ML092820146

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Updated Final Safety Analysis Report, Revision 45, Revision Summary Through List of Effective Pages
ML092820146
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 09/30/2009
From:
Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Reactor Regulation
Shared Package
ML092810047 List:
References
09-574
Download: ML092820146 (100)


Text

Revision 4509/30/09 NAPS UFSAR 1 REVISION

SUMMARY

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

KWI Removes the key word index.

[NAPS-UCR-2009-023]

11.2.2.2 Reflects replacement of the ion exchange filtration

[FN 2008-002] system.

6.4.1.1, 6.4.1.2, 6.4.1.3, 6.4.1.3.1, Incorporates technical specification change to remove 6.4.1.4, 6.4.1.5, 7.7.1.12.1, 9.4.1.1, requirements for the control room bottled air system.

9.4.1.2, 9.4.1.3, 9.4.1.5, Table 9.4-2, 12.1.2.10, 15.4.1.7, 15.4.1.7.7, 15.4.5.2, 15.4.5.3, 15.4.5.4, Table 15.4-6, Table 15.4-13

[NAPS-UCR-2009-016]

11.4.2, 11.4.2.15 Corrected description of the reactor coolant letdown

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

6.2.2.2, 6.3.2.1.6 Reflects the installation of the seal closure frames on the

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

9.3.2.1.2, 9.3.2.1.3, Reflects modification os online chemistry monitoring Figure 9.3-2 (Sheets 7, 9, &12) system for Unit 1 steam generator feedwater chemistry.

[FN 2008-039]

9.2.2.3.1 Changed the pH range for the chromated component

[NAPS-UCR 2009-010] cooling water.

12.3.3 Added Effective Dose Equivalent to the types of exposure

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

9.5.2.1.3 Corrected location of the communications tower.

[NAPS-UCR 2009-015]

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

[FN 2008-004] feedwater heaters.

5.2.5.4 Replaced the reactor coolant pump vibration monitoring

[FN 2007-032] system.

Figure 8.2-2 Updated figure to reflect modifications made to the

[FN 2008-015] switchyard buses.

Revision 4509/30/09 NAPS UFSAR 2 Major Revision 4509/30/09 (continued)

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

7.7.2.6 Corrected section on safety injection actuation input logic

[NAPS-UCR-2009-006] 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 reactor

[FN 2008-036] vessel head drop analysis.

8.2.2 Clarifies the backup sources of power to the battery

[FN 2006-007] 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 containment

[FN 2007-009] 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 point

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

Figure 6.2-38 Corrects snubber figure to be consistent with plant

[FN 2008-034] configuration.

Table 10.4-4, Table 15.1-2, Corrects tables to be consistent with the accident analysis Table 15.4-35 of record calculations.

[NAPS-UCR-2009-001]

10.2, 10.4.7.2 Updated electrical ratings and cooling water requirements

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

6.2.2.2, 6.3.2.1.6 Added description of the containment sump strainer seal

[FN 2008-017] 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, Designated original plant shielding zone criteria as Figure 12.1.1, Figure 12.1.2, historical.

Figure 12.1.3, Figure 12.1.4, Figure 12.1.5

[FN 2008-031]

18.5 Refs. Updated references associated with the Steam Generator

[FN 2008-037] Program.

Revision 4509/30/09 NAPS UFSAR 3 Major Revision 4509/30/09 (continued)

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

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

Table 6.2-38, Table 6.2-39, Table 6.2-40, Figure 6.2-55, Figure 6.2-56, Figure 6.2-58, Figure 6.2-59, 6.3.2, 6.3.2.1.6, 6.3.4.2, 6.3 Refs, Table 6.3-1, Table 6.3-6

[FN 2007-031]

Table 15.1-3,15.2.7.2.2, Updated the loss of load event figures and tables to reflect Table 15.2-1, Figure 15.2-19, current analysis of record. Changed the safety analysis Figure 15.2-20, Figure 15.2-21, limit on High Pressurizer Pressure.

Figure 15.2-22, Figure 15.2-23, Figure 15.2-24, Figure 15.2-25, Figure 15.2-26, Figure 15.2-27, Figure 15.2-28, Figure 15.2-29, Figure 15.2-30

[FN 2008-018]

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

Figure 2.1-8, Figure 2.1-9, Figure 2.1-10, Figure 2.1-11, Figure 2.1-12, Figure 2.1-13, Figure 2.1-14

[FN 2008-020]

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

[FN 2008-022] 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 beams and

[FN 2008-024] new filter casks.

Table 6.4-1 Updated quantity of chemicals stored on site and in the

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

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

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

Revision 4509/30/09 NAPS UFSAR 4 Revision 4409/30/08 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

8.3.1.1.1, 9.5.1.2.3 Corrected a note for the temperature detecting sensors

[FN 2008-016] 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 pump

[FN 2008-019] NPSHa case.

5.5.1.3.11 Amends the discussion on RCP seal-water injection filter

[FN 2008-014] size.

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

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

9.4.4.5 Changes the method of controlling the Turbine Building

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

15.3.1.13, 15.3 Refs, Incorporates the latest assessments allocated to the peak Table 15.3-24, 15.4.1.18, clad temperature analysis of record for the AREVA small 15.4 Refs, Table 15.4-27 break LOCA and large break LOCA.

[FN 2008-011]

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

Figure 2A-2, Figure 2A-8

[FN 2005-046]

Table 9.5-1 Incorporates changes associated with fire protection

[FN 2006-021] system upgrade.

9.5.1.2.2.1 Corrects the CO2 system description to reflect that the

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

15A.3.1 Updates the site boundary dose for postulated cask drop

[FN 2008-006] accidents.

3.8.2.1.4.2, Figure 3.8-11, Updated the description of the hot pipe containment 9.2.2.1.1, 9.2.2.3.1 penetration coolers (Unit 1)

[FN 2007-017]

12.3.1, 13.4 Incorporates changes in titles to the Quality Assurance

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

Revision 4509/30/09 NAPS UFSAR 5 Revision 4409/30/08 (continued)

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

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

Table 3.8-20, Table 3.8-21

[FN 2007-033]

Figure 8.2-1 Revised figure to reflect new type of disconnect for

[FN 2008-003] H204M.

9.5.9.2 Added description of vacuum drying system that

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

3.8.2.7.6.1.1 Added description for restoration of recirculation spray

[FN 2007-026] sump trench floor.

Revision 4509/30/09 NAPS UFSAR 6 Revision 4409/30/08 (continued)

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

KWI, 6.1, 6.2.1.1.1, 6.2.1.1.1.1, Performed containment analyses and LOCA alternate 6.2.1.1.1.2, 6.2.1.1.1.3, 6.2.1.3.1, source term analyses to support GSI-191 modifications 6.2.1.3.1.1, 6.2.1.3.1.2, Unit 1.

6.2.1.3.1.2.1, 6.2.1.3.1.2.2, 6.2.1.3.1.3, 6.2.2.1, 6.2.2.2, 6.2.2.3.1, 6.2.2.3.2, 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.3, 6.2.2.3.2.4, 6.2.2.3.2.5, 6.2.2.3.2.6, 6.2.2.3.3, 6.2.3.1.1, 6.2.3.2, 6.2.3.3, 6.2.6.3, 6.2 Refs, Tables 6.2-1, 6.2-2, 6.2-3, 6.2-4, 6.2-11, 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, Added the Unit 1 incore sump room drain to support 12.1.2.1, Table 12.1-2, GSI-191 containment sump modifications.

Figure 12.1-8

[FN 2006-020]

Revision 4509/30/09 NAPS UFSAR 7 Revision 4409/30/08 (continued)

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

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

6.2.3.3, 6.2 Refs, Table 6.2-38, Table 6.2-40, Figure 6.2-55, Figure 6.2-58, Figure 6.2-59, Figure 6.2-60, Figure 6.2-74, Figure 6.2-87, 6.3.2.2.3, Table 6.3-1

[FN 2007-008]

6.2.2.2, 6.2.2.3.2.1, 6.2.3.1.1, Incorporates reduction in the minimum IRS and OSR Table 6.2-2, Table 6.2-12, safety analysis pump flow rates and updates the LOCA Figures 6.2-63, 64, 65, 66, 67, 68, alternate source term analysis.

69, 70, 71, 72, & 73, Figures 6.3-7, 8, 9, & 10, Table 15.4-7

[FN 2007-020]

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

[FN 2007-029] 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, Editorial changes; Clarifies final markups for GSI-191 6.2.3.1.1, 6.2.3.3, Table 6.2-41, multiple packages.

15.4.1.8.7, 15.4.5.2, Table 15.4-7, 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, Updated the description of the RWST level-low ESFAS 7.3.2.11, Table 7.3-2 function to include Unit 1 GSI-191 modification.

[FN 2007-016]

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

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

Table 5.2-22 Updated the description of the pressurizer secondary side

[FN 2007-025] closure bolting material.

6.2.1.2.20 Provided for use and storage of a manbasket inside the

[FN 2007-018] containment.

Revision 4509/30/09 NAPS UFSAR 8 Revision 4409/30/08 (continued)

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

7.2.1, 7.2.1.2, 7.2.2.2.1.7, Updated the description of reactor trip system response 7.2 Refs, 15.1.3 time testing and verification.

[FN 2007-010]

9.5.2.2.4 Corrected the description of the emergency notification

[FN 2007-006] system.

10.2 Modified the turbine overspeed protection control

[FN 2007-004] circuitry.

15.4.1.5.3, Table 15.4-5 Incorporated the peak clad temperature penalties and

[FN 2007-014] 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 submitting the

[FN 2007-023] Inservice Inspection Plan.

Revision 4509/30/09 NAPS UFSAR 9 Revision 4309/27/07 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

KWI, 6.1, 6.2.1.1.1, 6.2.1.1.1.1, Performed containment analyses and LOCA alternate 6.2.1.1.1.2, 6.2.1.1.1.3, 6.2.1.3.1, source term analyses to support GSI 191 modifications.

6.2.1.3.1.1, 6.2.1.3.1.2, 6.2.1.3.1.2.1, 6.2.1.3.1.2.2, 6.2.1.3.1.3, 6.2.2.1, 6.2.2.2, 6.2.2.3.1, 6.2.2.3.2, 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.3, 6.2.2.3.2.4, 6.2.2.3.2.5, 6.2.2.3.2.6, 6.2.2.3.3, 6.2.3.1.1, 6.2.3.2, 6.2.3.3, 6.2.6.3, 6.2 Refs, Tables 6.2-1, 6.2-2, 6.2-3, 6.2-4, 6.2-11, 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]

Revision 4509/30/09 NAPS UFSAR 10 Revision 4309/27/07 (continued)

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

Table 3.2-1, 4.1, Figure 6.1-1, Completed partial installation of Unit 2 containment 6.2.2.2, 6.2.2.3, 6.2.2.4.3, sump strainers to support GSI 191 modifications.

6.2.2.4.4, 6.2.3.3, 6.2 Refs, Tables 6.2-40 & 6.2-42, Figures 6.2-57, 6.2-58, 6.2-59, 6.2-60, 6.2-61, 6.2-62, & 6.2-80, 6.3.2.2.3, 6.3.3.12, 6.3.3.13, Table 6.3-1, 6.3-8, & 15.4-2

[FN 2006-037]

3.8.2.1.4.2, 3.8.2.1.4.5 Increased the temperature limitation for containment

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

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

& 3.8-15 penetrations (except installed spares).

[FN 2007-001]

3.8.2.1.4.2, Figures 3.8-11, Updated the description of the hot pipe containment

& 3.8-15, 9.2.2.1.1, 9.2.2.3.1 penetration coolers.

[FN 2007-003]

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

4.5-2, 4.5-3, 15.4.1.9, 15.4 Refs

[FN 2005-043]

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

4.5.4.2.10.4, 4.5.4.2.10.5, 4.5.4.3.1.3, 4.5.4.3.4.1, 4.5.4.3.4.1.3, 4.5 Refs, Table 4.5-3, 7.2.2.1.2.1, 15.1.9.8, Table 15.1-2, 15.3.4.2.1, 15.4.4.2.1, 15.4.4.2.2

[FN 2005-023]

Table 5.2-22 Updated the description of the pressurizer closure bolting

[FN 2006-031] material.

Revision 4509/30/09 NAPS UFSAR 11 Revision 4309/27/07 (continued)

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

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

Figure 12.1-8

[FN 2006-011]

6.2.2.2 Corrected the description of debris generation and

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

[FN 2006-035] GSI 191 containment sump modifications.

8.1.2, 9.2.1.1, 9.2.1.2.2, 9.2.1.3.1, Modified the terminology associated with determinations 9.2.2.3, 9.3.1.2, 9.3.2.1.3, of operability and functionality in accordance with 9.3.2.2.3, 9.3.4.2.1, 9.3.4.3.1, Regulatory Issue Summary 2005-20.

9.5.1.2.3, 9.5.1.3.4, 9.5.1.4.2, 9.5.1.6, 9.5.1.6.1, 9.5.1.6.2, 9.5.2.1.1, 9.5.6.2, 10.3.4, 10.4.1.4, 10.4.7.4, 11.4.5, 12.1.4.1

[FN 2007-011]

9.2.1.2.2 Reduced the frequency of monitoring the service water

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

9.2.2.5.1 Clarified the description of system operation following a

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

Table 9.2-4 Replaced auxiliary service water pump, 1-SW-P-4.

[FN 2006-032]

9.5.1.2.2.2, 9.5.1.2.3 Replaced heat and smoke detectors in the Training Center

[FN 2006-009] records vault.

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

[FN 2007-013] benefits for the Westinghouse SBLOCA. [10 CFR 50.46]

15.3.1.13, 15.3 Refs, Table 15.3-4, Incorporated the peak clad temperature penalties and 15.4.1.17, 15.4 Refs, benefits for the Westinghouse SBLOCA and AREVA Table 15.4-26 RLBLOCA. [10 CFR 50.46]

[FN 2006-022]

15.4.2.1.3.2, 15.4.3.4.2, 15.4.4.3.2 Revised the description of steam generator leakage.

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

Revision 4509/30/09 NAPS UFSAR 12 Revision 4309/27/07 (continued)

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

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 4509/30/09 NAPS UFSAR 13 Revision 4209/29/06 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

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

3.1.15.2, 3.6.1, 3.7.3.2, 6.2.1.3.1, [10 CFR 50.90 License Amendment]

6.2.2.1, 6.2.3.1, 6.2.3.1.1, 6.2.3.2, 6.2.3.3, Table 6.2-41, 6.3.3.6, Table 6.3-6, 6.4.1.1, 6.4.1.2, 6.4.1.3, 6.4.1.3.1, 7.7.1.12.1, 9.4.1.3, 9.4.5.3, Table 10.4-3, 11.1.1.1, 12.1.1, 12.1.2.8, 12.1.2.10, Figure 12.1-10, 15.1.7.1, 15.2.13.3, 15.4, 15.4.1.7, 15.4.1.7.1, 15.4.1.7.2, 15.4.1.7.3, 15.4.1.7.4, 15.4.1.7.5, 15.4.1.7.6, 15.4.1.7.7, 15.4.1.7.8, 15.4.1.8.3, 15.4.2.1.3, 15.4.2.1.3.1, 15.4.2.1.3.2, 15.4.2.1.3.3, 15.4.2.1.3.4, 15.4.2.1.3.5, 15.4.3.2.1, 15.4.3.2.3, 15.4.3.3, 15.4.3.4, 15.4.3.4.1, 15.4.3.4.2, 15.4.3.4.3, 15.4.3.4.4, 15.4.3.4.5, 15.4.4.2.2, 15.4.4.3, 15.4.4.3.1, 15.4.4.3.2, 15.4.4.3.3, 15.4.4.3.4, 15.4.4.3.5, 15.4.5, 15.4.5.1, 15.4.5.2, 15.4.5.3, 15.4.5.4, 15.4.7.1, 15.4.7.2, 15.4.7.2.1, 15.4.7.2.2, 15.4.7.2.3, 15.4.7.2.4, 15.4.7.2.4.1, 15.4.7.2.4.2, 15.4.7.2.4.3, 15.4.7.2.4.4, 15.4 Refs, Tables 15.4-6, 15.4-7, 15.4-12, 15.4-13, 15.4-14, 15.4-15, 15.4-17, 15.4-18, 15.4-29, 15.4-30, 15.4-31, 15.4-32, 15.4-33, 15.4-34, 15.4-35, 15.4-36, & 15.4-37, Figures 15.4-74 & 15.4-110

[FN 2003-036 & 2004-021]

3.8.2.1.4.2, Figures 3.8-11 Isolated ten Unit 2 containment penetrations outer cooler

& 3.8-15 component cooling supply and return by seal plate or

[FN 2005-038 & FN 2005-042] plug.

Revision 4509/30/09 NAPS UFSAR 14 Revision 4209/29/06 (continued)

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

3.8.2.1.4.2, Figures 3.8-11 Isolated ten Unit 1 containment penetrations outer cooler

& 3.8-143 component cooling supply and return by seal plate or

[FN 2006-002] plug.

Table 3F-8 Revised the emergency diesel generator rooms maximum

[FN 2006-025] temperature.

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

[FN 2006-005] channel factor, F H , and referred to the Core operating N

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

4.5.3.2.2.6.4 Modified the discussion of Unit 1 peaking factor

[FN 2005-018] uncertainty.

4.5.3.2.2.6.4 Modified the discussion of Unit 2 peaking factor

[FN 2005-019] uncertainty.

Table 4.5-3 Reflected the increase in core pressure drop due to use of

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

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

[FN 2006-023]

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

[FN 2003-053] administrative cooldown rate limit. [10 CFR 50.90 License Amendment]

5.2.3.3.1, 5.2 Refs, 5.4.3.6, Updated the surveillance capsule withdrawal schedules to 5.4 Refs, Tables 5.4-2 & 5.4-3 incorporate the renewed operating licenses for both units.

[FN 2005-005 & FN 2005-041] [10 CFR 50, Appendix H]

5.2 Refs, 18.2.12 Removed specific interval and ASME XI edition and

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

Table 5.2-3 Clarified that the narrow range RTD thermowells and

[FN 2006-003] 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 the RWST

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

Revision 4509/30/09 NAPS UFSAR 15 Revision 4209/29/06 (continued)

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

6.2.2.3 Clarified the description of the layup condition of the

[FN 2005-021] recirculation spray heat exchangers.

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

[FN 2006-019] the control rooms.

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

[FN 2005-030] 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]

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

[FN 2005-011]

Figure 8.2-1, 8.3.1.1.2.3, 8.3.1.2.1, Replaced vital bus inverters 1-III & 1-IV and added a 8.3.1.2.2.4, Table 8.3-8 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 vessel to the

[FN 2005-028] 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 handling

[FN 2005-016] bridge crane.

9.2.3.1, Table 9.2-10 Replaced domestic water Well No. 3 with Well No. 7.

[FN 2003-048]

9.3.3.2, 10.4.2.3 Installed backflow preventers in the floor drains of the

[FN 2006-017] 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 isolated phase

[FN 2006-001] 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 evaporator

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

Table 9.3-7 Corrected the description of boron recovery system

[FN 2006-004] equipment.

9.4.6.3 Updated the description of the safeguards supply fans

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

Revision 4509/30/09 NAPS UFSAR 16 Revision 4209/29/06 (continued)

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

9.4.9.3 Updated the description of containment isolation during

[FN 2004-050] 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 governor

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

10.3.1 Clarified the description of the steam generator PORVs

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

10.4.2.3 Reanalyzed the maximum flooding elevation of the

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

10.4.7.1 Replaced the bearing cooling tower chemical addition

[FN 2005-013] system.

11.4.2.1, 12.1.4.1 Updated the description of radiation monitor recorders.

[FN 2005-026]

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 4509/30/09 NAPS UFSAR 17 Revision 4109/30/05 Section Changes Made under the provisions of 10 CFR 50.59 except where indicated in brackets.

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

[FN 2004-002] minimum operating level, required submergence, and actual submergence.

3.1.37.2, 3.11.2.5, Table 3.11-2, Incorporated license amendments on elimination of 3A.7, 6.1, 6.2.5.1, 6.2.5.2, 6.2.5.3, requirements for hydrogen recombiners and hydrogen 6.2 Refs, Table 6.2-55 & 6.2-62, monitors using the Consolidated Line Item Improvement Figures 6.2-91, 6.2-92, 6.2-96, Process. [10 CFR 50.44]

6.2-97, 6.2-98, & 6.2-99

[FN 2005-004]

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

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

3.8.1.4.7, 3.8 Refs Provided clarification to the description of masonry block

[FN 2004-042] walls.

4.4.2.3.4.2, 4.4 Refs, 4.5.3.2.2.6.4 Described the overall peaking factor uncertainty

[FN 2004-045] 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 safety

[FN 2005-024] valves.

5.2.5, 5.2.5.1, 7.3.1.2, Tables Incorporated editorial corrections to improve readability, 15.4-16, 15.4-23, & 15.4-26 corrected spelling, and incorporated changes omitted

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

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

[FN 2004-049] activities from Section XI to a general reference to the ASME Code.

Tables 6.2-44, 6.2-45, & 6.2-46, Revised the safety analysis flow rate for maximum low 6.3.2.2.6, 6.3.4.4 head safety injection recirculation mode flow rate for the

[FN 2004-018] LHSI pump net positive suction head analysis.

6.3.2.1.4.2 Allowed that check valves 1-CH-240 and 2-CH-155 can

[FN 2005-027] be fitted with or without a spring.

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

[FN 2005-033] radiation monitoring system.

Revision 4509/30/09 NAPS UFSAR 18 Revision 4109/30/05 (continued)

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

6.4.1.3.3, Table 6.4-1 Updated the concentration of ethanolamine up to 85%.

[FN 2004-031]

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

[FN 2004-040] 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 generator

[FN 2005-001] water level.

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

[FN 2005-002] and overpower T.

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

[FN 2003-012] cross-tie.

Table 7.5-2 Updated the indicated accuracy for the refueling water

[FN 2005-014] storage tank water level.

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

[FN 2001-040]

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

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

9.2.1.1 Incorporated editorial changes to cross-reference and be

[FN 2005-020] 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 test

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

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

[FN 2004-033] component design data.

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

[FN 2005-025]

Revision 4509/30/09 NAPS UFSAR 19 Revision 4109/30/05 (continued)

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

9.5.1.1, 9.5.1.2.1, Figure 9.5-1, Replaced the cooling tower for the bearing cooling Table 10.4-6 system.

[FN 2004-044]

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 fire

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

& 9.5-8 jacket coolant temperature switches with a temperature

[FN 2004-046] converter system.

10.4.3, 15.4.1.5.1 Incorporated editorial spelling correction and corrected

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

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

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

15.1 Refs, 15.2 Refs, 15.3 Refs, Updated the RETRAN Topical Report references.

15.4 Refs

[FN 2004-038]

15.3.1,8, 15.3.1.13, 15.3 Refs, Incorporated the peak clad temperature penalties and Table 15.3-24 benefits for the small break LOCA for Framatome ANP

[FN 2005-009] Advanced Mark BW fuel. [10 CFR 50.46]

18.2.1, 18.2.6, 18.2.9, 18.2.19, Reflected the completion of License Renewal Table 18-1 Commitment Item Nos. 3, 4, 5, 7, 8, 15, and 29.

[FN 2004-048]

Revision 4509/30/09 NAPS UFSAR 20 Revision 4009/30/04 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

Table 2.4-6 Provided revised values for bearing lubricating water

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

Table 2.4-6 Modified the minimum operating level and actual

[FN 2003-027] 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 expansion

[FN 2003-011] 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 expansion

[FN 2004-011] 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 compliance with

[FN 2000-011] Regulatory Guide 1.58.

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

[FN 2003-051]

Table 3C-3, 8.3.1.1.2.3, Incorporated editorial corrections to vital bus panel board Table 8.3-8 mark numbers.

[FN 2004-027]

Revision 4509/30/09 NAPS UFSAR 21 Revision 4009/30/04 (continued)

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

4.1, 4.1 Refs, Table 4.1-2, 4.5 All, Added the description of the Framatome ANP Advanced 5.1.2.1.2, 6.3.3.12, 6.3.3.13, Mark BW fuel product. [10 CFR 50.90 License 6.3 Refs, 7.2.1, 11A.1.1, Amendment]

11A Refs, 15, 15.1.2.2, 15.1.9.7, 15.1 Refs, Tables 15.1-2 & 15.1-3, 15.3.1, 15.3.1.8, 15.3.1.9, 15.3.1.10, 15.3.1.11, 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, Added the description of the Studsvik Core Management 4.3.3, 4.3.4, 4.3.4.1, 4.3.4.2, System computational model for reactor physics 4.3.4.2.1, 4.3.4.3, 4.3 Refs, analyses.

Tables 4.3-6 & 4.3-10, 15.1 Refs, 15.3 Refs

[FN 2003-035]

4.2.1.4.2, 4.2.3.4.1 Updated the feed fuel and burnable poison rod vendor

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

Revision 4509/30/09 NAPS UFSAR 22 Revision 4009/30/04 (continued)

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

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

[FN 2004-009]

5.2.3.4 Corrected typographical and grammatical errors.

[FN 2004-004]

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 pressurizer

[FN 2004-020] safety valve forgings.

5.5.1.3.11 Incorporated a filter size range for the reactor coolant

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

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

[FN 2004-012] annulus area of containment.

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

15.4-88, 15.4-89, 15.4-90, 15.4-91, 15.4-92, 15.4-93, 15.4-94, 15.4-95, 15.4-96, 15.4-97

[FN 2004-037]

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 name with

[FN 2004-007] the generic chemical compound.

Table 7.2-4, 15.4.2.2.2.1, Provided analysis results that smaller feedline breaks are 15.4 Refs protected by the high pressurizer pressure trip.

[FN 2004-005]

7.3.1.3.5, 8.3.1.1.2.3, Table 8.3-8, Modified the Unit 2 service water spray array 9.2.1.1, 9.2.1.2.2 motor-operated valve safety injection signal actuation

[FN 2002-056] cross-tie.

8.2.2 Clarified the requirements for switchyard stability.

[FN 2002-021]

Revision 4509/30/09 NAPS UFSAR 23 Revision 4009/30/04 (continued)

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

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 testing

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

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 water spray

[FN 2003-049] 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 refrigerant

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

Table 9.2-4 Replaced auxiliary service water pump, 2-SW-P-4.

[FN 2004-014]

9.3.4.2.4.21 Provided a new packing configuration for charging

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

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

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

9.5.5.2, 9.5.7.2, Figures 9.5-6 Replaced the 1H emergency diesel generator lube oil and

& 9.5-8 jacket coolant temperature switches with a temperature

[FN 2003-026] converter system.

9.5.5.2, 9.5.7.2, Figures 9.5-6 Replaced the 2H emergency diesel generator lube oil and

& 9.5-8 jacket coolant temperature switches with a temperature

[FN 2003-045] converter system.

10.4.8.5 Modified the conductivity monitoring function for the

[FN 2004-015] condensate polishing system.

Table 10.4-2 Incorporated editorial correction to properly locate the

[FN 2004-022] flash evaporator duty and shell design pressure data.

Figure 11.3-1, 11.4.3, 11.4.3.2, Replaced the Process Vent, Vent A, and Vent B radiation Table 11.4-4, 12.2.4 monitors.

[FN 2003-031]

Revision 4509/30/09 NAPS UFSAR 24 Revision 4009/30/04 (continued)

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

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

[FN 2002-043]

15.2.4.2.2 Corrected the description of valves required to be locked

[FN 2004-032] 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 document

[FN 2004-010] number.

15.4.1, 15.4.1.1, 15.4.1.4, Revised the large break loss of coolant accident analyses.

15.4.1.5.2, 15.4.1.5.6, 15.4 Refs, Table 15.4-1, 15.4-2, 15.4-3, 15.4-4, & 15.4-5, Figures 15.4-1, 15.4-2, 15.4-3, 15.4-4, 15.4-5, 15.4-6, 15.4-7, 15.4-8, 15.4-9, 15.4-10, 15.4-11, 15.4-12, 15.4-13, 15.4-14, 15.4-15, 15.4-16, 15.4-17, 15.4-18, 15.4-19, 15.4-20, 15.4-21, 15.4-22, 15.4-23, 15.4-24, 15.4-25, 15.4-26, 15.4-27, 15.4-28, 15.4-29, 15.4-30, 15.4-31, 15.4-32, 15.4-33, 15.4-34, 15.4-35, 15.4-36, 15.4-37, 15.4-38, 15.4-39, 15.4-40, 15.4-41, 15.4-42, 15.4-43, 15.4-44, 15.4-45, 15.4-46, 15.4-47, 15.4-48, 15.4-49, 15.4-50, 15.4-51, 15.4-52, 15.4-53, 15.4-54, 15.4-55, & 15.4-56

[FN 2004-016]

15.4.1.14.2, Table 15.4-25, Incorporated a change to the Unit 2 summary of peak 15.4-26, 15.4-27, & 15.4-28, clad temperature penalties and benefits for the large break Figures 15.4-98, 15.4-99, LOCA. [10 CFR 50.46]

15.4-100, 15.4-101, 15.4-102, 15.4-103, 15.4-104, 15.4-105, 15.4-106, 15.4-107, 15.4-108, 15.4-109

[FN 2004-026]

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)]

Revision 4509/30/09 NAPS UFSAR 25 Revision 4009/30/04 (continued)

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

17.2.2.8 Updated terminology to the current naming convention

[QA 2004-005] for inservice inspection personnel. [10 CFR 50.54(a)(3)]

17.2.10 Updated the description of qualification requirements for

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

[10 CFR 50.54(a)(3)]

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

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

Revision 4509/30/09 NAPS UFSAR 26 Revision 3909/30/03 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

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

6.2 Refs, 13.2.1

[FN 2003-041]

1.1, 2.1.3.1, Table 3.8-7, 3.11.2.2, Reflected the increased operating life basis from 40 to 3E.3.4, 4.0, 4.2.3.1.4, 5.1, 60 years and added Chapter 18 [10 CFR 54.21] to Tables 5.1-1, 5.2-20, 5.2-21, 5.4-2, describe the programs and activities that manage the

& 5.4-3, 5.5.2.3.4, 6.1, 7.1, 8.1, effects of aging materials during the extended operation 9.1, 10.1, 11.0, 18.0, 18.1, 18.1.1, period associated with license renewal.

18.1.2, 18.1.3, 18.1.4, 18.2, 18.2.1, 18.2.2, 18.2.3, 18.2.4, 18.2.5, 18.2.6, 18.2.7, 18.2.8, 18.2.9, 18.2.10, 18.2.11, 18.2.12, 18.2.13, 18.2.14, 18.2.15, 18.2.16, 18.2.17, 18.2.18, 18.2.19, 18.2.20, 18.3, 18.3.1, 18.3.1.1, 18.3.1.2, 18.3.1.3, 18.3.2, 18.3.2.1, 18.3.2.2, 18.3.2.3, 18.3.2.4, 18.3.3, 18.3.4, 18.3.5, 18.3.5.1, 18.3.5.2, 18.3.5.3, 18.3.5.4, 18.3.5.5, 18.3.5.6, 18.3.6, 18.4, 18.4.1, 18.4.2, 18.5, Table 18-1

[FN 2002-010]

2.3.3.2.5.1, 2.3.4.3, Tables 2.3-15 Replaced the emergency response facilities computer

& 2.3-16, Table 7.5-2, 7.7.1.10 systems.

[FN 2002-011]

Table 2.4-6 Modified the submergence of one auxiliary flash

[FN 2003-030] 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 quench spray

[FN 2002-004] and recirculation spray nozzles. [10 CFR 50.90 License Amendment]

3.1.53.1, 6.2.2.2, 6.2.3.1.1, Revised the boron concentration limits for the refueling Table 6.2-40, 6.3.3.4, Tables 6.3-1 water storage tank, casing cooling tank, safety injection

& 6.3-5, 9.1.4.5, 9.3.4.2.4.8, accumulators, and the spent fuel pool in accordance with 15.2.13.2.2 the Technical Specifications. [10 CFR 50.90 License

[FN 2000-027 & FN 2000-027B] Amendment]

Revision 4509/30/09 NAPS UFSAR 27 Revision 3909/30/03 (continued)

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

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

[FN 2003-021] 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, Replaced the Unit 2 reactor vessel closure head.

3.7.2.7.3.3, 3.7.2.7.3.4, 3.7.2.7.3.5, 3.7.3.1.3.7, 3.7 Refs, 4.2.3.2.2, Table 5.1-1, 5.2.3.1, 5.2.3.1.1, 5.2.3.3.1, 5.2 Refs, Tables 5.2-2, 5.2-3, 5.2-16, 5.2-22, & 5.2-27, 5.4.1.1, 5.4.4.2, 5.4.4.3, Tables 5.4-1, 5.4-4, & 5.4-5, Figures 5.4-1 & 5.4-2, 6.2.1.1.1.3, 7.7.1.9.1, Table 9.6-1

[FN 2002-054]

3.7.2.7.3, 3.7.2.7.3.1, 3.7.3.1.4, Replaced the Unit 1 reactor vessel closure head.

4.1, 4.2.3.2.2, Table 5.1-1, 5.2.3.1, 5.2.3.1.1, 5.2.3.3.1, 5.2 Refs, Tables 5.2-2, 5.2-3, 5.2-22, 5.2-26,

& 5.2-27, 5.4.1.1, 5.4.2, 5.4.4.2, Tables 5.4-1, 5.4-4, 5.4-5, Figures 5.4-1 & 5.4-2, 6.2.1.1.1.3, 7.7.1.9.1, Table 9.6-1

[FN 2003-008]

3.8.1.5.1, 3.8.1.5.2, 3.8.1.5.2.1, Completed the restoration of construction opening in the 3.8.1.5.3, 3.8.2, 3.8.2.1.2.3, containment structure for the Unit 2 reactor pressure 3.8.2.1.2.4, 3.8.2.3, 3.8.2.7, vessel head replacement.

3.8.2.7.1, 3.8.2.7.2, 3.8.2.7.3, 3.8.2.9, 3.8.2.9.1, 3.8.2.9.2, 3.8.2.9.3, 3.8.2.9.4, 3.8.2.9.5, 3.8 Refs, 3A.10, 3A.15, 3A.18, 3A.19

[FN 2002-051 & FN 2003-005]

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

[FN 2002-050] opening in the containment due to reactor vessel head replacement. [10 CFR 50.54(a)(3)]

Revision 4509/30/09 NAPS UFSAR 28 Revision 3909/30/03 (continued)

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

3.8.2.9, 3.8.2.9.2, 3.8.2.9.4, Completed the restoration of construction opening in the 3.8.2.9.5 containment structure for the Unit 1 reactor pressure

[FN 2003-007 & FN 2003-019] vessel head replacement.

3.8.4.5.4.2, 3.8.4.5.4.5, Replaced service water discharge piping mechanical Figures 3.8-41 & 3.8-43 (metal) expansion joints with rubber expansion joints.

[FN 2002-022] & [FN 2002-029]

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 corrosion of

[FN 2002-057] zirconium-based fuel assembly structural components.

4.2.1.2, 4.2.1.2.1, 4.2.1.2.2, Incorporated small dimensional changes for fuel 4.2.3.3.1, Table 4.2-2 assemblies and accurately reflected burnable poison

[FN 2002-049] assembly design.

4.2.3.4.2 Eliminated the seismic allowance in the control rod drop

[FN 2002-044] 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, Modified the service structure, cooling air shroud and 6.2.1.2.15, Table 6.3-8, 9.1.4.4.2, shroud support, insulation, and intermediate lift ring for Figures 9.1-5 & 9.1-6, 9.6.4.4, the Unit 2 reactor vessel head replacement.

Table 9.6-1

[FN 2002-052]

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

9.6 Refs, Table 9.6-1

[FN 2003-009]

5.2.2.2 Reflected Low Temperature Overpressure Protection

[FN 2003-003] 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 accumulator

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

Revision 4509/30/09 NAPS UFSAR 29 Revision 3909/30/03 (continued)

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

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

6.2.1.3.1.1, 6.2.2.2, 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.4, 6.2.2.3.2.6, 6.2.2.3.3, 6.2.6.3, Tables 6.2-1, 6.2-2, 6.2-4, 6.2-11, 6.2-12, 6.2-13, 6.2-38, 6.2-44, 6.2-45,

& 6.2-56, Figures 6.2-61, 6.2-62, 6.2-63, 6.2-64, 6.2-65, 6.2-66,

& 6.2-82, 6.3.2.2.2, 6.3.2.2.6, Table 6.3-9, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-11, 6.3-12,

& 6.3-13

[FN 2002-046]

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

6.2.2.2, 6.2.2.3.2.1, 6.2.2.3.2.2, 6.2.2.3.2.4, 6.2.2.3.2.6, 6.2.2.3.3, 6.2.6.3, Tables 6.2-1, 6.2-2, 6.2-4, 6.2-11, 6.2-12, 6.2-13, 6.2-38, 6.2-44, 6.2-45, & 6.2-56, Figures 6.2-61, 6.2-62, 6.2-63, 6.2-64, 6.2-65, 6.2-66, & 6.2-82, 6.3.2.2.2, 6.3.2.2.6, Table 6.3-9, Figures 6.3-7, 6.3-8, 6.3-9, 6.3-10, 6.3-11, 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 10 CFR 50,

[FN 2002-030] Appendix J Type C Program.

6.4.1.2, 6.4.1.3, 6.4 Ref Dwgs, Installed two new control room bottled air trains to 9.4.1.1, 9.4.1.2, 9.4.1.3, 9.4.1.5, provide a total of four trains supplying breathing air and Table 9.4-2 pressurization.

[FN 2001-029]

7.2.1.1.2, Figure 7.2-4 Reformatted the equations describing overtemperature

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

8.1.2 Eliminated the battery charger for the spillway gate

[FN 2002-023] supervisory control system batteries.

Revision 4509/30/09 NAPS UFSAR 30 Revision 3909/30/03 (continued)

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

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

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

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

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

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

Table 8.3-8

[FN 2003-004]

8.3.1.1.2.3, 8.3.1.4.1.4, 8.3.1.2.2.4, Installed replacement vital bus inverters 2-I and 2-II.

Table 8.3-8

[FN 2002-017]

9.1.4.9.1, 9.1.4.9.2, 9A.2, 9B.2, Placed a cask pedestal in the cask loading area of the 9B.3, 15A.1 spent fuel storage pool.

[FN 2003-029]

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

[FN 2003-034]

9.3.1.3.2 Provided cross-reference to UFSAR Section 3.1.19.2.

[FN 2002-041]

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

[FN 2003-015] ion exchangers.

9.5.1.3.1.3 Corrected the description of the auxiliary feedwater pump

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

9.5.2.1.1 Allowed the public address system to be powered from

[FN 2003-017] either vital bus 1-II or 2-II.

9.5.5.2, 9.5.7.2, Figures 9.5-6 Replaced the 1J emergency diesel generator lube oil and

& 9.5-8 jacket coolant temperature switches with a temperature

[FN 2003-013] converter system.

10.2 Clarified the operating pressure limit for high pressure

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

10.4.2.2 Provided a clarified description of the function of the

[FN 2002-039] 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 polishing

[FN 2002-012 & FN 2002-048] systems with programmable logic controllers.

Revision 4509/30/09 NAPS UFSAR 31 Revision 3909/30/03 (continued)

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

11.4.2.1, 11.4.2.2, 11.4.2.3, Replaced the Process Vent, Vent A, and Vent B radiation 11.4.2.4, 11.4.2.5, 11.4.3, monitors.

11.4.3.1.1, 11.4.3.1.2, 11.4.3.1.3, 11.4.3.2, 11.4.5, Table 11.4-1

& 11.4-2

[FN 2003-038]

15.1.2.3 Provided an enhanced text description of rod cluster

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

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

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

17.2.0.2, Table 17.2-0, 17.2.2.1, Made editorial corrections to correctly refer to 17.2.2.5, 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, Revised organizational titles of the Senior Vice President 17.2.1.2.B.1, 17.2.1.2.B.1.b.1.1, Nuclear Operations, Shift Manager, and Unit Supervisor.

17.2.1.2.C.1, 17.2.16.2.B.2, [10 CFR 50.54(a)(3)]

17.2.16.2.C, 17.2.1.16.2.D, Figures 17.2.1-1 & 17.2.1-2, Table 17.2-0, App C A.8.e, B.6.e, B.6.i, B.7.c, & B.8

[FN 2003-016]

17.2.1.2 Assigned responsibility for maintenance of plant

[FN 2003-010] 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 Nuclear

[FN 2002-008] Oversight Board. [10 CFR 50.54(a)(4)]

Revision 4509/30/09 NAPS UFSAR 32 Revision 3809/03/02 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

KWI Deleted Hypochlorite Treatment from the Key Word

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

Figure 1.2-1 Added the Independent Spent Fuel Storage Installation to

[FN 96-021] the Site Plan.

2.4.3, 2.4.14, 2A.4, 2A.5, 3.1.7.2, Implemented the conversion to Improved Technical 3.8.4.5.2, 3.8.4.5.3, 3.8.4.6, Specifications including the relocation of requirements to 3.8.4.8, Table 3.8-15, 3A.13, the UFSAR. [10 CFR 50.90 License Amendment]

3A.16, 4.3.1.3, 4.3.1.5, 4.3.2.2.6, 4.3.2.4, 4.3.2.5.2, 4.3.2.5.6, 4.4.5.3, 5.1.3.1, 5.2.1.2, 5.2.4.1.1, 5.2.4.2, Table 5.2-4, 5.5.4.4, 5.5.7.3, 5.5.9.2.2, 6.2.1.4.5, 6.2.2.4.1, 6.2.4.4, 6.2.7.5, Tables 6.2-50, 6.2-58, & 6.2-59, 6.3.2.1.4.5, 6.3.2.1.4.7, 6.4.1.2, 6.4.1.3.1, 6.4.1.4, 7.1.1, 7.2.1, 7.2.1.1, 7.2.1.10, 7.2.2.1.1, 7.2.2.1.2, 7.2.2.2.1.7, 7.2.3.1, 7.2.3.2, Table 7.2-5, 7.3.1.1.1, 7.3.2.1.5.9, Table 7.3-2, 7.7.1.3.3, 7.7.1.13.1, 7.7.2.2, Table 7.7-2, 9.1.2, 9.1.4.6.1.1, 9.2.1.5, 9.2.2.6, 9.2.2.7, 9.2.5.4, 9.3.4.2.5.2, 9.3.4.3.1, 9.3.4.4, 9.4.1.1, 9.4.1.3, 9.4.1.4, 9.4.5.3, 9.4.5.4, 9.4.6.4, 9.4.8.5, 9.5.4.2, 9.5.4.4, 9.6.3, 10.3.2, 11.3.3.2, 11.4.2, 11.4.2.14.2, 11.4.3.1.1, 11.4.3.1.2, 11.4.3.1.3, 11.4.5, 11.5, 11C cover, 12.0, 12.1.4.1, 12.2.4, 12.3.1, 13.4, 13.5, 13.5 Refs, 14A, 15.1.2.3, 15.2.3.1, 15.2.6.3.1, 15.2.10.1, 15.3.1.4, 15.4.1.2, 15.4.1.4, 15.4.1.7, 15.4.5.2.1, 15.4.5.2.3, 15.4.7.2.1, 15.4.7.2.4.1, 15.4.7.2.4.4, 16.1, 16.2

[FN 2002-014]

Revision 4509/30/09 NAPS UFSAR 33 Revision 3809/03/02 (continued)

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

2.4.10, 2.5.5, 2A.3, 2A.4, Provided description of the flood protection dike.

Table 3.2-1, 3.8.6, 3.8.6.1, 3.8.6.2, Figure 3.8-61

[FN 2001-006]

2.4.11.4 Included reservoir discharge flow reductions for drought

[FN 2000-040] 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, Established spent fuel pool soluble boron concentration 4.3.2.7, 4.3 Refs, 9.1.2, and fuel assembly loading restrictions based on burnup Table 15.3-1 and enrichment. Increased maximum fuel enrichment

[FN 2000-037] from 4.3 to 4.6 weight percent U-235. [10 CFR 50.90 License Amendment]

3.1.53.2, 6.2.2.2, 6.2.3.1.1, 6.2.3.3, Increased the boron concentration in the spent fuel pool Table 6.2-40, Figures 6.2-76 and Unit 1 refueling water storage tank, casing cooling

& 6.2-77, 6.3.3.4, Tables 6.3-1 storage tank, and safety injection accumulators.

& 6.3-5, 9.1.4.5, 9.3.4.2.4.8, [10 CFR 50.90 License Amendment]

15.2.13.2.2, Table 15.2-1

[FN 2001-041]

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

15.4.5.3

[FN 2002-036]

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

[FN 2001-038] 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, Supplemented the fuel rod design criteria references to 4.4.3.4.2, 4.4 Refs, 15.4 Refs new fuel performance models.

[FN 2002-028]

5.2.5.1, 5.2 Refs Updated references to the current inservice inspection

[FN 2001-039] interval.

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

[FN 2001-022] 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 available for the

[FN 2001-016] recirculation spray pumps.

Revision 4509/30/09 NAPS UFSAR 34 Revision 3809/03/02 (continued)

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

6.2.3.2, Table 6.2-50, 9.4.2.3, Indicated that the maximum relative humidity of the 9.4.6.3, 9.4.8.2 auxiliary building charcoal filter inlet air will be below

[FN 2001-025] 70%. Clarified the design description of the primary ventilation system.

6.2.5.3, 6.2 Refs, Tables 6.2-54 Reanalyzed hydrogen concentration in containment

& 6.2-59, Figures 6.2-80, 6.2-81, following a LOCA.

6.2-82, 6.2-86, 6.2-87, 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 incorporated changes

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

Tables 6.2-44 & 6.2-45, 6.3.2.2.6, Revised the safety analysis flow rate for maximum low 6.3.4.4 head safety injection recirculation mode flow rate NPSH

[FN 2002-005] 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 is

[FN 2000-038] 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 revised its

[FN 2001-035] storage tank capacity.

6.4.1.3.3, Table 6.4-1 Updated the description of potentially hazardous

[FN 2002-013] 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 pressurizer

[FN 2001-026] 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 representation of the

[FN 2001-034] 34.5 kV system in the switchyard.

8.3.1.1.2.3, 9.5.1.1, 17.2.1.2, Removed terminology associated with the former 17.2.5 10 CFR 50.59 regulation and incorporated wording from

[FN 2001-032] the current rule.

9.2.1.2.1, 9.2.1.4.1 Clarified the two-valve isolation from the service water

[FN 2000-012] header provided by the manual isolation valve and the single check valve. Added stainless steel service water piping and Hastelloy C276 valves.

Revision 4509/30/09 NAPS UFSAR 35 Revision 3809/03/02 (continued)

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

9.2.1.2.1, Figure 9.2-1 Reconfigured the service water supply and return headers

[FN 2000-036] 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 compressor, dryer,

[FN 2001-020] and receiver tank.

9.2.2.3.1 Clarified the component cooling system thermal relief

[FN 2001-028] requirements.

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

[FN 2001-031] chemistry monitoring system.

9.3.2.2, 9.3 Refs Clarified the status of the High Radiation Sampling

[FN 2002-007] System Post-Accident. [10 CFR 50.90 License Amendment]

9.5.1 Clarified the description of the low pressure carbon

[FN 2002-009] dioxide system zone isolation.

9.5.1.1 Identified fire protection systems that are not required to

[FN 2001-036] satisfy regulatory requirements. [10 CFR 50.48]

9.5.1.1 Identified fire protection systems that are not required to

[FN 2002-003] satisfy regulatory requirements. [10 CFR 50.48]

Figure 15.2-44, 15.4.6.2.3.4 Corrected a typographical error and incorporated a

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

15.4.2.2.2.2, 15.4 Refs Incorporated the evaluation of steam generator mid-deck

[FN 2002-020] plate pressure differential on safety analysis transients.

17.2.1.1, 17.2.1.2, 17.2.10, Modified organizational titles and realigned certain Figures 17.2.1-1, 17.2.1-2, reporting relationships within the Nuclear Business Unit.

& 17.2.1-3 [10 CFR 50.54(a)(3)]

[FN 2002-006]

17.2.1.2, Figures 17.2.1-1 Relocated the Records Management Program

& 17.2.1-3 organization from General Services to Nuclear

[FN 2001-037] Engineering. [10 CFR 50.54(a)(3)]

Revision 4509/30/09 NAPS UFSAR 36 Revision 3809/03/02 (continued)

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

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

[FN 2001-021] QA Topical Report. [10 CFR 50.90 License Amendment]

17.2.7 Updated the description of the organizational structure to

[FN 2002-032] 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 4509/30/09 NAPS UFSAR 37 Revision 3709/04/01 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

1.1, 1.2.3, 1.3.2, 1.5, 1.5.1, 1.5.1.1, Incorporated technical and editorial corrections and 1.5.1.2, 1.5.1.3, 1.5.1.4, 1.5.1.5, clarifications related to miscellaneous portions of the 1.5.1.6, 1.5.2, 1.5.2.1, 1.5.2.2.1, reactor design.

1.5.2.2.2, 1.5.2.2.3, 1.5.2.2.4, 1.5.2.2.5, 1.5.2.3, 1.5.3, 1.5.3.1, 1.5.3.2, 1.5.3.2.1, 1.5.3.2.2, 1.5.3.2.3, 1.5.3.2.4, 1.5.3.2.5, 1.5.3.2.6. 1.5.3.2.7, 1.5.3.2.8, 1.5.3.2.9, 1.5.3.2.10, 1.5.3.2.11, 1.5.3.2.12, 1.5.3.2.13, 1.5.3.2.14, 1.5.3.2.15, 1.5 Refs, 3.1.23.2, 3.1.53.2, 3.9.1.2.9, 3.9.3.1.4, 3.9 Refs, 3A.19, 3A.80, 5.5.1.1, Figure 6.2-2, 7.7.1.3.3, 7.9.2.1, 7.9.2.2, 9.3.4.2.5.2, 9.3.4.3.1, 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, Corrected typographical, administrative, and format 9.1.4.5 errors.

[FN 2001-023]

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, Updated the description of fire protection and fire 9.5.1.3.1.2, 9.5.1.4.1.2 fighting equipment.

[FN 2001-011]

3.7.2.5, 3.7.3, 3.7.3.2, 3.7.3.2.2.3, Incorporated the criteria and methodology of the generic 3.7.3.2.2.4, 3.7.3.3.5, 3.7 Refs, implementation procedure for seismic design and 3.9.1.3, 3.10.1, 3.10.2, 3.10.3, equipment verification. [Unresolved Safety Issue A-46]

3.10 Refs

[FN 2001-007]

3.8.1.1.6, 9.1.4.4.12, 9.5.9.1, Installed Helium and Vacuum Drying System equipment 9.5.9.2 that supports loading of Independent Spent Fuel Storage

[FN 96-024] Installation casks. Updated the cask trolley description.

Figure 3.8-31 Deleted pump house gate and fence symbols and labels

[FN 2000-033] from the service water reservoir figure representation.

Revision 4509/30/09 NAPS UFSAR 38 Revision 3709/04/01 (continued)

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

3A.46.1, 6.2.2.1, 12.1.4.2, 12.2.6, Corrected typographical spelling errors and electronic 15.2.4.2.2 scanning discrepancies, and incorporated a phrase

[FN 2001-009] omitted from a previously implemented UFSAR change.

Table 3C-2 Revised operating pressure and temperature, line size,

[FN 2001-001] seismic class, and quality class parameters for specific high-energy lines outside containment.

Revision 4509/30/09 NAPS UFSAR 39 Revision 3709/04/01 (continued)

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

4.2.1.2, Table 4.2-2, 4.3.2.6, Incorporated technical and editorial corrections and Figures 4.3-38 & 4.3-39, clarifications related to plant safety analyses.

6.2.1.3.1.1, 6.2.1.3.1.3, 6.2 Refs, 6.3.2.2.1, Figures 6.4-2 & 6.4-3, 7.2.2.1.2.1, 7.6.3.2, 11.1.1.2, Table 11.1-11, 15, 15 Refs, 15.1, 15.1.2.1, 15.1.2.2, 15.1.2.3, 15.1.3, 15.1.5, 15.1.6, 15.1.7.2, 15.1.8.1, 15.1.8.2, 15.1.9.2, 15.1.9.4, 15.1 Refs, Tables 15.1-2, 15.1-3, 15.1-4, 15.1-7, & 15.1-8, Figure 15.1-2, 15.2, 15.2.1.2.1, 15.2.1.2.2, 15.2.2.1, 15.2.2.2.1, 15.2.2.3, 15.2.3.2, 15.2.4.2.2, 15.2.6.1, 15.2.6.1.1, 15.2.6.1.2, 15.2.6.2.1.1, 15.2.6.2.2.1, 15.2.6.2.3.1, 15.2.6.2.3.2, 15.2.7.2.1, 15.2.7.2.2, 15.2.10.3.2, 15.2.10.3.3, 15.2.13.2.1, 15.2.13.2.2, 15.2.13.3, 15.2.14.1, 15.2.14.2.1, 15.2 Refs, Table 15.2-1, Figures 15.2-19, 15.2-20, 15.2-21, 15.2-22, 15.2-23, 15.2-24, 15.2-25, 15.2-26, 15.2-27, 15.2-28, 15.2-29, 15.2-30,

& 15.2-31, 15.3.1.3, 15.3.1.4, 15.3.1.5.2, 15.3.1.6, 15.3.3.1, 15.3.3.3, 15.3.4.1, 15.3.5.2, 15.3.7.1, 15.3.7.2, Figure 15.3-29, 15.4.1.5.4, 15.4.1.8.1, 15.4.2.1.2.2, 15.4.2.2.2.1, 15.4.3.4.1, 15.4.3.4.2, 15.4.5.1, 15.4.5.2.3, 15.4.5.2.4, 15.4.6.2.1, 15.4.6.2.1.2, 15.4.6.2.2.5, 15.4.6.2.3.6, 15.4.7.2.4.2, 15.4 Refs, &

Table 15.4-15

[FN 99-066]

4.2.1.2.2 Changed the material of the fuel assembly hold-down

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

Revision 4509/30/09 NAPS UFSAR 40 Revision 3709/04/01 (continued)

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

4.3.1.1, 4.3.1.3, 4.3.1.5, 4.3.2.1, Incorporated technical and editorial corrections and 4.3.2.2, 4.3.2.2.3, 4.3.2.2.4, clarifications related to reactor design nuclear.

4.3.2.2.5, 4.3.2.2.6, 4.3.2.2.7, 4.3.2.3.1, 4.2.3.2.3, 4.3.2.3.4, 4.3.2.4, 4.3.2.4.2, 4.3.2.4.6, 4.3.2.4.8, 4.3.2.4.9, 4.3.2.5.1, 4.3.2.5.3, 4.3.2.5.4, 4.3.2.5.6, 4.3.2.6, 4.3.2.7, 4.3.2.8.4, 4.3.2.8.5, 4.3.2.9, 4.3.3, 4.3.3.1, 4.3.3.2, 4.3.3.2.1, 4.3.3.2.2, 4.3.3.2.3, 4.3.3.2.4, 4.3.3.2.5, 4.3.3.3, 4.3 Refs, Tables 4.3-1, 4.3-3, 4.3-6, 4.3-7, 4.3-8, 4.3-9, 4.3-10, & 4.3-11, Figures 4.3-4, 4.3-14, 4.3-15, 4.3-16, 4.3-17, 4.3-18, 4.3-19, 4.3-20, 4.3-23, 4.3-37, 4.3-40, 4.3-43, 4.3-44, 4.3-45, & 4.3-46

[FN 99-037]

4.4.1.1, 4.4.1.5, 4.4.2.1, 4.4.2.2, Incorporated technical and editorial corrections and 4.4.2.2.1, 4.4.2.2.2, 4.4.2.2.3, clarifications related to thermal-hydraulic reactor design.

4.4.2.2.5, 4.4.2.2.6, 4.4.2.3, 4.4.2.3.1, 4.4.2.3.2.1, 4.4.2.3.2.2, 4.4.2.3.3, 4.4.2.3.4, 4.4.2.3.4.1, 4.4.2.3.4.2, 4.4.2.5, 4.4.2.6, 4.4.2.7.1, 4.4.2.7.2, 4.4.2.8.1, 4.4.2.8.2, 4.4.2.8.3, 4.4.2.10.1, 4.4.2.10.2, 4.4.2.10.4, 4.4.2.10.5, 4.4.2.10.6, 4.4.2.10.7, 4.4.2.10.8, 4.4.2.11, 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.

Revision 4509/30/09 NAPS UFSAR 41 Revision 3709/04/01 (continued)

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

5.2.2.2, 5.2.3.3.1, 5.2 Refs, Revised the analysis basis for reactor coolant system Tables 5.2-20 & 5.2-21, 5.4.3.6, pressure/temperature operating limits, LTOPS setpoints, 5.4.3.6.1, 5.4.3.6.3.2, 5.4 Refs, and LTOPS enable temperatures. [10 CFR 50.90 License Tables 5.4-2 & 5.4-3 Amendment]

[FN 2000-048]

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

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

[10 CFR 50.61]

6.2.4.1, 6.2 Refs Documented the evaluation of isolated water-filled

[FN 99-016] 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, Provided additional description of the fuel transfer tube 9.1.4.6.3 design, the function of its isolation valve, and associated

[FN 99-076] test requirements.

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

[FN 2001-010] generation analysis.

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

[FN 99-054] 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 recirculation

[FN 2000-027A] 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 head safety

[FN 2000-006] 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 station service

[FN 2000-046] 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 analysis

[FN 2001-018] results for various refueling scenarios.

Revision 4509/30/09 NAPS UFSAR 42 Revision 3709/04/01 (continued)

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

9.2.1.2.1, 9.2.1.2.2, 9.2.1.3.1, Clearly defined the number of service water system 9.2.1.2.3 reservoir spray arrays that are required to be operable to

[FN 2000-049] meet minimum design basis requirements.

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

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

9.6.4.1 Deleted the requirement for Station Nuclear Safety and

[FN 2000-044] 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 the reactor

[FN 2000-043] 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, Modified organizational titles and reporting relationships 17.2.1.2, 17.2.2.1, 17.2.2.5, 17.2.3, associated with the entire Nuclear Business Unit.

17.2.7, 17.2.10, 17.2.15, 17.2.16.2, [10 CFR 50.54(a)(3)]

17.2.17, 17.2.18, Figures 17.2.1-1, 17.2.1-2, & 17.2.1-3, Table 17.2-0

[FN 2001-015]

15.2.6, 15.2.6.1, 15.2.6.1.1, Reflected the current design bases that credit Technical 15.2.6.1.2, 15.2.6.2, 15.2.6.2.1, Specification controls with precluding the preconditions 15.2.6.2.1.2, 15.2.6.2.2, for significant and uncontrolled reactivity insertion 15.2.6.2.2.2, 15.2.6.2.3, during the startup of an inactive loop. Incorporated 15.2.6.2.3.2, 15.2.6.3, 15.2.6.3.1, conservative analysis of reactivity effects of the isolated 15.2.6.3.2, 15.2.6.4 loop recirculation activity required by Technical

[FN 2000-047] Specifications.

15.2.7.2.1, Table 15.2-1, Updated the analysis of the Loss of External Electric Figures 15.2-20, 15.2-21, 15.2-22, Load and/or Turbine Trip transient.

15.2-23, 15.2-24, 15.2-25, 15.2-26, 15.2-27, 15.2-28, 15.2-29, 15.2-30,

& 15.2-31

[FN 2001-005]

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 experience for a

[FN 2001-017] bachelors degree. [10 CFR 50.54(a)(3)]

Revision 4509/30/09 NAPS UFSAR 43 Revision 3709/04/01 (continued)

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

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

[FN 2000-004] ANSI N45.2.9 or applicable regulations.

[10 CFR 50.54(a)(4)]

Revision 4509/30/09 NAPS UFSAR 44 Revision 3609/01/00 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

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

2.4.3.4, 2.4.3.5, 2.4.3.6, 2.4.8, Tbl 2.4-6, Figs 2.4-4 & 2.4-7 thru 2.4-15, 2.5.4.3, 2.5.5, Fig 2.5-3, 2A.2.1, 2A.2.4.1.1, 2A.2.4.1.2, 2A.2.5.3, 2A.2.7, 2A.2.8, 3.2.2, Tbl 3.2-1, 3.3.2, 3.5.3, 3.5.4, 3.5.5, Tbl 3.5-5, 3.7.1, 3.7.2, 3.7.2.1, 3.7.2.3, 3.7.2.5, 3.7.2.6, 3.7.2.7, 3.7.2.7.1.7, 3.7.3.1.1, 3.7.3.1.2.2, 3.7.3.1.2.4, 3.7.3.2.2.2, 3.7.5, 3.7 Refs, Tbls 3.7-3 thru 3.7-8, 3.8.1.1.1, 3.8.1.1.5, 3.8.1.1.6, 3.8.1.2, 3.8.1.2.1, 3.8.1.4.7, 3.8.2.1.4.1, 3.8.2.1.4.4, 3.8.2.5, 3.8.2.7.6.1.2, 3.8.2.7.6.1.2.1, 3.8.2.7.6.1.2.2, 3.8.2.7.6.1.2.3, 3.8.2.7.6.1.2.4, 3.8.2.7.6.1.2.5, 3.8.2.7.6.2, 3.8.2.7.6.2.1, 3.8.2.7.6.2.2, 3.8.2.7.6.2.3, 3.8.2.8.1.8, 3.8.3.5, 3.8.4.5.3, 3.8.4.6, 3.8.4.7.5, 3.8.4.7.7, 3.8.4.8, 3.8.5.4, 3.8 Refs, 3.8 RefDwgs, Tbls 3.8-1 thru 3.8-6, 3.8-12, 3.8-15, 3.8-16,

& 3.8-19, Figs 3.8-1, 3.8-4, 3.8-12, 3.8-20, 3.8-21, 3.8-23 thru 3.8-25, 3.8-30, 3.8-31, 3.8-35, 3.8-38, 3.8-39, 3.8-42, & 3.8-52 thru 3.8-59, 3.9.1.2.4, 3.9.1.2.4.1, 3.9.1.2.4.2, 3.9.1.2.6, 3.9.2.2, 3.9.3.3.1, 3.9.3.3.2, Fig 3.9-1, 3.10.1, 3.10.2, 3.10 Refs, Tbl 3.10-1, 3.11 Refs, Tbl 3.11-4, App. 3E, Tbl 3E-8, App. 3E Att. 2, App. 3E Att. 4, App. 3E Att. 5 Fig. 8, 11, & 12, App. 3E Att. 6, 5.2.1.2, 5.2.3.3.2, 5.5.1.4.1, 5.5.1.4.2, 5.5.1.4.2.1, 5.5.1.4.2.2, 5.5.1.4.2.3, 5.5.1.4.2.4, 5.5.1.4.3, 5.5.3.1, 5.5.9.2.2, 5.5.9.3.3, 7.9.1, Tbl 9.6-1, 9B.4.1

[FN 99-014]

Revision 4509/30/09 NAPS UFSAR 45 Revision 3609/01/00 (continued)

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

KWI, 2.3.3.1.2, Table 3.2-1, Corrected cross-references, typographical and editorial 3.7.2.1, 3.7.2.6.1.7, 3.7.3.1.1, errors, and electronic scanning discrepancies and 3.7.3.1.2.3, 3.7.3.1.2.4, standardized equation and footnote notations.

3.7.3.1.2.5.1, 3.7.3.1.3.2, 3.7.3.2.2.2, 3.8.5, Figure 3.8-32, 4.3.2.2.6, 4.3.2.8.2, 5.5.9.3.3, 5A Att. 1 Table 1, 6.2.1.3.2.5, Table 6.2-52, Tables 6.2-52

& 6.2-54, 6.4.1.5, Table 6A-1, 9.2.2.1, Table 9.2-5, 9.3.3.1, 9.5.1.1, Table 11.5-1

[FN 99-048]

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

3.9.2.1, Table 3.11-3, 3A, 3A.20, Table 3A-1, 9.1.3.2, 9.1.3.3.1, 9.1.3.3.3, Table 9.1-2, Figures 9.1-1 & 9.1-3, 9.2.2.1.2, 9.2.2.1.3, 9.2 RefDwgs, Figures 9.2-3 & 9.2-4, 10.2.1.2, 10.2.1.7, Figures 10.2-1 & 10.2-2, 10.4.7.2, Figure 10.4-9

[FN 99-069]

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

Chapter 11, 11.2.1, 11.2.2, 11.2.2.2, 11.2.3, 11.2.5, 11.2.5.1, Table 11.2-1, Figures 11.2-1 through 11.2-4, 11.4.4.1, 11.5, 11.5.2.1, 11.5.2.4, 11.5.3, 11.5.3.1, 11.5.3.2, 11.5.3.3, 11.5.4, 11.5.5, Tables 11.5-1 & 11.5-2, Figure 11.5-3, 11.6.3

[FN 99-043]

Revision 4509/30/09 NAPS UFSAR 46 Revision 3609/01/00 (continued)

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

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

8.3.1.1.1, 8.3.1.1.2.3, 8.3.1.2, 8.3.1.2.1, 8.3.1.2.2.3

[FN 99-042]

1.2.11, Tables 3.2-1 & 3.9-2, Incorporated technical and editorial corrections and 3.11.1.1, Tables 3.11-1 & 3C-3, clarifications related to chemical and volume control 5.2.3.2, Table 5.2-19, 6.3.2.1.2, system.

9.3.4.1, 9.3.4.1.2, 9.3.4.2.1, 9.3.4.2.2.1, 9.3.4.2.2.3, 9.3.4.2.2.4, 9.3.4.2.4, 9.3.4.2.4.1, 9.3.4.2.4.2, 9.3.4.2.4.5, 9.3.4.2.4.8, 9.3.4.2.4.9, 9.3.4.2.4.13, 9.3.4.2.4.16, 9.3.4.2.4.22, 9.3.4.2.4.23, 9.3.4.2.5.1, 9.3.4.3.1, 9.3.5.2, Tables 9.3-5 & 9.3-6, Figure 9.3-5, 12.1.2.7, 15.2.4.1

[FN 99-030]

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, Incorporated technical and editorial corrections and 2.3.3.2.4, 2.3.3.2.5.1, Table 2.3-15, clarifications related to the electrical instrumentation 3.11.2.10, 7.7.1.4 system.

[FN 2000-019]

2.4 Update the description of the service water reservoir

[FN 99-049] spray array freeze protection.

Revision 4509/30/09 NAPS UFSAR 47 Revision 3609/01/00 (continued)

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

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

Tables 6.2-48, 6.2-49, & 6.2-51, 6.3.2.1.4.1, 6.4.1.1, 6.4.1.2, 6.4.1.3, 6.4.1.3.1, 6.4.1.3.3, 6.4.1.4, 7.7.1.12.1, 7.7.1.13, 9.2.3.1, 9.4.1.1, 9.4.1.2, 9.4.1.3, 9.4.1.4, 9.4.1.5, 9.4.1.6, 9.4.2.1, 9.4.2.2, 9.4.2.3, 9.4.3.1, 9.4.3.2, 9.4.3.3, 9.4.3.4, 9.4.4.3, 9.4.5.1, 9.4.5.2, 9.4.5.3, 9.4.5.6, 9.4.5.7, 9.4.6.1, 9.4.6.2, 9.4.6.3, 9.4.6.4, 9.4.6.5, 9.4.7.1, 9.4.7.2, 9.4.7.3, 9.4.7.4, 9.4.7.5, 9.4.8, 9.4.8.1, 9.4.8.2, 9.4.8.3, 9.4.8.5, 9.4.9.1, 9.4.9.2, 9.4.9.3, 9.4.9.4, Tables 9.4-2 & 9.4-4, Figures 9.4-1 through 9.4-6, 9.5.1.2.2.1, 9.5.9.2, 9.5.10.3, Table 9.5-5, 11.3.5.7, 11.3.5.8, 12.1.2.10, 12.2.1, 12.2.2, 12.2.2.4, 12.2.4, 12.2.5.2, 15.4.5.2.3

[FN 99-044]

3.1.42.2, Table 3.9-1, 9.2.2.1.3, Incorporated technical and editorial corrections and 9.2.2.2.1, 9.2.2.2.4, 9.2.2.3.1, clarifications related to component cooling water system.

9.2.2.3.3, 9.2.2.5.1, Tables 9.2-5, 9.2-8, & 9.2-9, Figures 9.2-2

& 9.2-3

[FN 99-053]

Revision 4509/30/09 NAPS UFSAR 48 Revision 3609/01/00 (continued)

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

3.1.46.2, 3.1.47.2, 3.1.48.2, Incorporated technical and editorial corrections and 3.11.2.3, 5.2.4.1.1, 6.1, 6.2.1.1.1.1, clarifications related to containment systems.

6.2.1.2.6, 6.2.1.2.9, 6.2.1.2.13, 6.2.1.3.1.1, 6.2.1.3.2.1, 6.2.1.3.2.3, 6.2.1.3.2.4, 6.2.1.3.2.5, 6.2.1.3.2.6, 6.2.1.4.2, 6.2.1.4.3, 6.2.1.4.4, 6.2.2.1, 6.2.2.2, 6.2.2.3, 6.2.2.3.2.4, 6.2.2.3.2.7, 6.2.2.3.3, 6.2.4.4, 6.2.6.2, 6.2.6.3, 6.2.7, 6.2.7.2, 6.2.7.3, 6.2.7.4, 6.2.7.5, 6.2 Refs, Tables 6.2-22 through 6.2-28, 6.2-30, 6.2-34 through 6.2-37, 6.2-39, & 6.2-58, Figures 6.2-11, 6.2-13, 6.2-15 through 6.2-18, 6.2-27, 6.2-28, 6.2-46, 6.2-84, & 6.2-85, 6.3.3.12, Table 6.3-8

[FN 99-020]

3.1.53.2, 4.2.1.4.1, 4.2.1.4.2, Incorporated technical and editorial corrections and 6.2.2.2, 9.1.1, 9.1.2, 9.1.4.2, clarifications related to the fuel handling system.

9.1.4.3.1, 9.1.4.4.1, 9.1.4.4.4, 9.1.4.4.6, 9.1.4.4.8, 9.1.4.4.10, 9.1.4.4.12, 9.1.4.5, 9.1.4.6.6.1, 9.1.4.7, Figure 9.1-4

[FN 99-067]

3.6.2.3 Revised the list of piping runs subject to augmented

[FN 96-038] inservice inspection. [10 CFR 50, Appendix A, GDC 4]

Revision 4509/30/09 NAPS UFSAR 49 Revision 3609/01/00 (continued)

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

3.6.2.3, 3.6.2.4, 3.6.2.5.3, Incorporated technical and editorial corrections and 3.6.3.2.1, 3.6.3.2.2, 3.6.3.3, clarifications related to the high energy line break report.

3.6 Refs, 3C.1.1, 3C.1.2, 3C.1.3, 3C.2.7, 3C.2.7.1, 3C.2.7.2, 3C.2.7.3, 3C.2.7.9, 3C.4.3, 3C.5.1.1, 3C.5.1.1.1, 3C.5.1.1.2, 3C.5.1.1.3, 3C.5.1.2.2, 3C.5.1.8.1, 3C.5.2.1, 3C.5.4.1, 3C.5.4.6.2, 3C.5.4.9, 3C RefDwgs, Tables 3C-1 through 3C-4,

& 3C-7, Figures 3C-3, 3C-12, 3C-13, 3C-22 through 3C-24,

& 3C-26, 3F.1, 3F.3, 3F.4, 3F Refs, Tables 3F-1, 3F-3 through 3F-7, Figures 3F-1, 3F-4, 3F-6, 3F-7, 3F-12, App 5A Att.1 Table 1, 9.3.4.2.5.2

[FN 99-072]

3.8.2.1.4 Incorporated a description of the containment liner repair

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

3.8.2.1.4.1, 5.5.4.3.1, 5.6.2.1, Incorporated technical and editorial corrections and 6.4.1.3.2, 7.2.2.3.2, 7.2.2.3.4, clarifications related to the fire protection system.

8.3.1.1.2.6, Table 9.2-10, 9.3.3.2, 9.4.8.5, 9.5.1, 9.5.1.1, 9.5.1.2.2.1, 9.5.1.2.2.2, 9.5.1.2.3, 9.5.1.2.4.4, 9.5.1.3.1.1, 9.5.1.3.1.3, 9.5.1.3.1.8, 9.5.1.3.1.10, 9.5.1.3.1.11, 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 calculating

[FN 2000-029] service water reservoir losses.

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

[FN 97-053A] numbers. [10 CFR 50.90 License Amendment]

Revision 4509/30/09 NAPS UFSAR 50 Revision 3609/01/00 (continued)

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

3.9, 6.2.2.2, 7.7.1.14, 9.1.3.3.3, Incorporated editorial changes consisting of grammatical Tables 9.2-6, 10.2-7, & 10.2-8, enhancement, correction of typographical errors and 15.2.10.3.2, Tables 15.4-5 cross-references, and consistent use of terminology,

& 15.4-6 capitalization, and punctuation.

[FN 2000-005]

3.9.2.1, 10.3.1 Clarified the design code for the main steam safety

[FN 99-056] system valves.

Table 3.9-1, 5.5.2.2, 9.2.3.2, Incorporated technical and editorial corrections and 9.2.3.2.2, 10.1, 10.4.3.2, 10.4.4.3, clarifications related to feedwater, condensate, steam 10.4.6.2, 10.4.6.3, 10.4.6.5, generator blowdown, and condensate polishing systems.

10.4.8.2, 10.4 Refs, Tables 10.4-2

& 10.4-4, Figure 10.4-4

[FN 99-021]

3.11.1.3.1, 3.11.1.3.2, 3.11.1.3.3, Incorporated technical and editorial corrections and 3.11.2.2, 4.2.3.5, 5.5.1.3.9, clarifications related to nuclear control system.

7.2.2.3.2, 7.5.1, 7.5.2, Tables 7.5-1 through 7.5-3, 7.7.1.3.3, 7.7.1.4.2, 7.7.1.8.2, 7.7.2.2, 7.7.2.6, Table 7.7-1, Figures 7.7-1, 7.7-3, 7.7-5, 7.7-9, 7.7-10, & 7.7-12

[FN 99-057]

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

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

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

[FN 2000-010] 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 and

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

Revision 4509/30/09 NAPS UFSAR 51 Revision 3609/01/00 (continued)

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

Chapter 4, 4.1, 4.4 Refs, Incorporated technical and editorial corrections and Tables 4.1-1 & 4.1-2, 4.2.1.1.1, clarifications related to the reactor design (mechanical).

4.2.1.1.2, 4.2.1.2, 4.2.1.2.1, 4.2.1.2.2, 4.2.1.3.1, 4.2.1.3.2, 4.2.1.4.2, 4.2.1.4.4, 4.2.2.1, 4.2.3.1.1, 4.2.3.1.3, 4.2.3.2, 4.2.3.2.1, 4.2.3.2.2, 4.2.3.3.1, 4.2.3.3.2, 4.2 Refs, Figures 4.2-6 through 4.2-8, 4.2-10, 4.2-11,

& 4.2-16 through 4.2-27

[FN 2000-013]

4.2.1.4.3 Updated the new fuel and insert component inspection

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

4.2.3.4.2 Incorporated a discussion of the allowance, taken to

[FN 99-046] account for seismic activity, in the control rod drop time test criteria.

5.1.3.5, 5.1 Refs, 5.5.4.1, Incorporated technical and editorial corrections and 5.5.4.2.1.1, 5.5.4.2.1.3, 5.5.4.2.2.1, clarifications related to residual heat removal system.

5.5.4.2.2.3, 5.5.7.2, 5.6.1, 7.6.2.1

[FN 99-045]

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

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

5.5.1.2, 5.5 Refs Updated the design description of the reactor coolant

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

5.5.10.2, 5.5.10.3 Modified the reactor head vent line to provide clearance

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

6.2.1.2.5 Corrected the description of the structural integrity of the

[FN 2000-031] neutron shield surge tank.

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 format

[FN 2000-039] errors.

Revision 4509/30/09 NAPS UFSAR 52 Revision 3609/01/00 (continued)

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

6.4.1.3.3, Table 6.4-1 Updated the description of potentially hazardous

[FN 99-071] 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 system in

[FN 97-020] accordance with approved plant modifications.

8.3.1.1.2.3, 8.3.1.1.2.5, 8.3 Refs, Incorporated technical and editorial corrections and Table 8.3-8, 9.5.2.1.2, 9.5.2.1.3, clarifications related to the electrical and communication 9.5.2.1.4, 9.5.2.2.1, 9.5.2.2.2, systems.

9.5.2.2.3, 9.5.2.2.4, 10.2

[FN 2000-002]

9.1.3.2, Table 9.1-1, 9.3.4.2.2.3, Added descriptions of the administrative controls applied Table 9.3-5 to the filters for the chemical volume and control system

[FN 99-074] and refueling purification system.

9.2.2.1.1, 9.3.2.1.1, 9.3.2.1.3, Incorporated modifications to the on-line chemistry Table 9.3-2, 10. 4.7.2 monitoring system.

[FN 97-055]

9.2.2.1.2, 9.2.2.2.2, 9.2.2.3.1, Added notes reflecting that some steam generator 9.2.2.3.2 sampling coolers have been abandoned in place.

[FN 97-010]

9.2.2.1.2, 9.2.2.2.2, 9.2.2.3.2, Incorporated a plant modification that allows the Unit 1 10.4.7.2 isolated phase bus duct air cooler to be supplied by

[FN 99-023] chilled water as an alternative to bearing cooling.

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

[FN 97-050] component cooling water heat exchangers to reflect a design modification.

9.3.1.2, 9.3.1.3, 9.3.1.3.1, Incorporated technical and editorial corrections and 9.3.1.3.2, Table 9.3-1, clarifications related to instrument air system.

Figure 9.3-1, 9.5.10.3, 10.3.2

[FN 2000-003]

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

[FN 99-051]

Revision 4509/30/09 NAPS UFSAR 53 Revision 3609/01/00 (continued)

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

9.3.2.1.2 Add a discussion of the on-line chemistry monitoring

[FN 98-042] system.

9.3.2.1.5 Clarified the use of the on-line chemistry monitoring

[FN 99-068] system panel.

9.3.4.2.4.7 Augmented the description of purging gases from the

[FN 2000-009] 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 emergency

[FN 99-033] switchgear room halon system.

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

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

Table 10.4-2 Revised design data to reflect the replacement moisture

[FN 96-074 & FN 99-035] separator-reaheaters on Units 1 and 2.

Table 10.4-4, 15.2.8.1, 15.2.8.2.1, Incorporated changes resulting from the revised loss of 15.2.8.2.2, 15.2.8.3, 15.2.9.1, normal feedwater accident analysis.

15.2.9.2.1, 15.2.9.2.2, Table 15.2-1, Figures 15.2-28 through 15.2-35

[FN 99-047]

13.2.1, 16.1 Corrected reference from Environmental Technical

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

13.4 Updated the name of the subcommittee responsible for

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

15.2.10.1 Corrected the description of feedwater pump discharge

[FN 99-041] 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, Incorporates a summary of the peak clad temperature Table 15.3-4, 15.4.1.5.3, penalties and benefits for the small and large break 15.4 Refs, Table 15.4-5 LOCA which are reported per 10 CFR 50.46

[FN 99-070] requirements.

Revision 4509/30/09 NAPS UFSAR 54 Revision 3609/01/00 (continued)

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

15.3.5.2 Corrected the values of total activity assumed to be

[FN 99-055] 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, Modified organizational titles and reporting relationships Figure 17.2.1-1 associated with information technology.

[FN 2000-032]

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

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

17.2.1.2, Figure 17.2.1-2 Modified organizational titles and reporting relationships

[FN 2000-017] associated with records management.

17.2.1.2, Figure 17.2.1-2 Modified organizational titles and reporting relationships

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

Revision 4509/30/09 NAPS UFSAR 55 Revision 3509/01/99 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

KWI, 1.2.12, 2.1.1.1, 2.1.1.2, Incorporated technical and editorial corrections and 2.1.2.1, 2.1.2.2, 2.1.3.3, clarifications related to the service water system.

Table 2.1-2, 2.2.1.3, 2.2.1.5, 2.3.2.2.1, 2.3.2.4, 2.4.1.1, 2.4.1.2, 2.4.2.2, 2.4.3, 2.4.4, 2.4.8, 2.4.10, 2.4.11.1, 2.4.11.4, 2.4.11.5, 2.4.11.6, Table 2.4-2, 2.5.4.1, 2.5.4.2, 2.5.5, Table 2.5-1, 2A.2.2, 2A.2.3.1, 2A.2.4.1.1, 2A.2.4.1.2, 2A.2.4.1.3, 2A.2.5.1, 2A.2.5.2, 3.4, 3.8.1.1.7, 3,8.1.1.9, 3.8.2.1.3, 3.8.3.1, 3.8.3.2, 3.8.4.1, 3.8.4.5.2, 3.8.4.5.4.7, 3.8.4.5.4.8, 3.8.4.6, 3.8.4.7.5, 3.8.4.8, Table 3.9.1, 3.11.2.6, 3.11.2.7, 3.11.2.8, 3.11.2.9, 3.11.2.10, Table 3.11-2, 3A.27, 3E.2.1, 9.2.1.1, 9.2.1.2.1, 9.2.1.2.2, 9.2.1.2.3, 9.2.1.2.4, 9.2.1.2.4.1, 9.2.1.2.5, 9.2.1.3, 9.2.1.3.1, 9.2.1.3.2, 9.2.1.4.1, 9.2.1.6, 9.2.2.2.4, 9.2.3.2.2, 9.2.5, 9.2.5.1, 9.2.5.2, 9.2.5.3, 9.2 Refs, 9.2 Ref Dwgs, Tables 9.2-1, 9.2-3,

& 9.2-4, Figure 9.2-1, 9.4.1.2, 9.4.10.2, 9.5.1.2.1, 9.5.1.3.2, 10.1, 10.4.2.2, 11.2.3, 11.2.5.1, 11.2.8, Tables 11.2-16 & 11.2-19, 11.4.2.1, 11.4.2.10, Table 11.4-2, 11.6.3.6, 11B.1, 11B.2.1, 11B.2.2, 11B.4, 11B.4.1.1, 11B.4.1.4, 11B.4.2.2, Tables 11B-4, 11B-6, 11B-7, & 11B-9, 15

[FN 98-043]

Revision 4509/30/09 NAPS UFSAR 56 Revision 3509/01/99 (continued)

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

KWI, 1.2.3, 4.2.3.5, 5.5.2.3.5, Incorporated technical and editorial corrections and 6.2.4.1, 6.2.4.2, 7.3.1.3.5.4, clarifications related to the main steam system.

Table 7.5-3, 7.7.1.8, 7.7.1.8.1, 10.1, Figures 10.1-1 and 10.1-2, 10.2, 10.3.1, 10.3.2, 10.3.3, 10.3.3.2, 10.3.4, 10.3 RefDwg, Tables 10.3-1 through 10.3-4, Figures 10.3-1 and 10.3-3, 10.4.1.2, 10.4 RefDwg, 15.4.2.1.1

[FN 98-031]

KWI, 2.3.5.1, 2.4.11.5, Corrected references, spelling, and format.

Table 3.2-1, 3.4, 3.7.2.4, 3.7.3.1.1,

& Tables 3.7-4, 6.2-45, 9.6-1, &

15.4-10

[FN 98-046]

KWI, Ref Dwgs: 1.2, 2.4, 2.5, 3.6, Corrected a Key Word Index reference, supplemented the 3.8, 3C, 5.1, 5.5, 5.6, 6.2, 6.3, 6.4, reference drawings lists, and corrected text citations of 7.1, 7.3, 7.7, 8.1, 8.2, 8.3, 9.1, 9.2, reference drawings.

9.3, 9.4, 9.5, 9A, 10.2, 10.3, 10.4, 11.2, 11.3, 11.4, 11.5, 11C, 12.1, 12.2, 12.3, 14.1, 15, 15.4; Sections 2.4.2.2, 2.4.11.5, 2.4.13.1, 5.1.5.1, 5.5.4.2, 6.2.1.2.18, 6.3.2, 8.1.2, 8.3.1, 8.3.1.1, 8.3.1.1.1, 8.3.2.1, 9.2.1.2.4, 9.2.1.2.4.1, 9.2.1.2.4.2, 9.4.9.1, 9.4.10.2, 10.4.3.2, 10.4.4.3, 10.4.5.2, 10.4.6.2, 10.4.7.2, 10.4.8; Tables 2.4-8, 2.4-9, 5.5-6, 9.4-4

[FN 99-003]

Revision 4509/30/09 NAPS UFSAR 57 Revision 3509/01/99 (continued)

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

KWI, Table 3.5-1, Table 6.2-46, Corrected cross-references, typographical errors, and 6.3.2.1.1, 6.3.2.1.4.6, 6.3.3.12, electronic scanning discrepancies; improved consistency 6.3.5.3.2, 7.1, 7.1.3.1, 7.2.2.2.2, of exponent, numerical, and Greek letter notation; 7.2.2.2.3, 7.2.2.2.4, 7.2.2.2.5, improved consistency of abbreviations; and incorporated 7.2.2.2.6, 7.2.2.2.8, 7.2.2.2.9, two tables omitted from a previous UFSAR change.

7.3.2.1, 7.5.2, 7.6.2.2, 7.6.3.2, 7.6.5, 7.6 Refs, 7.9.1, 7.9 Refs, 9.2.3.2.1, Table 9.2-3, 11.3.5.4, Table 12.1-4, 12.2.6, 15.2.6.2.2.2, 15.2.13.2.2, Table 15.4-5, Table 15.4-6.

[FN 99-012]

1.2.10, 2.4.11.5, 2.4.11.6, Incorporated technical and editorial corrections and Table 2.4-7, 10.4.2.3, clarifications related to the circulating water system.

Figures 10.4-1 and 10.4-2

[FN 99-027]

Ref Dwgs: 1.2, 2.4, 2.5, 3.6, 3.8, Clarified the reference drawings lists by spelling out 3C, 5.1, 5.5, 5.6, 6.2, 6.3, 6.4, 7.1, words abbreviated in the titles and using consistent 7.3, 7.7, 8.1, 8.2, 8.3, 9.1, 9.2, 9.3, punctuation.

9.4, 9.5, 9A, 10.2, 10.3, 10.4, 11.2, 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, Incorporated technical and editorial corrections and 1.3.1.4, 1.3.1.4.1, 1.3.1.4.2, clarifications related to the emergency power system.

1.3.1.5, 1.3.1.6, 1.3.2, Tables 1.3-1 through 1.3-13, 7.7.1.13.2, 8.1.2, 8.1 RefDwg, 8.3.1.1.1, 8.3.1.1.2.2, 8.3 RefDwg

[FN 99-002]

Revision 4509/30/09 NAPS UFSAR 58 Revision 3509/01/99 (continued)

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

Table 1.3-1, 3.8.4.1, Tables 3.9-1 Corrected cross-references, typographical errors, and

& 3, 3.11.2.2, Figure 4.3-6, electronic scanning discrepancies; improved consistency 5.1.2.1.3, Figure 5.1-2, 5.2.3.3.1, of upper and lower case and listing notation; improved 5.2.5.1, Tables 5.2-12, 22, & 28, superscript and subscript notation; and incorporated a list Figures 5.2-5, 6, 9, & 10, omitted from a previous UFSAR change.

5.4.3.6.1, 5.4.3.6.2, 5.4 Refs, 5.6.2.3, Figure 6.2-66, 7.7.1.5, 11.4.3.1.1, 15.4.1.7.2, 15.4.1.7.3

[FN 99-001]

Table 1.3-2, 3.1.33.2, Tables 3.9-2 Incorporated technical and editorial corrections and

& 3.11-1, 3A.1.2, 6.3.2.1.1, clarifications related to the safety injection system.

6.3.2.1.4.1, 6.3.2.1.4.2, 6.3.2.1.4.4, 6.3.2.1.4.5, 6.3.2.1.4.6, 6.3.2.1.5, 6.3.2.2.5, 6.3.3.5, 6.3.3.8.1, 6.3.3.10, 6.3.3.12, 6.3.4, 6.3.4.1, 6.3.4.2, 6.3.4.3, 6.3.4.4, 6.3.4.5, 6.3.5.2.1, 6.3 Refs, Tables 6.3-1, 6.3-2, and 6.3-4, through 6.3-6, Figures 6.3-1, 6.3-16, and 6.3-17, 6A.1, 9.5.10.2, 14.1, 14.1.1, 14.1.2, 14.1.2.1, 14.1.2.2, 14.1.2.3, 14.1.2.4, 14.1.3, 14.1.4, 14.1 Refs, Tables 14.1-1 through 14.1-5, Figures 14.1-1 through 14.1-3

[FN 99-008]

Table 1.3-2, 3.1.36.2, Table 3.9-1, Incorporated technical and editorial corrections and 3.11.22, 3A.1.2, 6.2.2.2, 6.2.2.2.2, clarifications related to the recirculation spray system.

6.2.2.2.3, 6.2.2.2.4, 6.2.2.3.2.1, 6.2.2.3.2.6, 6.2.2.4.2, 6.2.3.1.1, 6.2.3.3, Tables 6.2-4 & 6.2-42, Figures 6.2-50 & 6.2-68, 9.3.3.2

[FN 98-057]

Revision 4509/30/09 NAPS UFSAR 59 Revision 3509/01/99 (continued)

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

Tables 1.3-8, 1.3-9, & 1.3-10, Incorporated technical and editorial corrections and 3.1.55.2, 5.2.4.2, 7.7.1.12.2, clarifications related to the radiation monitoring system.

9.3.2.1.3, 11.2.3, 11.4.1, 11.4.2, 11.4.2.1, 11.4.2.13, 11.4.2.14, 11.4.2.14.1, 11.4.2.14.2, 11.4.2.15, 11.4.3, 11.4.3.1.1, 11.4.3.1.2, 11.4.3.1.3, 11.4.3.2, 11.4.4.1, 11.4.4.2, Tables 11.4-1 through 11.4-4, 12.1.4.1, 12.1.4.2, 12.1 RefDwg, Table 12.1-4, 12.2.4, 15.4.7.2.4.1, 14.4.7.2.4.2

[FN 98-050]

Table 1.3-12, 11.3.5.1, Revised the catalytic hydrogen recombiner description to Table 11.3-1, 11C.4.1.5 reflect that it is no longer used.

[FN 95-031]

2.1.3.4, 2.4.13.4, 3.1.52.2, 3A.4, Incorporated technical and editorial corrections and 3A.21, 3A.111, 3A.113, 11.1, clarifications related to the radiation protection system.

11.1.1.3, 11.1.1.4, Tables 11.1-7, 11.1-9, 11.1-11, & 11.1-12, 11.2.8, Table 11.2-4, 11.3.5, 11.3.5.1, 11B.4.1.1, 11.B.4.1.2, 11B.4.2, 11B.4.2.1, 11B.5, Table 11B-9, Figure 11B-1, 11C, 11C.1, 11C.2, 11C.3, 11C.4, 11C.4.1, 11C.4.1.2, 11C.4.1.3, 11C.4.1.4, 11C.4.1.5, 11C.4.1.6, 11C.4.1.7, 11C.4.2, 11C.4.3, 11C.4.4, 11C.4.5, 11C.5, 11C References, Tables 11C-1 through 11C-18, Figure 11C-1, 12.1.2.2, 12.1.2.5, 12.1.2.11, 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 hazardous

[FN 99-015] chemicals found on-site

Revision 4509/30/09 NAPS UFSAR 60 Revision 3509/01/99 (continued)

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

2.3.1.1, 2.3.2.1, Figure 2.3-23, Corrected cross-references, typographical errors, and 3.10.1, 3.11.2.8, 3A.32, 3A TOC, electronic scanning discrepancies; improved consistency 3F.4, Table 3F-8, 5.6.2.1, 6.2.2.2, of upper and lower case and listing notation; and Figure 6.2-65, 7.9 References, incorporated a title change.

Tables 8.3-6 & 7, Table 9.2-3, 11.1.1.3, 15.1.2.3, 17.2.16.2

[FN 98-060]

2.3.5.1, 3.1.3.2, Table 3C-3, Incorporated technical and editorial corrections and Figure 5.2-13, 9.5.10.3, 11.3.2, clarifications related to the gaseous waste system.

11.3.3, 11.3.3.2, 11.3.5.2, 11.3.5.3, 11.3.5.6, 11.3.5.10, Table 11.3-1, Figure 11.3-1, 11.4.4.2, Table 11.4-1, 12.2.4, 15.4.7.2.4.2

[FN 99-028]

2A.2.3.1, 2A.2.3.2, 2A.2.3.3, Corrected text cross-references.

2A.2.4.1.1, 2A.2.4.1.3, 2A.2.5.1, 2A.2.8

[FN 99-050]

Revision 4509/30/09 NAPS UFSAR 61 Revision 3509/01/99 (continued)

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

3.1, 3.1.11.2, 3.1.16.2, 3.1.17.2, Incorporated technical and editorial corrections and 3.1.20.2, Table 3.11-2, 4.3.1.7, clarifications related to the reactor protection system.

7.1.1, 7.1.3.2.3, 7.1.3.3.1.2, 7.1.3.3.3, 7.1.4, 7.1 Refs, 7.1 RefDwgs, 7.2.1, 7.2.1.1.1, 7.2.1.1.4, 7.2.1.1.5, 7.2.1.1.6, 7.2.1.3.1, 7.2.1.3.2, 7.2.1.8, 7.2.2.1.2.2, 7.2.2.2.1, 7.2.2.2.1.5, 7.2.2.2.1.7, 7.2.2.3.2, 7.2.2.3.3, 7.2.2.3.4, 7.2.2.3.5, 7.2.3.2, 7.2 Refs, Tables 7.2-1 through 7.2-4, Figures 7.2-1, 7.2-2, 7.2-3, 7.2-5 through 7.2-10, 7.2-12, & 7.2-13, 7.3.1.2, 7.3.1.31., 7.3.1.3.2, 7.3.1.3.2.1, 7.3.1.3.3.2, 7.3.1.3.5, 7.3.1.3.5.1, 7.3.2.1.4, 7.3.2.1.5.2, 7.3.2.1.5.6, 7.3.2.1.5.8, 7.3.2.1.5.11, 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, Incorporated technical and editorial corrections and 5.1.1.9, 5.1.2.1, 5.1.2.1.1, clarifications related to the Reactor Coolant System.

5.1.2.1.2, 5.1.2.1.3, 5.1.2.2, 5.1.2.3, 5.1.2.4, 5.1.3.1, 5.1.3.3, 5.1 Ref Dwgs, Figures 5.1-1

& 5.1-2, 5.5.4.2.2.3, 5.6.2.2, 5.6.2.3, 5.6 Refs Dwgs, Figure 5.6-1, 7.2.2.3.3, 7.2.2.3.4, 7.7.1.5, 7.7.1.6

[FN 98-017]

Revision 4509/30/09 NAPS UFSAR 62 Revision 3509/01/99 (continued)

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

3.1.53.2, 9.1.1, 9.1 Refs Added clarification that criticality monitors are not

[FN 97-060] 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, Corrected errors associated with table formatting, text 3.8.2.1.4.2, App. 3E Att. 4, App. cross-references, typographical entries, implementation 3E Att. 5, 5.5.9.3.1, 5.5.9.3.2, of a previous update, and punctuation.

9.2.1.4.1, Table 9.3-7, Table 10.4-2.

[FN 99-038]

3.8.2.7.6.2.4, Table 3.8-11 Clarified the description of unqualified coatings in

[FN 98-053] containment.

3.8.4.7.7, 3.8.4.8, 3.8 Refs, Incorporated new piezometers locations and editorial Table 3.8-17, Figures 3.8-32, corrections.

3.8-33, and 3.8-61

[FN 97-053]

Table 3.8-12, Figure 3.8-24 Updated the locations of piezometers at the main dam.

[FN 98-051]

Table 3.8-14 Corrected the factors of safety applicable to the service

[FN 97-041] water reservoir dikes.

Table 3.11-2, 6.2.2.3, Corrected spelling and typographical errors, eliminated Table 6.2-37, 6.3.3.12, 6.4.1.3.3, duplicate phrases, updated text figure references, Table 6.4-1, 7.2.2.1.2, 7.2.2.1.2.1, corrected punctuation, spelled out a non-standard Table 11.1-11, 11.2.8, 11B.2.1, acronym, standardized a system title, and capitalized the 11B.2.2, 11B.4, 11B.4.1.1, titles of computer codes.

11B.4.1.4, 11B.4.2.2, Tables 11B-4, 11B-6, & 11B-7, 12.1.2.11

[FN 99-022]

3A, 7.4, 8.1, 8.3, 9.5, 14.1 Incorporated technical and editorial corrections and

[FN 98-045] clarifications related to the Emergency Diesel Generator System.

Revision 4509/30/09 NAPS UFSAR 63 Revision 3509/01/99 (continued)

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

3A.22, 4.4.5.1, 4.4.5.2, Incorporated technical and editorial corrections and Figures 4.4-20 and 4.4-21, 7.1, clarifications related to the nuclear instrumentation 7.2.3.4, Figure 7.2-5, 7.3.2.1.5.10, system.

Figure 7.3-9

[FN 99-024]

3C.1.1, 3C.2.7, 3C.2.7.1, Reduced the number of weld inspections required to be 3C.5.1.2.2, 3C.5.1.8.2, 3C.5.2.8.2, performed on high energy piping outside containment.

3C Refs [NRC Safety Evaluation Report]

[FN 96-007]

4.1, Table 4.1-1, 4.2.3.2.2, Incorporated changes to reflect removal of the Unit 2 5.2.3.1.1, 5.4.2 part-length control rod drive mechanisms.

[FN 98-041]

4.3.2.2.6, 4.3.2.7, 4.3 Refs Reflected changes to reload design calculations,

[FN 96-046] 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.

5.2.1.1, 5.2.1.2, 5.2.2.1, 5.2.2.2, Incorporated technical and editorial corrections and 5.2.2.4, 5.2.3.1, 5.2.3.1.1, clarifications related to the Reactor Coolant System.

5.2.3.1.2, 5.2.3.1.3, 5.2.3.1.4, 5.2.3.1.5, 5.2.3.1.6, 5.2.3.1.7, 5.2.3.1.8, 5.2.3.1.9, 5.2.3.1.10, 5.2.3.1.11, 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]

Revision 4509/30/09 NAPS UFSAR 64 Revision 3509/01/99 (continued)

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

5.4.2, 5.4.3.6, 5.4.3.6.1, 5.4.3.6.2, Incorporated technical and editorial corrections and 5.4.3.6.3.1, 5.4.3.6.3.2, 5.4.3.7, clarifications related to the Reactor Coolant System.

5.4 References, Table 5.4-1, Figure 5.4-4, 5.5.1.3.1, 5.5.1.3.3, 5.5.1.3.10, 5.5.2.3.4, 5.5.2.3.5, 5.5.2.4, 5.5.3.2, 5.5.3.2.1, 5.5.3.3.1, 5.5.3.3.3, 5.5.4.3.4, 5.5.5.1.1, 5.5.5.3.2, 5.5.7.2, 5.5.8.2, 5.5.10.2, 5.5.10.3, 5.5 Ref Dwgs, Tables 5.5-1, 5, 6, & 12

[FN 98-036]

5.5.1.3.4 Clarified reactor coolant pump bearing integrity

[FN 96-090] 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 of RHR

[FN 97-023] MOVs.

5.5.8.2, 5.5.8.3 Added a description of the surveillance criteria and

[FN 95-032] 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 pressurizer

[FN 97-012] power-operated relief valve nitrogen reserve tanks.

5.5.9.3.3, Figures 5.5-16, 5.5-17, Removed vendor specific information from the

& 5.5-18 description of snubbers.

[FN 97-038]

6.2.1.4.3 Revised the description of the Type B test equipment,

[FN 97-028] 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 Service Water

[FN 96-059] Reservoir and corrected a reference in the text.

6.2.2.2 Clarified encapsulation of insulation inside containment.

[FN 98-055]

6.2.4.2 Corrected the description of the hydrogen recombiner

[FN 99-036] suction piping connection.

Revision 4509/30/09 NAPS UFSAR 65 Revision 3509/01/99 (continued)

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

6.2.6.3 Reverted the description of containment vacuum pumps

[FN 92-161A] to wording from the original FSAR.

Table 6.2-54 Revised the description of the outside recirculation spray

[FN 97-035] containment penetrations.

6.3.2.1.1 Added clarification on the applicability of the minimum

[FN 99-007] boron concentration requirement to the SI piping.

6.3.2.1.1, Table 6.3-4 Incorporated changes to the safety injection accumulator

[FN 97-043] test lines, level control descriptions, and sampling methods.

6.3.2.1.3.2, 6.3.3.1, 6.3.4.2, Incorporated revised ECCS analyses.

Figure 6.3-5

[FN 97-007 & FN 97-007A]

6.3.2.1.4.1, 6.3 Refs Added a description of design features that prevent

[FN 96-089] 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 valve

[FN 97-013] misfunction on ECCS flow discussion.

6.3.4.4 Reverted description of routine periodic testing of ECCS

[FN 92-125A] 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 checking proper

[FN 97-026] seating of the Unit 1 accumulator check valves.

6.3.5.2.3 Changed the description of provisions for testing

[FN 97-027] accumulator check valve seating to pressure taps from pressure indicators.

Tables 6.3-1 & 5 Reverted description of accumulator minimum pressure

[FN 92-127A] to that which preceded the present value supported by an inadequate safety evaluation.

Table 6.3-5, 8.3.1.1.1 Updated to reflect new charging pump interlocks.

[FN 96-017]

6.4.1.2 Added requirements if the fuel pit bridge radiation

[FN 97-058] monitor is out of service.

Revision 4509/30/09 NAPS UFSAR 66 Revision 3509/01/99 (continued)

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

6A.3.2, 12.1.2.10, 15.4.1.7, Revised the control whole body dose resulting from a 15.4.1.7.2, Table 15.4-7 LOCA.

[FN 98-056]

7.1, 7.2.1, 7.2 Refs, 7.3.1.3.2, Incorporated clarifications and editorial corrections and 7.3.1.3.5, 7.3.1.3.5.4, 7.3 Refs added a reference to the instrumentation section.

[FN 99-006]

Table 7.2-2 Corrected the reactor trip system over temperature delta T

[FN 99-029] range description.

8.1.2, 8.3.2.1, 8.3.2.2.4 Revised the description of the role of the station battery

[FN 95-039] swing chargers.

8.3.1.1.2.1 Revised the description of the emergency diesel generator

[FN 98-023] 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 results on Dow

[FN 96-053] 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 and

[FN 99-031] clarifications related to the 125V dc (emergency diesel) system.

9.1.1 Revised the description of new fuel container unloading

[FN 96-064] 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 over

[FN 97-002] irradiated fuel in accordance with Technical Specifications. [10 CFR 50.90 License Amendment]

9.1.3.1 Clarified the seismic classification and associated

[FN 98-039] contingency actions for refueling purification piping and equipment.

9.1.3.2 Added a description of the administrative controls for

[FN 96-043] isolation of the non-seismic portions of the refueling purification system.

9.1.4.4.4 Added a description of the manipulator crane in-mast

[FN 96-014] sipping system.

Figure 9.1-9 Changed the fuel transfer system drive to cable from an

[FN 96-048] air motor.

Revision 4509/30/09 NAPS UFSAR 67 Revision 3509/01/99 (continued)

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

9.2.1.2.2 Added an analysis of the impact of accumulation of

[FN 96-076A] 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 service

[FN 96-023] water pumps and clarified NPSH requirements.

9.2.1.3.1 Clarified the description of isolation of service water flow

[FN 96-067] 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 coupons in the

[FN 97-015] service water piping.

9.2.2.5.1 Revised the description of how the component cooling

[FN 97-008] system may be aligned to supply cooling loads.

9.2.3.2, 9.2.3.2.1, 9.2.3.2.2, Revised the description of the water treatment system to 10.4.7.2 say that the flash evaporator is obsolete and no longer

[FN 94-053] used.

Table 9.2-5 Revised the component cooling heat exchanger tube

[FN 97-025] material description.

9.3.1.2 Enhanced the description of the operation of the

[FN 97-017] 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 system,

[FN 96-071] post-accident required sample times.

9.3.2.2.2 Revised the description of the high radiation sampling

[FN 97-019] system containment sump pump.

9.3.4.1.3, 9.3.4.1.4, 9.3.4.2.2.3, Added descriptions of hydrogen peroxide user during 9.3.4.2.4.10, 9.3.4.3.2 refueling shutdown, clarified the potential effects of

[FN 97-047] demineralizer overheating, and incorporated editorial changes.

9.3.4.2.4.11 Added a description of hydrogen-form cation resin use in

[FN 98-022] mixed-bed demineralizers.

9.3.4.2.4.21.6 Revised the description of the capacity of the seal-water

[FN 96-083] return line relief valve.

Revision 4509/30/09 NAPS UFSAR 68 Revision 3509/01/99 (continued)

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

9.4.4.2 Allowed blocking Turbine Building grating ventilation

[FN 97-006] 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 for the

[FN 98-058] main and station service transformers.

10.2 Revised the throttle and governor valve stem freedom test

[FN 99-019] 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 valve use

[FN 98-004] during steam generator tube rupture events and revised the valve description.

10.3.2 Revised the normal relieving pressure of the atmospheric

[FN 97-014] steam dump valves.

10.4.3.3.1 Removed the auxiliary feedwater system from the list of

[FN 98-052] systems analyzed for steam-hammer and water-hammer occasional mechanical loading.

11.1.1.5, Tables 11.1-5 & 11.1-12, Revised the volume control tank analysis of effects and 15.3.6.2 consequences.

[FN 99-011]

11.3.2, 11.3.3, 11.3.3.2, 11.3.5.2 Revised the gaseous waste system description to reflect

[FN 97-036] 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 implemented

[FN 92-094A] change package.

11.4.3.1.1 Corrected the calibration sources used for effluent gas

[FN 97-022] monitors.

15.1.6, Table 15.1-2, Figure 15.1-3 Updated the Doppler reactivity coefficients to be

[FN 99-040] consistent with the accident analysis basis.

Revision 4509/30/09 NAPS UFSAR 69 Revision 3509/01/99 (continued)

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

15.1.6, Table 15.1-2, 15.2.2.1, Updated the results for the transient analysis of the 15.2.2.2.1, 15.2.2.2.2, 15.2.2.4, uncontrolled rod cluster control assembly withdrawal at Table 15.2-1, Figures 15.2-6 power (RWAP) accident.

through 15.2-13

[FN 99-034]

15.1.2.3, Table 15.1-3 Added current trip setpoint and response time values to

[FN 95-044] 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, Revised the description of the uncontrolled rod 15.2.1.3, 15.2.4.1, 15.2.4.2.1, withdrawal from subcritical and uncontrolled boron 15.2.4.2.2, 15.2.4.2.3, dilution transients to reflect current analyses of record.

Table 15.2-1, Figures 15.2-1 [10 CFR 50.90 License Amendment]

through 15.2-5

[FN 97-037]

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 interlocks

[FN 96-062] 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 of

[FN 99-039] 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, Reflected the current analysis of record for a fuel 15.4.7.2.4.3, 15.4.7.2.4.4, handling accident inside containment regarding Tables 15.4-16 thru 15.4.18 containment purge, exhaust valve closure times, and

[FN 98-048] radiation detector response times.

17.2.2.5 Clarified the qualification requirements of key Nuclear

[FN 98-059] Oversight personnel.

Table 17.2-0 Revised the description to indicate the both Innsbrook

[FN 98-047] record vaults meet ANSI requirements.

Revision 4509/30/09 NAPS UFSAR 70 Revision 34 Changes Made under the provisions of 10 CFR 50.59 except where Section indicated in brackets.

KWI, 1.5.2.1, 1.6, 2.5.2.5, Corrected references and typographical errors, and 3.1.37.2, 3.1.43.2, 3.8.2.1.4.1, clarified word spelling and illegible text.

Figures 3E-18 thru 3E-24, 4.3.2.7, 6.1, 6.2.1.2, 6.2.1.3.1, 6.2.1.3.1.1, 6.2.7.1, 6.3.2, 6.3.2.1.2, 6.3.2.1.5, 7.7.1.1, 9.3.4.2.2.4, 9.3.4.2.4.8, 9.3.5.1, 9.5.4.2, 11.3.3.2, 11B.3.3.3, 11C.4.1.1, 15.4.1.7, 15.4.1.7.2

[FN 98-038]

1.2.6, 9.1, App. 9B & App. 15A Updated descriptions of cask loading and unloading

[FN 98-014] 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 areas map.

[FN 98-020]

Table 2.4-7, 9.2.3.2.1, 10.4.2.2 Added raw lake water pumping system that supplies the

[FN 95-059] upgraded Reverse Osmosis System.

3.1.34.1, 3.1.35.1, 3.1.36.1, Incorporated technical and editorial corrections and 3.1.37.1, 3.1.39.1, 3.11.2.1, clarifications related to the Quench Spray System.

3.11 Refs, Table 3C-3, 6.2.2.2, 6.2.2.3.2.1, 6.2.2.4.1, 6.2.2.5.1, 6.2.3.4, Tables 6.2-40 & 6.2-42, Figure 6.3-8

[FN 97-057]

3.1.40.2, 3.1.42.1, & 3.1.42.2 Added AFW system to GDC 44, 45, and 46 applicability

[FN 97-054] discussions.

Revision 4509/30/09 NAPS UFSAR 71 Revision 34 (continued)

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

3.8.2.2, 6.2.1.1.1.2, 6.2.1.3.1.1, Updated containment analysis to reflect revised flowrates 6.2.2.1, 6.2.2.2, 6.2.2.3.2, for QS, IRS, ORS, and SW.

6.2.2.3.2.1, 6.2.2.3.2.6, 6.2.2.3.2.8, 6.2.2.3.3, Tables 6.2-2, 6.2-11, 6.2-14, & 6.2-38, Figures 6.2-7 thru 6.2-9, 6.2-64 thru 6.2-80, &

6.2-82 thru 6.2-86, 6.3.2.2.6

[FN 97-024]

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 system for

[FN 97-046] underground piping.

3.C.5.3, Table 3C-2, 9.2.3.2.2, Added high-capacity steam generator blowdown system.

10.4.6.2, Figures 11.2-3 & 11.2-4, 11.3.5.9, Table 11.4-1, 15.4.3.1

[FN 95-009]

6.2.1.3.1.2, 6.2.2.2, 6.2.3.3, Revised quench spray start times and annotated derivative 6.2.3.1.1, Tables 6.2-44 & 6.3-9 information.

[FN 98-001]

6.2.1.3.1.2, Table 6.2-18, & Table Clarified AFW pump flow sensitivity analysis.

10.4-4

[FN 97-056]

6.2.3.1, 6.2.3.1.1, 6.2.3.3, 6.2 Incorporated updated LOCA dose calculations.

References 27-41, Tables 6.2-47, 48 & 53 thru 62, 15.4.1.7, 15.4.1.8, 15.4.1.9.3, 15.4 References 59-67, Tables 15.4-5 thru 7, Figures 15.4-38 thru 41

[FN 98-012]

6.2.3.1.1 Revised post-LOCA containment sump pH.

[FN 97-061]

6.2.4.2, 6.2 References, Table Provided for partial draining of several containment 6.2-37 penetrations which are isolated during normal power

[FN 97-039] operation.

Revision 4509/30/09 NAPS UFSAR 72 Revision 34 (continued)

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

6.2.5.3, 6.2 Refs, Tables 6.2-66 & Revised calculation of post-LOCA containment hydrogen 6.2-71, Figures 6.2-98 thru concentration.

6.2-111

[FN 96-008]

7.2.1.1.5, 7.2.1.1.6, 7.2.2.3.5, Clarified design and licensing basis for AMSAC C-20 7.7.1.14, 7.7 Refs arming setpoint.

[FN 98-019]

7.2.2.2.1.7 Revised testing sequence for reactor trip breakers and

[FN 98-005] 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 conform with

[FN 97-054] standard format (system-component-id).

7.3.1.3.5.3 Expanded discussion about motor-driven AFW pump

[FN 97-054] interlocks and turbine-driven AFW pump interlocks.

Changed AFW MOV pushbutton to switch.

7.3.1.3.5.3 Rewrote description of AFW autostart interlocks.

[FN 97-054] Rewrote description of Control Room AFW flow indication qualifications.

7.6.7 Clarified pressurizer relief valve flow indication

[FN 96-002] 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 spent fuel

[FN 96-050] 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 coolers that

[FN 96-092] were removed from the Service Water system.

9.2.1.4.1 Incorporated provision for the use of high corrosion

[FN 98-011] resistant alloy steel in Service Water piping of ten-inch diameter and smaller.

Revision 4509/30/09 NAPS UFSAR 73 Revision 34 (continued)

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

9.2.2.3 Updated component cooling chemistry specifications for

[FN 98-027] chromate concentration and pH.

9.3.4.2.4.1 Deleted description that charging pump seals have

[FN 98-034] leakoffs to collect seal leakage before it can leak to the atmosphere.

9.3.4.2.5.2 Clarified acceptable methods for adding boron to the

[FN 97-004] reactor coolant system.

9.5.1.2 Added reference to fire protection system connections in

[FN 97-054] description of feedwater system.

9.6 Included the Fuel Building Trolley in the NUREG-0612

[FN 98-029] Heavy Loads Program.

10.2.1.1.2 Added new section on the effect of extending turbine

[FN 97-049] throttle and governor valve test interval. [10 CFR 50.90 License Amendment]

10.4.3.1 Updated referenced BTP to Auxiliary System Branch

[FN 97-054] (ASB). Deleted statement specifying Terry Turbine nominal speed.

10.4.3.2 Clarified discussion of SG water level management when

[FN 97-054] 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 high-high level

[FN 97-054] 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.

Revision 4509/30/09 NAPS UFSAR 74 Revision 34 (continued)

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

10.4.3.4 Deleted discussion of vital bus diversity.

[FN 97-054]

Table 10.4-3 Clarified peak reactor coolant system pressure criterion.

[FN 97-054]

Table 10.4-4 Corrected initial SG inventories. Corrected main steam

[FN 97-054] 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 range.

[FN 98-018]

13.1.1.2.1, 17.2, & KWI Updated Station Manager title to Site Vice President and

[FN 98-008] Assistant Station Managers titles to Manager-Station O&M and Manager-Station S&L. [10 CFR 50.90 License Amendment]

15.1.2.2 Reflected revised safety analyses that support an

[FN 95-055] 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 thermal

[FN 98-024] power determination from secondary plant measurements.

15.2.8.1 Deleted parenthetical statement of turbine-driven AFW

[FN 97-054] 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 (TRM) in

[FN 98-040] the UFSAR by listing the technical requirements.

17.2.1.2.B.1 Identified the Site Vice President as the station position

[FN 98-037] fulfilling the Plant Manager position identified in the ISFSI Technical Specifications.

17.2.3 Revised to reflect replacement of A/E Instruction Manual

[FN 98-021] with an Engineering Standard.

Revision 4509/30/09 NAPS UFSAR 75 Revision 33 Section Changes 17.2, 17.2.1.2, 17.2.2.1, 17.2.3, Deleted reference to the Nuclear Operations Department 17.2.4, 17.2.5, Figure 17.2.1-1, & Standards and replace with Nuclear Business Unit Table 17.2-0 Standard. Added position of Project Manager (Configuration Management).

17.2.1.1 and 17.2.1.2 Clarified organizational position descriptions by noting responsibilities for the ISFSI as they already exist.

17.2.1.2, Figures 17.2.1-2 & Deleted the position of Supervisor Administrative 17.2.1-3 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 Coordinator qualifications.

17.2.17, Tables 17.2-2 & 17.2-3 Added Generic Letter 88-18 commitment regarding storage of quality assurance records on optical disk media.

Table 17.2.0 Added provision for storage of quality assurance records in an approved offsite facility.

Table 17.2-0 Provided an additional alternative to ANSI/ANS 3.1.

Tables 17.2-2 & 17.2-3 Clarified the description of onsite and offsite nuclear safety review committees.

Revision 32 Section Changes Foreword Updated to reflect recent NRC initiatives regarding

[FN 96-055] 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 Engineering

[FN 96-049] standards STD-CEN-0020, STD-CEN-0026, and STD-GN-0038 4.1 Revised to indicate that fuel assemblies may be used that

[FN 96-051] differ from those described in the UFSARwith an NRC-approved exemption or license condition.

4.2.3 Revised to reflect removal of secondary neutron sources

[FN 97-032] starting with the Unit 1 Cycle 13 reload core; secondary source replacement in future reloads is optional.

Revision 4509/30/09 NAPS UFSAR 76 Intentionally Blank

Volume I Assignment Sheet General Table of Contents Revision 4509/30/09 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 List of Effective Pages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . LEP-1 Key Word Index (DELETED) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . KWI-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 MATERIAL INCORPORATED BY REFERENCE WESTINGHOUSE 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 . . . . . . . . . . . . . . . . . . . . . 2A-i 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-1

Revision 4509/30/09 NAPS UFSAR TOC-ii North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page Appendix 2C Report on Foundation Studies for the Proposed North Anna Power Station in Louisa County, Virginia . 2C-1 VOLUME II CHAPTER 3 DESIGN CRITERIA - STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS . . . . . . . . . . . . . . . 3.1-1 3.1 CONFORMANCE WITH 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 Appendix 3B Comparison Between Time - History and Frequency Response Methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3B-i Appendix 3C Effects of Piping System Breaks Outside Containment. . . . . . . . . 3C-i Appendix 3D Testing of Protective Coatings Under Design Basis Accident Conditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3D-1

Revision 4509/30/09 NAPS UFSAR TOC-iii North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page Appendix 3E Geotechnical Investigations and Soil Sample Testing for the Service Water Reservoir . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3E-i Appendix 3F Safety-Related Equipment Temperature Transients During the Limiting Main Steam Line Break . . . . . . . . . . . . . . . . 3F-i VOLUME IV CHAPTER 4 REACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.0-1 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 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-1

Revision 4509/30/09 NAPS UFSAR TOC-iv North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page 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 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 8.2 OFFSITE POWER SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.2-1 8.3 ONSITE POWER SYSTEMS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.3-1

Revision 4509/30/09 NAPS UFSAR TOC-v North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page 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 Appendix 9B Fuel Pool Separating Wall Design . . . . . . . . . . . . . . . . . . . . . . . . . 9B-i 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 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 Appendix 11B Radiation Exposure Evaluation for Estimated Radioactive Effluents 11B-i Appendix 11C Evaluation of Compliance With Proposed 10 CFR 50, Appendix I 11C-i

Revision 4509/30/09 NAPS UFSAR TOC-vi North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page 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 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 Appendix 14A NRC Questions and Vepcos Responses Regarding the North Anna Power Station Unit 2 Modified Startup Physics Testing Program. 14A-i

Revision 4509/30/09 NAPS UFSAR TOC-vii North Anna Power Station Updated Final Safety Analysis Report Table of Contents (continued)

Section Title Page 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 - LOCA ACCIDENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.3-1 15.4 CONDITION IV - LIMITING FAULTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15.4-1 Appendix 15A Spent Fuel Cask Drop Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . 15A-i 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. . . . . . . . . . . . . . . . . . . . . . . . . 17.1-1 CHAPTER 18 PROGRAMS AND ACTIVITIES THAT MANAGE THE EFFECTS OF AGING . . . . . . . . . . . . . . . . . . 18.18-1 18.1 NEW AGING MANAGEMENT ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . 18.18-1 18.2 EXISTING AGING MANAGEMENT ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . 18.18-5 18.3 TIME-LIMITED AGING ANALYSIS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18.18-22 18.4 TLAA SUPPORTING ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18.18-30

18.5 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18.18-33

Revision 4509/30/09 NAPS UFSAR TOC-viii Intentionally Blank

Foreword Revision 4509/30/09 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.

Revision 4509/30/09 NAPS UFSAR 2

  • One original and 12 copies of the initial UFSAR and subsequent updates are required to be submitted to the NRC.
  • The updates are required to be certified by a duly 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 4509/30/09 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:

  • 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 4509/30/09 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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List of Effective Pages Revision 4509/30/09 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-viii Revision 4509/30/09 Foreword First Page Last Page Revision 1 6 Revision 4509/30/09 List of Effective Pages First Page Last Page Revision LEP-1 LEP-8 Revision 4509/30/09 Key Word Index First Page Last Page Revision KWI-1 KWI-2 Revision 4509/30/09 Chapter 1 First Page Last Page Revision 1-i 1-iv Revision 4509/30/09 1.1-1 1.1-2 Revision 4509/30/09 1.2-1 1.2-16 Revision 4509/30/09 1.3-1 1.3-28 Revision 4509/30/09 1.4-1 1.4-12 Revision 4509/30/09 1.5-1 1.5-30 Revision 4509/30/09 1.6-1 1.6-4 Revision 4509/30/09 Chapter 2 First Page Last Page Revision 2-i 2-x Revision 4509/30/09 2.1-1 2.1-26 Revision 4509/30/09 2.2-1 2.2-10 Revision 4509/30/09 2.3-1 2.3-74 Revision 4509/30/09 2.4-1 2.4-42 Revision 4509/30/09 2.5-1 2.5-36 Revision 4509/30/09 8

Revision 4509/30/09 NAPS UFSAR LEP-2 Chapter 2 (continued)

First Page Last Page Revision 2A-i 2A-vi Revision 4509/30/09 2A-1 2A-40 Revision 4509/30/09 2A Att. 1-1 2A Att. 1-22 Revision 4509/30/09 2A Att. 2-1 2A Att. 2-72 Revision 4509/30/09 2A Att. 3-1 2A Att. 3-58 Revision 4509/30/09 2A Att. 4-1 2A Att. 4-46 Revision 4509/30/09 2B-1 2B-24 Revision 4509/30/09 2C-1 2C-54 Revision 4509/30/09 VOLUME II Chapter 3 First Page Last Page Revision 3-i 3-xvi Revision 4509/30/09 3.1-1 3.1-48 Revision 4509/30/09 3.2-1 3.2-24 Revision 4509/30/09 3.3-1 3.3-4 Revision 4509/30/09 3.4-1 3.4-2 Revision 4509/30/09 3.5-1 3.5-14 Revision 4509/30/09 3.6-1 3.6-42 Revision 4509/30/09 3.7-1 3.7-118 Revision 4509/30/09 3.8-1 3.8-226 Revision 4509/30/09 3.9-1 3.9-40 Revision 4509/30/09 3.10-1 3.10-32 Revision 4509/30/09 3.11-1 3.11-24 Revision 4509/30/09 8

Revision 4509/30/09 NAPS UFSAR LEP-3 VOLUME III Chapter 3 (continued)

First Page Last Page Revision 3-i 3-xvi Revision 4509/30/09 3A-i 3A-viii Revision 4509/30/09 3A-1 3A-30 Revision 4509/30/09 3B-i 3B-iv Revision 4509/30/09 3B-1 3B-20 Revision 4509/30/09 3C-i 3C-vi Revision 4509/30/09 3C-1 3C-140 Revision 4509/30/09 3D-1 3D-234 Revision 4509/30/09 The Franklin Institute Research Laboratories Technical Report F-C3486, Testing of Protective Coatings under Design Basis Accident Environment, dated April 1973; UFSAR pagination does not appear on 232 pages that follow 3D-2, which were taken from original report and are not subject to revision.

3E-i 3E-vi Revision 4509/30/09 3E-1 3E-118 Revision 4509/30/09 3E Att. 1-1 3E Att. 1-26 Revision 4509/30/09 3E Att. 2-1 3E Att 2-22 Revision 4509/30/09 3E Att. 3-1 3E Att. 3-60 Revision 4509/30/09 Geotechnical Engineers Inc. Report on Laboratory Soil Testing, dated June 21, 1976; UFSAR pagination does not appear on 56 pages that follow 3E Att. 3-4, which were taken from original report and are not subject to revision.

3E Att. 4-i 3E Att. 4-iv Revision 4509/30/09 3E Att. 4-1 3E Att. 4-68 Revision 4509/30/09 3E Att. 5-i 3E Att. 5-iv Revision 4509/30/09 3E Att. 5-1 3E Att. 5-50 Revision 4509/30/09 3F-i 3F-vi Revision 4509/30/09 3F-1 3F-42 Revision 4509/30/09 VOLUME IV Chapter 4 First Page Last Page Revision 4-i 4-x Revision 4509/30/09 4-1 4-2 Revision 4509/30/09 4.1-1 4.1-14 Revision 4509/30/09 8

Revision 4509/30/09 NAPS UFSAR LEP-4 Chapter 4 (continued)

First Page Last Page Revision 4.2-1 4.2-92 Revision 4509/30/09 4.3-1 4.3-98 Revision 4509/30/09 4.4-1 4.4-78 Revision 4509/30/09 4.5-1 4.5-46 Revision 4509/30/09 Chapter 5 First Page Last Page Revision 5-i 5-viii Revision 4509/30/09 5.1-1 5.1-16 Revision 4509/30/09 5.2-1 5.2-96 Revision 4509/30/09 5.3-1 5.3-2 Revision 4509/30/09 5.4-1 5.4-24 Revision 4509/30/09 5.5-1 5.5-90 Revision 4509/30/09 5.6-1 5.6-10 Revision 4509/30/09 5A-1 5A-166 Revision 4509/30/09 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; UFSAR pagination does not appear on 164 pages that follow 5A-2, which were taken from original report and are not subject to revision.

5A Att. 1-1 5A Att. 1-32 Revision 4509/30/09 VOLUME V Chapter 6 First Page Last Page Revision 6-i 6-x Revision 4509/30/09 6.1-1 6.1-4 Revision 4509/30/09 6.2-1 6.2-278 Revision 4509/30/09 6.3-1 6.3-70 Revision 4509/30/09 6.4-1 6.4-18 Revision 4509/30/09 6A-i 6A-iv Revision 4509/30/09 6A-1 6A-6 Revision 4509/30/09 8

Revision 4509/30/09 NAPS UFSAR LEP-5 Chapter 7 First Page Last Page Revision 7-i 7-viii Revision 4509/30/09 7.1-1 7.1-14 Revision 4509/30/09 7.2-1 7.2-58 Revision 4509/30/09 7.3-1 7.3-50 Revision 4509/30/09 7.4-1 7.4-8 Revision 4509/30/09 7.5-1 7.5-20 Revision 4509/30/09 7.6-1 7.6-8 Revision 4509/30/09 7.7-1 7.7-46 Revision 4509/30/09 7.8-1 7.8-2 Revision 4509/30/09 7.9-1 7.9-8 Revision 4509/30/09 VOLUME VI Chapter 8 First Page Last Page Revision 8-i 8-iv Revision 4509/30/09 8.1-1 8.1-6 Revision 4509/30/09 8.2-1 8.2-12 Revision 4509/30/09 8.3-1 8.3-64 Revision 4509/30/09 Chapter 9 First Page Last Page Revision 9-i 9-x Revision 4509/30/09 9.1-1 9.1-54 Revision 4509/30/09 9.2-1 9.2-64 Revision 4509/30/09 9.3-1 9.3-118 Revision 4509/30/09 9.4-1 9.4-36 Revision 4509/30/09 9.5-1 9.5-86 Revision 4509/30/09 9.6-1 9.6-12 Revision 4509/30/09 9A-i 9A-vi Revision 4509/30/09 9A-1 9A-22 Revision 4509/30/09 9B-i 9B-vi Revision 4509/30/09 9B-1 9B-16 Revision 4509/30/09 8

Revision 4509/30/09 NAPS UFSAR LEP-6 VOLUME VII Chapter 10 First Page Last Page Revision 10-i 10-vi Revision 4509/30/09 10.1-1 10.1-6 Revision 4509/30/09 10.2-1 10.2-32 Revision 4509/30/09 10.3-1 10.3-18 Revision 4509/30/09 10.4-1 10.4-60 Revision 4509/30/09 Chapter 11 First Page Last Page Revision 11-i 11-viii Revision 4509/30/09 11-1 11-2 Revision 4509/30/09 11.1-1 11.1-22 Revision 4509/30/09 11.2-1 11.2-60 Revision 4509/30/09 11.3-1 11.3-20 Revision 4509/30/09 11.4-1 11.4-22 Revision 4509/30/09 11.5-1 11.5-10 Revision 4509/30/09 11.6-1 11.6-8 Revision 4509/30/09 11A-i 11A-iv Revision 4509/30/09 11A-1 11A-6 Revision 4509/30/09 11B-i 11B-vi Revision 4509/30/09 11B-1 11B-34 Revision 4509/30/09 11C-i 11C-vi Revision 4509/30/09 11C-1 11C-164 Revision 4509/30/09 Chapter 12 First Page Last Page Revision 12-i 12-iv Revision 4509/30/09 12-1 12-2 Revision 4509/30/09 12.1-1 12.1-44 Revision 4509/30/09 12.2-1 12.2-12 Revision 4509/30/09 12.3-1 12.3-4 Revision 4509/30/09 12.4-1 12.4-2 Revision 4509/30/09 12A-i 12A-vi Revision 4509/30/09 12A-1 12A-20 Revision 4509/30/09 8

Revision 4509/30/09 NAPS UFSAR LEP-7 Chapter 13 First Page Last Page Revision 13-i 13-ii Revision 4509/30/09 13.1-1 13.1-2 Revision 4509/30/09 13.2-1 13.2-4 Revision 4509/30/09 13.3-1 13.3-2 Revision 4509/30/09 13.4-1 13.4-2 Revision 4509/30/09 13.5-1 13.5-2 Revision 4509/30/09 13.6-1 13.6-2 Revision 4509/30/09 13.7-1 13.7-2 Revision 4509/30/09 Chapter 14 First Page Last Page Revision 14-i 14-iv Revision 4509/30/09 14-1 14-4 Revision 4509/30/09 14.1-1 14.1-54 Revision 4509/30/09 14.2-1 14.2-2 Revision 4509/30/09 14A-i 14A-iv Revision 4509/30/09 14A-1 14A-10 Revision 4509/30/09 VOLUME VIII Chapter 15 First Page Last Page Revision 15-i 15-xxii Revision 4509/30/09 15-1 15-4 Revision 4509/30/09 15.1-1 15.1-30 Revision 4509/30/09 15.2-1 15.2-120 Revision 4509/30/09 15.3-1 15.3-214 Revision 4509/30/09 15.4-1 15.4-210 Revision 4509/30/09 15A-i 15A-iv Revision 4509/30/09 15A-1 15A-4 Revision 4509/30/09 15A Att. 1-1 15A Att. 1-54 Revision 4509/30/09 Nuclear Energy Services, Inc. report on Spent Fuel Cask Drop Analysis for North Anna Power Station Units 1 & 2, NES 81A0478, dated August 23, 1976; UFSAR pagination not applied to 52 pages that follow 15A Att. 1-2, which were taken from original report and are not subject to revision.

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Revision 4509/30/09 NAPS UFSAR LEP-8 Chapter 16 First Page Last Page Revision 16-i 16-ii Revision 4509/30/09 16.1-1 16.1-4 Revision 4509/30/09 16.2-1 16.2-2 Revision 4509/30/09 Chapter 17 First Page Last Page Revision 17-1 17-2 Revision 4509/30/09 Chapter 18 First Page Last Page Revision 18-i 18-iv Revision 4509/30/09 18-1 18-40 Revision 4509/30/09 8

Key Word Index (DELETED)

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Revision 4509/30/09 NAPS UFSAR KWI-2 Intentionally Blank