). . . . . . . . . . . . . . . . . . . . . . 3A-14 3A.32 Protection Against Pipe Whip Inside Containment (Regulatory Guide 1.46) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-15

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Section Title Page 3A.33 Design Limits and Loading Combinations for Seismic Class I Fluid System Components (Regulatory Guide 1.48). . . . . . . . . . . . . . 3A-18 3A.34 Design, Maintenance, and Testing Criteria for Atmospheric Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants (Regulatory Guide 1.52) . . . . . . . . . . . . . 3A-19 3A.35 Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel (Regulatory Guide 1.58, Revision 1, 1980) . 3A-19 3A.36 Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants (Regulatory Guide 1.63, Revision 2, July 1978) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-19 3A.37 Nondestructive Examination of Tubular Products (Regulatory Guide 1.66). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-20 3A.38 Preoperational and Initial Start-Up Test Programs for Water-Cooled Power Reactors (Regulatory Guide 1.68). . . . . . . . . . . . . . . . . . 3A-22 3A.39 Assumptions for Evaluating the Habitability of a Nuclear Plant Control Room During a Postulated Hazardous Chemical Release (Regulatory Guide 1.78) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-23 3A.40 Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors (Regulatory Guide 1.79) . . . . . . . . 3A-23 3A.41 Preoperational Testing of Instrument Air Systems (Regulatory Guide 1.80) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-24 3A.42 Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release (Regulatory Guide 1.95) . . . . . . . 3A-25 3A.43 Instrumentation for Light-water-cooled Nuclear Power Plants to Access Plant Conditions During and Following an Accident (Regulatory Guide 1.97) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-25 3A.44 Emergency Planning and Preparedness for Nuclear Power Reactors (Regulatory Guide 1.101, November 1975) . . . . . . . . . . . . . . . . 3A-25 3A.45 Periodic 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

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Section Title Page 3A.46 Calculation of Annual Doses to Man 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-25 3A.47 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors (Regulatory Guide 1.111, March 1976) . . . . . . . . . . . 3A-26 3A.48 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors (Regulatory Guide 1.112) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3A-26 3A.49 Inspection of Water-Control Structures Associated with Nuclear Power Plants (Regulatory Guide 1.127) . . . . . . . . . . . . . . . . . . . . . . . . 3A-26 3A.50 Qualification of Quality Assurance Program Audit Personnel of Nuclear Power Plants (Regulatory Guide 1.146, August 1980) . . . . . . . 3A-26 3A.51 Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Post-Earthquake Actions (Regulatory Guide 1.166, March 1997) 3A-26 3A.52 Restart of a Nuclear Power Plant Shut Down By a Seismic Event (Regulatory Guide 1.167, March 1997) . . . . . . . . . . . . . . . . . . . 3A-27 Appendix 3B Comparison Between Time - History and Frequency Response Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3B-i Appendix 3C Effects of Piping System Breaks Outside Containment . 3C-i 3C.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3C-1 3C.2 Criteria for Pipe Breaks and Analysis . . . . . . . . . . . . . . . . . . . . 3C-3 3C.3 High-Energy Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3C-22 3C.4 Plant Shutdown and Equipment Important to Safety . . . . . . . . . 3C-23 3C.5 Effects of Pipe Breaks and Cracks . . . . . . . . . . . . . . . . . . . . . . . 3C-24 3C.6 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3C-40 Appendix 3D Testing of Protective Coatings Under Design Basis Accident Conditions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3D-i Appendix 3E Geotechnical Investigations and Soil Sample Testing for the Service Water Reservoir . . . . . . . . . . . . . . . . . . . . . . . . . 3E-i 3E.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3E-1

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Section Title Page 3E.2 Dike and Foundation Conditions . . . . . . . . . . . . . . . . . . . . . . . . 3E-1 3E.3 Settlement of Pump House for Units 1 and 2 . . . . . . . . . . . . . . . 3E-7 3E.4 Seepage Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3E-12 3E.5 Stability Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3E-13 3E.6 Liquefaction Potential of Foundation Materials. . . . . . . . . . . . . 3E-14 Appendix 3F Safety-Related Equipment Temperature Transients During the Limiting Main Steam Line Break. . . . . . . . . 3F-i 3F.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3F-1 3F.2 Calculational Model . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3F-4 3F.3 Safety-Related Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3F-4 3F.4 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3F-6 VOLUME IV CHAPTER 4 REACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1 Summary Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1 4.2 Mechanical Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.2-1 4.3 Nuclear Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.3-1 4.4 Thermal and Hydraulic Design . . . . . . . . . . . . . . . . . . . . . . . . . 4.4-1 4.5 Advanced Mark-BW Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.5-1 CHAPTER 5 REACTOR COOLANT SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1-1 5.1 Summary Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1-1 5.2 Integrity of the Reactor Coolant System Boundary . . . . . . . . . . 5.2-1 5.3 Thermal-Hydraulic System Design . . . . . . . . . . . . . . . . . . . . . . 5.3-1 5.4 Reactor Vessel and Appurtenances . . . . . . . . . . . . . . . . . . . . . . 5.4-1 5.5 Component and Subsystem Design . . . . . . . . . . . . . . . . . . . . . . 5.5-1 5.6 Instrumentation Application. . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.6-1

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Section Title Page Appendix 5A Discussion 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 6 ENGINEERED SAFETY FEATURES . . . . . . . . . . . . . . . . . . . . . . . 6.1-1 6.1 General . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1-1 6.2 Containment Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.2-1 6.3 Emergency Core Cooling System . . . . . . . . . . . . . . . . . . . . . . . 6.3-1 6.4 Habitability Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.4-1 Appendix 6A Single Failure Capability . . . . . . . . . . . . . . . . . . . . . . . . 6A-i 6A.1 Definitions of Terms. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6A-1 6A.2 Active-Failure Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6A-1 6A.3 Passive-Failure Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6A-1 CHAPTER 7 INSTRUMENTATION AND CONTROLS. . . . . . . . . . . . . . . . . . . . 7.1-1 7.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.1-1 7.2 Reactor Trip System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.2-1 7.3 Engineered Safety Features Actuation System. . . . . . . . . . . . . . 7.3-1 7.4 Systems Required for Safe Shutdown . . . . . . . . . . . . . . . . . . . . 7.4-1 7.5 Safety-Related Display Instrumentation. . . . . . . . . . . . . . . . . . . 7.5-1 7.6 All Other Systems Required for Safety . . . . . . . . . . . . . . . . . . . 7.6-1 7.7 Plant Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.7-1 7.8 Emergency Response to Accidents . . . . . . . . . . . . . . . . . . . . . . 7.8-1 7.9 Inadequate Core Cooling Monitor (ICCM) System . . . . . . . . . . 7.9-1 VOLUME VI CHAPTER 8 ELECTRIC POWER SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.1-1 8.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.1-1

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Section Title Page 8.2 Offsite Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.2-1 8.3 Onsite Power Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.3-1 CHAPTER 9 AUXILIARY SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.1-1 9.1 Fuel Handling and Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.1-1 9.2 Water Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.2-1 9.3 Process Auxiliaries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.3-1 9.4 Air-Conditioning, Heating, Cooling, and Ventilation Systems . 9.4-1 9.5 Other Auxiliary Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.5-1 9.6 Control of Heavy Loads . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.6-1 Appendix 9A Structural Analysis of the Spent-Fuel Pool . . . . . . . . . . 9A-i 9A.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-1 9A.2 Description of the Fuel Building . . . . . . . . . . . . . . . . . . . . . . . . 9A-1 9A.3 Description of the Deficiency. . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-2 9A.4 Analysis of Safety Implications . . . . . . . . . . . . . . . . . . . . . . . . . 9A-3 9A.5 Corrective Action Taken . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-3 9A.6 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9A-9 Appendix 9B Fuel Pool Separating Wall Design . . . . . . . . . . . . . . . . . 9B-i 9B.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-1 9B.2 Casks Evaluated . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-1 9B.3 Accidents Considered. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-1 9B.4 Separating Wall Analysis and Design . . . . . . . . . . . . . . . . . . . . 9B-3 9B.5 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9B-6 VOLUME VII CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM. . . . . . . . . . . . . . 10.1-1 10.1 Summary Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.1-1 10.2 Turbine Generator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.2-1

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Section Title Page 10.3 Main Steam System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.3-1 10.4 Other Features of Steam and Power Conversion System. . . . . . 10.4-1 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT. . . . . . . . . . . . . . . . . . . 11.0-1 11.1 Source Terms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.1-1 11.2 Liquid Waste Disposal System. . . . . . . . . . . . . . . . . . . . . . . . . . 11.2-1 11.3 Gaseous Waste Disposal System . . . . . . . . . . . . . . . . . . . . . . . . 11.3-1 11.4 Process and Effluent Radiation Monitoring System . . . . . . . . . 11.4-1 11.5 Solid Waste System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.5-1 11.6 Offsite Radiological Monitoring Program . . . . . . . . . . . . . . . . . 11.6-1 Appendix 11A Tritium Control. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-i 11A.1 System Sources. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-1 11A.2 Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-2 11A.3 Design Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11A-2 Appendix 11B Radiation Exposure Evaluation for Estimated Radioactive Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-i 11B.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-1 11B.2 Summary and Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-1 11B.3 Radiation Exposure from Gaseous Effluents . . . . . . . . . . . . . . . 11B-5 11B.4 Radiation Exposure from Liquid Effluents . . . . . . . . . . . . . . . . 11B-9 11B.5 Dose Totals and Comparison with Federal Regulations and Natural Background. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-14 11B.6 Computational Methods for Doses Resulting from Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-15 11B.7 Computational Methods for Doses Resulting from Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11B-18 Appendix 11C Evaluation of Compliance With Proposed 10 CFR 50, Appendix I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-i 11C.1 Summary and Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-1 11C.2 Doses from Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-3

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Section Title Page 11C.3 Doses from Gaseous Effluents . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-4 11C.4 Data and Methodology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-6 11C.5 Source-Term Information. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11C-17 CHAPTER 12 RADIATION PROTECTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.0-1 12.1 Shielding. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.1-1 12.2 Ventilation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.2-1 12.3 Health Physics Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.3-1 12.4 Radioactive Materials Safety . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.4-1 Appendix 12A Description of Neutron Supplementary Shield. . . . . . . . 12A-i 12A.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12A-2 12A.2 Neutron Shield Design Criteria . . . . . . . . . . . . . . . . . . . . . . . . . 12A-2 12A.3 Effectiveness of the Supplementary Neutron Shield . . . . . . . . . 12A-3 12A.4 Shield Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12A-4 12A.5 Reactor Pressure Vessel Support Integrity Reviews . . . . . . . . . 12A-6 CHAPTER 13 CONDUCT OF OPERATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.1-1 13.1 Organizational Structure of Virginia Electric and Power Company. . . . . . . . . . . . . . . . . . . . 13.1-1 13.2 Training Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.2-1 13.3 Emergency Planning. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.3-1 13.4 Review and Audit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.4-1 13.5 Plant Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.5-1 13.6 Plant Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.6-1 13.7 Industrial Security . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.7-1 CHAPTER 14 INITIAL TESTS AND OPERATION . . . . . . . . . . . . . . . . . . . . . . . . 14.0-1 14.1 Test Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.1-1 14.2 Augmentation of VEPCOs Staff for Initial Test and Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.2-1

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Section Title Page Appendix 14A NRC Questions and VEPCOs Responses Regarding the North Anna Power Station Unit 2 Modified Startup Physics Testing Program . . . . . . . . . . 14A-i VOLUME VIII CHAPTER 15 ACCIDENT ANALYSES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.0-1 15.1 Condition I - Normal Operation and Operational Transients. . . 15.1-1 15.2 Condition II - Faults of Moderate Frequency. . . . . . . . . . . . . . . 15.2-1 15.3 Condition III - Loss-of-Coolant Accident (LOCA) Accidents. . 15.3-1 15.4 Condition IV - Limiting Faults. . . . . . . . . . . . . . . . . . . . . . . . . . 15.4-1 Appendix 15A Spent Fuel Cask Drop Analysis . . . . . . . . . . . . . . . . . . . 15A-i 15A.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-1 15A.2 Arrangement of Spent Fuel Cask Handling System. . . . . . . . . . 15A-1 15A.3 Cask Drop Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-2 CHAPTER 16 TECHNICAL SPECIFICATIONS AND REQUIREMENTS . . . . . 16.1-1 16.1 Safety and Environmental Technical Specifications . . . . . . . . . 16.1-1 16.2 Technical Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16.2-1 CHAPTER 17 QUALITY ASSURANCE PROGRAM . . . . . . . . . . . . . . . . . . . . . . . 17-1 CHAPTER 18 PROGRAMS AND ACTIVITIES THAT MANAGE THE EFFECTS OF AGING . . . . . . . . . . . . . . . . . . . . . . 18-1 18.1 New Aging Management Activities . . . . . . . . . . . . . . . . . . . . . . 18-1 18.2 Existing Aging Management Activities . . . . . . . . . . . . . . . . . . . 18-5 18.3 Time-Limited Aging Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . 18-22 18.4 TLAA Supporting Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-31 18.5 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-33

Revision 5209/29/2016 NAPS UFSAR 1 FOREWORD In the May 9, 1980, edition of the Federal Register (45 FR 30614), the NRC published a Final Rule requiring all licensed reactors to periodically update their Final Safety Analysis Reports. The purpose of the Rule was to establish baseline reference documents to be used in recurring safety analyses by licensees, the NRC, or other interested parties.

The Supplementary Information section of the Final Rule notice stated that submittal of an updated FSAR does not constitute a licensing action, but is only intended to provide information. The NRC Staff may review the material submitted, but does not intend to formally approve it. The NRC intends to use the updated FSAR in the future for appropriate applications such as reporting of deviations from conditions stated in the UFSAR.

The Rule became effective July 22, 1980, and established the following basic requirements for VEPCOs nuclear power stations:

• A complete Updated FSAR (UFSAR) was required as the initial submittal.

• The UFSAR was to reflect information and analyses submitted to the NRC by VEPCO, or prepared by VEPCO pursuant to NRC requirements, since submission of the original FSAR (or, as appropriate, the last UFSAR).

Note: The Supplementary Information section of the Final Rule notice clarifies this requirement by stating that no analyses other than those already prepared or submitted pursuant to NRC requirements are required because of the Rule: however, FSAR analyses that are known to be nonconservative based on new analyses must be updated. Other new analyses not previously included in the FSAR may be incorporated in the UFSAR at the option of the licensee. Furthermore, specialized studies provided in the original FSAR (e.g., seismology, meteorology) should include the latest information developed in response to NRC requirements when these studies are transferred to the UFSAR, and program type material referenced by the UFSAR (e.g., security plan, emergency plan, QA Program) should be referenced accurately. In addition, the level of detail in the UFSAR should be at least the same as but not necessarily greater than that provided in the original FSAR. Information on design changes should not be included until the changes are approved for use and operable.

• The initial UFSAR was due no later than July 22, 1982.

• The initial UFSAR was required to be up-to-date as of a maximum of six months prior to the date of filing (January 31, 1982, was chosen by VEPCO as the cutoff date).

• Subsequent updates are required at least annually and must reflect changes made up to a maximum of six months prior to the date of filing.

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• One original and 12 copies of the initial UFSAR and subsequent updates are required to be submitted to the NRC.

• The updates are required to be certified by a duly authorized officer of VEPCO.

• The initial UFSAR should be a clean document without change bars and revision numbers. The subsequent annual revisions should include change indicators and page change identification.

In response to the foregoing FSAR update requirements, VEPCO and NUS Corporation executed an Agreement for FSAR update services in April 1981, and NUS began work on the project immediately. The project was accomplished in four basic phases:

1. Document Retrieval

2. Change Package Development

3. FSAR Revision

4. Printing

• During the initial document retrieval phase in the Spring of 1981, NUS engineers researched the licensing correspondence files at VEPCO offices in Richmond and the design change files at the plant sites. All documents potentially affecting the FSAR were copied and taken to the NUS home office.

Following the initial document review phase, NUS engineers periodically visited Richmond and the plant sites to acquire newly developed information. NUS was also placed on the distribution list for VEPCO/NRC correspondence.

The document retrieval phase continued until early 1982, at which time sufficient information was available to document changes up to the January 31, 1982, cutoff date.

• The documentation retrieved during the first phase was reviewed in detail during the second phase to determine the particular two-digit section or sections of the FSAR that should be revised, i.e., 1.1, 1.2, 1.3, etc. Copies of the document (or of the particular pages of the document that were of interest) were placed in separate files corresponding to the two-digit sections. These files were defined as change packages. Development of the change packages continued in parallel with the document retrieval phase, with new information being reviewed and assigned to appropriate change packages. The final change packages became a work product delivered to VEPCO on conclusion of the update effort and are available for tracing the sources of changes to the original FSARs.

• After development of the initial change packages the material filed therein was used in the third phase of the project to make the actual FSAR revisions. The revision process continued in parallel with the continuing development of the change packages.

Revision 5209/29/2016 NAPS UFSAR 3 The revision phase for most FSAR chapters included two cycles of VEPCO review and comment. These comments became part of the change packages and were used in the development of the final draft UFSAR.

• VEPCO reviewed and approved the final draft chapters of the UFSARs for printing. The printer prepared approximately 125 sets of the UFSARs. NUS delivered one original and 12 copies of the UFSAR directly to the NRC on July 20, 1982, for Surry and July 22, 1982, for North Anna. The original UFSARs were transmitted under cover letter supplied to NUS by VEPCO (see the attachment to this foreword). The remaining copies were shipped to Richmond and the plant sites.

The following work products were also delivered to VEPCO by NUS and are available for use in producing subsequent annual updates:

• Printers copy of the UFSARs

• Annotated FSARs (2 copies)

• Final Change Packages (2 sets)

• Plant Drawing Indexes

• Key Word Indexes

• IBM Displaywriter Floppy Discs (2 sets each of the FSAR, Annotated FSAR, and Key Word Index)

• Update Procedures

• Introductory Volumes to the FSARs including this foreword, a list of effective pages, the key word indexes, the plant drawing indexes and a record of changes.

Further 10 CFR 50.71(e) rulemaking pertaining to UFSAR requirements for nuclear power stations was promulgated as recently as July 29, 1996 [61 FR 39278]. In particular, the annual revision requirement has been relaxed to six months after each refueling outage provided the interval between successive updates does not exceed 24 months.

The NRC issued a letter to licensees dated October 9, 1996, entitled Request for Information Pursuant to 10 CFR 50.54(f) Regarding Adequacy and Availability of Design Basis Information. The letter required submittal of information that will provide the NRC added confidence and assurance that Virginia Electric and Power Companys nuclear plants are operated and maintained within their design bases and that any deviations are reconciled in a timely manner. The Companys response (Serial No.96-535) dated February 7, 1997, described previously conducted programmatic reviews of the Updated Final Safety Analysis Report (UFSAR). The 1996 UFSAR Project Team examined the existing administrative controls for maintaining UFSAR content and usability. Process enhancements to simplify administrative

Revision 5209/29/2016 NAPS UFSAR 4 controls, to increase accountability for technical content, and to improve UFSAR accessibility and usability are promoted by conversion to electronic media.

Under separate cover (Serial No.97-108) dated May 23, 1997, Virginia Electric and Power Company notified the NRC about its project to address potential regulatory concerns involving the current design and licensing bases for the Surry and North Anna Power Stations. This project scope exceeds the level of scrutiny normally applied to the current licensing basis through routine surveillance and quality assurance activities. In order to facilitate thorough review, exhaustive validation, and a rigorous corrective action process, the recommended conversion to electronic media was implemented in Revision 32 of the North Anna UFSAR. The entire text of the UFSAR was entered into electronic media. The conversion was accomplished by a process of augmenting recent UFSAR revision word processing packages with scanned-in optical character recognition documents for the balance of text, tables, and figures not previously stored electronically. A 100-percent word-for-word proofing was conducted by comparing a printed version of the entire electronic document with current controlled distribution copies. Thus, the electronic UFSAR was conveyed into service as the quality assurance document of record without introducing any substantive, technical, or non-editorial changes.

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Revision 5209/29/2016 NAPS UFSAR LEP-1 LIST OF EFFECTIVE PAGES VOLUME I General Table of Contents (Note: Repeated in each volume)

First Page Last Page Revision TOC-i TOC-xii Revision 5209/29/2016 Foreword First Page Last Page Revision 1 6 Revision 5209/29/2016 List of Effective Pages First Page Last Page Revision LEP-1 LEP-8 Revision 5209/29/2016 Chapter 1 First Page Last Page Revision 1-i 1-iv Revision 5209/29/2016 1.1-1 1.1-2 Revision 5209/29/2016 1.2-1 1.2-14 Revision 5209/29/2016 1.3-1 1.3-24 Revision 5209/29/2016 1.4-1 1.4-10 Revision 5209/29/2016 1.5-1 1.5-26 Revision 5209/29/2016 1.6-1 1.6-4 Revision 5209/29/2016 Chapter 2 First Page Last Page Revision 2-i 2-xii Revision 5209/29/2016 2.1-1 2.1-26 Revision 5209/29/2016 2.2-1 2.2-10 Revision 5209/29/2016 2.3-1 2.3-74 Revision 5209/29/2016 2.4-1 2.4-40 Revision 5209/29/2016 2.5-1 2.5-40 Revision 5209/29/2016 2A-i 2A-ii Revision 5209/29/2016 2A-1 2A-38 Revision 5209/29/2016 2A Att. 1-1 2A Att. 1-22 Revision 5209/29/2016 2A Att. 2-1 2A Att. 2-74 Revision 5209/29/2016 2A Att. 3-1 2A Att. 3-60 Revision 5209/29/2016 2A Att. 4-1 2A Att. 4-48 Revision 5209/29/2016

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Chapter 2 (continued)

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First Page Last Page Revision 3-i 3-xxx Revision 5209/29/2016 3A-i 3A-ii Revision 5209/29/2016 3A-1 3A-30 Revision 5209/29/2016 3B-i 3B-ii Revision 5209/29/2016 3B-1 3B-20 Revision 5209/29/2016 3C-i 3C-ii Revision 5209/29/2016 3C-1 3C-142 Revision 5209/29/2016 3D-i 3D-ii Revision 5209/29/2016 3D-1 3D-232 Revision 5209/29/2016 The Franklin Institute Research 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 and are not subject to revision.

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Chapter 3 (continued)

First Page Last Page Revision 3E-i 3E-ii Revision 5209/29/2016 3E-1 3E-116 Revision 5209/29/2016 3E Att. 1-i 3E Att. 1-ii Revision 5209/29/2016 3E Att. 1-1 3E Att. 1-24 Revision 5209/29/2016 3E Att. 2-i 3E Att. 2-ii Revision 5209/29/2016 3E Att. 2-1 3E Att 2-20 Revision 5209/29/2016 3E Att. 3-i 3E Att. 3-ii Revision 5209/29/2016 3E Att. 3-1 3E Att. 3-58 Revision 5209/29/2016 Geotechnical 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.

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Chapter 5 (continued)

First Page Last Page Revision 5.6-1 5.6-10 Revision 5209/29/2016 5A-i 5A-ii Revision 5209/29/2016 5A-1 5A-164 Revision 5209/29/2016 Discussion 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, Transcript, dated April 13, 1976; corrected copy of transcript, dated May 18, 1976; 164 pages which were taken from original report and are not subject to revision.

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VOLUME VI Chapter 8 First Page Last Page Revision 8-i 8-iv Revision 5209/29/2016 8.1-1 8.1-6 Revision 5209/29/2016 8.2-1 8.2-12 Revision 5209/29/2016 8.3-1 8.3-58 Revision 5209/29/2016 Chapter 9 First Page Last Page Revision 9-i 9-xii Revision 5209/29/2016 9.1-1 9.1-54 Revision 5209/29/2016 9.2-1 9.2-62 Revision 5209/29/2016 9.3-1 9.3-116 Revision 5209/29/2016 9.4-1 9.4-38 Revision 5209/29/2016 9.5-1 9.5-86 Revision 5209/29/2016 9.6-1 9.6-12 Revision 5209/29/2016 9A-i 9A-ii Revision 5209/29/2016 9A-1 9A-22 Revision 5209/29/2016 9B-i 9B-ii Revision 5209/29/2016 9B-1 9B-16 Revision 5209/29/2016 VOLUME VII Chapter 10 First Page Last Page Revision 10-i 10-iv Revision 5209/29/2016 10.1-1 10.1-6 Revision 5209/29/2016 10.2-1 10.2-20 Revision 5209/29/2016 10.3-1 10.3-18 Revision 5209/29/2016 10.4-1 10.4-60 Revision 5209/29/2016 Chapter 11 First Page Last Page Revision 11-i 11-xii Revision 5209/29/2016 11-1 11-2 Revision 5209/29/2016 11.1-1 11.1-22 Revision 5209/29/2016 11.2-1 11.2-56 Revision 5209/29/2016 11.3-1 11.3-20 Revision 5209/29/2016

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Chapter 11 (continued)

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Chapter 14 (continued)

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