ML14339A616
| ML14339A616 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 11/24/2014 |
| From: | Dominion Energy Kewaunee |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14339A626 | List: |
| References | |
| 14-572 | |
| Download: ML14339A616 (60) | |
Text
KEWAUNEE POWER STATION UPDATED SAFETY ANALYSIS REPORT
Intentionally Blank Revision 25 11/26/14 Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.1, 2.1, 6.2.2.2.11, 6.3.2.3, 6.3.2.4, 6.3.2.6.2, Removal of redundant information on GDC
.4.2.2, 6.5.1.2.5, 8.2.2.4, Figure 8.2-1, 9.3, compliance and record retention requirements.
le 9.3-3, 9.5.1.3, 9.5.3.2, 9.6.3.2, Removed reference to deleted Table D.8-4.
le 11.1-2, Appendix B Remove reference to deleted Table 6.2-11.
PS-UCR-2014-028] Removed reference to deleted Section 5.8.2.6.1. Changed description to reflect previously approved operation of a single Fan Coil Unit. Grammatical corrections. Revised previously approved description of the number of containment dome fans. Fixed incomplete electrical bus numbering nomenclature.
Corrected incorrect revision to Figure 8.2-1.
Corrected previously approved discussion on monitoring spent fuel pool. Corrected previously approved description of Table 9.3-3.
Removed obsolete description of analysis of the effects of a turbine generated missile.
Added previously approved term fuel pool makeup. Removed footnote discussing abandoned Waste Evaporator. Removed reference to deleted Section 7.2.
, 1.0 Refs, Table 1.0-1 (Deleted), Major revision to document the KPS le 1.0-2 (Deleted), Figure 1.1-1, permanently defueled status and its entrance ure 1.1-2, 1.2, 1.2.1 thru 1.2.7, 1.2.8 into the SAFSTOR condition.
eleted), Figure 1.2-1 thru Figure 1.2-11, 1.3,
.1, 1.3.2 (Deleted), 1.3.3, 1.3.4 (Deleted),
.5 (Deleted), 1.3.6 (Deleted), 1.3.7 eleted), 1.3.8, 1.3.9, 1.4 (Deleted),
le 1.4-1 (Deleted), 1.5 (Deleted), 1.6, 1.6.1 u 1.6.9 (Deleted), 1.6.11 (Deleted), 1.6.12 eleted), 1.6 Refs (Deleted), 1.7 (Deleted),
, 1.8 Refs, 1.9 PS-UCR-2014-005]
, 2.6, 2.6.1, 2.6.2, 2.6.3, 2.6.4, 2.7.5, KPS USAR chapter 2 revision to reflect the PS-UCR-2014-006] KPS permanently defueled status and its entrance into the SAFSTOR condition.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
, 3.1, 3.1.1, 3.1.2 (Deleted), 3.1.3, 3.2, 3.2.1 This change reflects the permanent cessation of eleted), 3.2.2 (Deleted), 3.2.3, 3.2 Refs, plant operation, the permanent removal of fuel le 3.2-1, Table 3.2-2 thru Table 3.2-6 from the reactor vessel, and that the 10 CFR eleted), Table 3.2-7, Figure 3.2-1 thru Part 50 license no longer authorizes ure 3.2-3 (Deleted), Figure 3.2-5 thru emplacement or retention of fuel into the ure 3.2-7 (Deleted), Figure 3.2-9 (Deleted), reactor vessel.
ure 3.2-10 (Deleted), 3.3 (Deleted), 3.3 Refs eleted)
PS-UCR-2014-007]
Deleted), 15.5.2 This chapter has been deleted to reflect the PS-UCR-2014-008] abandonment of the Reactor Coolant System (i.e., its elimination from the KPS Design Basis). Reference to deleted Table 4.1-8 removed.
, 5.1.1, 5.1.2, 5.2, 5.2.1, 5.2.2, 5.2 Refs, The revision reflects abandonment of the KPS le 5.2-1 thru Table 5.2-18 (Deleted), containment system as a fission product barrier ure 5.2-8 thru Figure 5.2-14 (Deleted), 5.3 (i.e., its elimination from the KPS design and eleted), 5.3 Refs (Deleted), Figure 5.3-1 Design Basis as a fission product barrier). The eleted), 5.4, 5.4.1, 5.4.2, 5.4.3 (Deleted), change also reflects that elements of the le 5.4-1 thru Table 5.4-3 (Deleted), containment continue to function as a fire ure 5.4-1, Figure 5.4-2 thru Figure 5.4-4 barrier.
eleted), 5.5 (Deleted), 5.5 Refs (Deleted),
(Deleted), 5.6 Refs (Deleted), Table 5.6-1 eleted), 5.7 (Deleted), 5.7 Refs (Deleted),
(Deleted), 5.8 Refs (Deleted), Figure 5.8-1 eleted), Figure 5.8-2 (Deleted), 5.9 eleted), 5.9 Refs (Deleted), Table 5.9-1 thru le 5.9-9 (Deleted), Figure 5.9-1 thru ure 5.9-13 (Deleted)
PS-UCR-2014-009]
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
(Deleted), 6.1 Refs (Deleted), 6.2.1, 6.2.2, The revision reflects abandonment of most of
.3 (Deleted), 6.2.4 (Deleted), 6.2.5 the SSCs described within the chapter. The eleted), 6.2 Refs (Deleted), Table 6.2-1, chapter, titled Engineered Safety Features le 6.2-2 thru Table 6.2-4 (Deleted), formerly described those mechanical systems le 6.2-5, Table 6.2-6 (Deleted), Table 6.2-8 designed to mitigate the consequences of a u Table 6.2-11 (Deleted), Table 6.2-12, RCPB breach: SI (HH & LH), ICS, le 6.2-13 (Deleted), Figure 6.2-1 thru Containment Cooling, and Leakage Detection ure 6.2-5 (Deleted), 6.3, 6.3.1, 6.3.2, 6.3.3, Systems, as well as the AFW system. With the
.4, 6.3 Refs, Table 6.3-1 thru Table 6.3-3 exception of those SSCs remaining in service eleted), 6.4 (Deleted), 6.4 Refs (Deleted), to support secondary (i.e., non-accident le 6.4-1 thru Table 6.4-4 (Deleted), mitigating) functions, the systems have been ure 6.4-1 thru Figure 6.4-2 (Deleted), 6.5, abandoned and their descriptions removed.
.1, 6.5.2 (Deleted), 6.5.3 (Deleted), 6.5 Refs eleted), 6.6 (Deleted), 6.6 Refs (Deleted)
PS-UCR-2014-010]
(Deleted), 7.1 Refs (Deleted), 7.2 This revision reflects abandonment of the KPS eleted), 7.2 Refs (Deleted), Table 7.2-1 thru RPS, NI, and ESFAS Systems (i.e., their le 7.2-3 (Deleted), Figure 7.2-1 thru elimination from the KPS design basis using ure 7.2-12 (Deleted), 7.3 (Deleted), 7.3 Refs the abandonment process). The change also eleted), Figure 7.3-1 (Deleted), 7.4 reflects the removal of the Control Room as a eleted), 7.4 Refs (Deleted), 7.5 (Deleted), necessary part of the facility described in the Refs (Deleted), Table 7.5-1 (Deleted), SAR (formerly needed to meet AEC GDC ure 7.5-1 (Deleted), Figure 7.5-2 (Deleted), Criterion 11 and related design basis (Deleted), 7.6 Refs (Deleted), Figure 7.6-1 requirements). Finally, consistent with the u 7.6-2 (Deleted), 7.7 (Deleted), 7.7 Refs discontinuation of the Appendix R program, eleted), Figure 7.7-1 (Deleted), 7.8.5 the discussion of the dedicated shutdown panel eleted), 7.8.6 was removed.
PS-UCR-2014-011]
, 8.1.1, 8.1 Refs, 8.2, 8.2.1, 8.2.2, 8.2.3, The revision reflects abandonment of portions
.4, 8.2.5 (Deleted), 8.2 Refs, Table 8.2-1 of high and low voltage electrical systems and u Table 8.2-3 (Deleted), Figure 8.2-3, the change of the use of the Reserve Auxiliary ure 8.2-5 thru Figure 8.2-9, Figure 8.2-10 Transformer to that of a standby power source eleted) (i.e., not normally in service). It also reflects PS-UCR-2014-012] the abandonment of the Main Auxiliary Transformer and Buses 1-1, 1-2, 1-3, and RPS
& ESF circuits. The change also reflects the current USAR Chapter 14 safety analyses.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
, 9.1.1 (Deleted), 9.2, 9.2.1 (Deleted), 9.2.2 Major revision to document the KPS eleted), 9.2.3, 9.2 Refs (Deleted), permanently defueled status and its entrance le 9.2-1 (Deleted), Table 9.2-2 (Deleted), into the SAFSTOR condition. This is a le 9.2-3, Table 9.2-4 (Deleted), Figure 9.2-1 significant revision of the chapter to reflect u Figure 9.2-4 (Deleted), Figure 9.2-5, 9.3, applicable system modifications and system
.1 thru 9.3.4. 9.3.5 (Deleted), 9.3 Refs, abandonments in support of station le 9.3-1 thru Table 9.3-3, Table 9.3-5, decommissioning and management of ure 9.3-1 thru Figure 9.3-4, 9.4 (Deleted), irradiated fuel.
Refs (Deleted), Table 9.4-1 thru Table 9.4-3 eleted), Figure 9.4-1 (Deleted), 9.5, 9.5.1 u 9.5.4, 9.5 Refs, Table 9.5-1, Table 9.5-2, ure 9.5-1, Figure 9.5-2, 9.6, 9.6.1 thru 9.6.4,
.5 (Deleted), 9.6.6 thru 9.6.8, 9.6 Refs, ure 9.6-1 thru Figure 9.6-7, 9.7, 9.7.1 PS-UCR-2014-013]
1 (Deleted), Table 10.1-1 thru Table 10 1-2 The change reflects abandonment of the eleted), 10.2, 10.2.1 (Deleted), 10.2.2, 10.2.3 following systems: Main Turbine, Main Steam, eleted), 10.2 Refs (Deleted), Figure 10.2-1 Condensate, Air Removal, Main Feedwater, u Figure 10.2-6 (Deleted), Figure 10.2-7, Aux Feedwater, Traps and Drains, Heater ure 10.2-8 thru Figure 10.2-9 (Deleted), Drains, Bleed Steam, Secondary Sampling, ure 10.2-10, Figure 10.2-11 (Deleted), 10.3 Turbine Oil Purification, Main Generator eleted), Table 10.3-1 (Deleted), 10.4 Electrical, Main Generator Mechanical, H2 and eleted), Table 10.4-1 (Deleted), N2, and the Main Circulating Water Systems.
pendix 10A (Deleted)
PS-UCR-2014-014]
1, 11.1.1 thru 11.1.4, 11.1 Refs, Table 11.1-1 The change reflects abandonment/partial eleted), Table 11.1-2 thru Table 11.1-4, abandonment of the following systems: RCS, le 11.1-6 (Deleted), Figure 11.1-1 thru RBV, SBV, ABV, CVC, WG, SGBD/T, SWT, ure 11.1-7, Figure 11.1-8 (Deleted), 11.2, LWT, RM, and ESF. It also reflects the 2.1 thru 11.2.4, 11.2.6, Table 11.2-5, relocation of R-10 via the modification process.
le 11.2-7, Table 11.2-8, 11.3, 11.3.1, 11.3.3 PS-UCR-2014-015]
1, 12.1 Refs, 12.3, 12.4, 12.4 Refs, 12.5, The change reflects the SSC reclassification 6 performed to reflect that station SSCs are no PS-UCR-2014-016] longer credited with accident mitigating functions as described in the safety analyses.
(Deleted) This revision deletes chapter 13, Initial Test PS-UCR-2014-017] and Operation, formerly shown as historical.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
0.1, 14.0.2, 14.0.3 thru 14.0.6 (Deleted), The change revises USAR Chapter 14 to reflect 0 Refs (Deleted), Table 14.0-1 (Deleted), that 90 days post permanent reactor shutdown ure 14.0-1 thru Figure 14.0-2 (Deleted), has been achieved. The change deletes all 1 (Deleted), 14.1 Refs (Deleted), historical information and that information le 14.1-1 thru Table 14.1-14, Figure 14.1-1 identified as only applicable up until 90 days u Figure 14.1-71 (Deleted), 14.2, 14.2.1, post reactor shut down has been achieved. The 2.2, 14.2.3 thru 14.2.6 (Deleted), 14.2 Refs, change also reflects the abandonment of certain le 14.2-1 thru Table 14.2-9 (Deleted), SSCs.
le 14.2-10 thru Table 14.2-12, ure 14.2-1 thru Figure 14.2-29 (Deleted),
3 (Deleted), 14.3.2 Refs thru 14.3.6 eleted), Table 14.3-1 thru Table 14.3-27 eleted), Figure 14.3-1 thru Figure 14.3-49 eleted), Appendix 14A (Deleted),
pendix 14B (Deleted), Appendix 14C eleted)
PS-UCR-2014-018]
, B.2, B.2.1, Table B.2-1, B.4.6, B.5, B.6, The change reflects abandonment of portions
.2, B.7.2, Table B.7-1, Table B.7-6, B.8.2, of containment systems. It also reflects the SSC
.3, B.9 (Deleted), Table B.9-1 (Deleted), reclassification consistent with the most current 0 (Deleted), B.11, B.11.1 (Deleted), B.11.2, USAR Chapter 14 safety analyses. It also 1.3 (Deleted), B.11.4 (Deleted), B.11.5, reflects the permanent conformance to internal ure B.11-1 (Deleted), Figure B.11-2 flooding design requirements achieved by the eleted), B.12 (Deleted), B Refs permanent cessation of plant operation and PS-UCR-2014-021] permanently defueled status of the RPV.
pendix D (Deleted) The change eliminates calculation inputs for PS-UCR-2014-023] the KPS Fuel Handling Accident now identified within the current USAR Ch. 14. It also reflects the elimination of several design basis accident analyses no longer applicable to KPS.
pendix F (Deleted) This change merely deletes the reference to the PS-UCR-2014-025] previously deleted Appendix.
pendix H (Deleted) The change reflects abandonment of the KPS PS-UCR-2014-027] Containment System as a fission product barrier (i.e., its elimination from the KPS Design Basis as a fission product barrier).
Abandonment of the KPS containment renders this Appendix obsolete.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
2 Corrected Decontamination Factor.
PS-UCR-2014-001]
.4.2.3, Table 9.3-5, Table 9.5-2, and Updated to reflect SAFSTOR Configuration.
le B.2-1 PS-UCR-2013-003]
0.1, 14.2, 14.2.2, 14.2.3, 14.2.3.1, and Updated Section 14 to discuss credibility of le 14.2-2 postulated accidents for liquid Waste and Gas PS-UCR-2013-005] Decay Tanks.
le 9.3-3 Updated USAR Table 9.3-3 Spent Fuel Pool.
PS-UCR-2013-007]
ure 8.2-1 KPS Substation and Mini-Substation PS-UCR-2013-008] Modifications.
2.1.3, 14.2.1.7, Table 14.2-1, and Corrected Terminology of Decontamination le 14.2-10 Factor.
PS-UCR-2013-009]
.1.3 Spent Fuel Pool Water Level.
PS-UCR-2013-010]
.4.2.3 Spent Fuel Pool Temperature and Level PS-UCR-2013-011] Indications.
2.3.2.4 Gas decay tank and volume control tank PS-UCR-2012-028] rupture dose consequence analysis results and conclusions updated from whole body (rem) to Rem TEDE.
1.3, B.11.4, and References Internal flood protection features discussion PS-UCR-2013-002] was updated to reflect acceptable flood barrier degradation.
0, 14.0.1, 14.0.5, 14.1, 14.2, 14.2.2, 14.2.4, Safety Analysis updated to reflect existing 2.5, 14.2.6, 14.2.1.1, 14.2.1.4, 14.3, 14A, accident/transient analyses to support the B, and 14C permanent cessation of power operations and PS-UCR-2013-004] the permanent reactor vessel defueling.
.1.3, 9.3.2.3, 9.3.3.3, 9.3.4.2.3, and 9.3 Updated due to an increase in the SFP heat load ferences resulting from the power uprate and the use of PS-UCR-2012-017] administrative controls for core offload to remain within SFP temperature limits.
.4.3 Updated due to installation of control room PS-UCR-2013-001] annunciation following closure of a Relay Room supply or exhaust damper.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
, Figure 2.2-1, Figure 2.4-1, Figure 2.4-2, Modified to indicate population information as le 2.6-4. HISTORICAL and reference the appropriate PS-UCR-2012-024] document for current population information.
.3.3 Updated to reflect control room temperatures PS-UCR-2012-026] being maintained as per the temperature range defined in operating procedure OP-KW-NOP-ACC-001.
, 8.2.3.4 Updated minimum safeguards battery terminal PS-UCR-2012-027] voltages based on calculation C11723 Rev. 1 Addendum J.
Revision 24 (11/08/12)
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
.1.1 and 4.4.-2 Updated due to installation of a new reactor PS-UCR-2012-001] vessel surveillance capsule.
-1, 1.2-1, 1.2-3, 1.2-4, 1.2-5, 1.2-6, 1.2-7, Updated Table 1.0-1 and associated USAR
-8, 1.2-9, 1.2-10, 5.4-1, 6.4-1, 8.2-3, Figure changes (based on plant drawing
-5, 9.2-5, 9.3-1, 9.4-1, 9.6-1, 9.6-5, changes) that occurred since USAR Rev. 23 was
.2-3, 10.2-5, 10.2-7, 10.2-9, 11.1-6, issued.
.2-1, 11.2-2, 11.2-3, and 11.2-4.
PS-UCR-2011-015]
.2.3, 8.2.2.2, and 10.2.2.7 Updated due to installation of a Main Feedwater PS-UCR-2011-014] Pump trip feature (to a single MFW pump) during initiation of a fast bus transfer.
.5, 4.2.6, 4.2 Refs, 9.3 Updated to reflect the revised PS-UCR-2011-017] pressure-temperature limiting curves and low temperature overpressure protection requirements.
.3.1.3(new), 14.3.2.6, 14.3.3.4.1, 14.3.3.5 Safety analysis updated to include the loss of PS-UCR-2012-008] coolant accident peak clad temperature post analysis of record evaluation results.
.2.1.3 Fuel handling accident updated due to the Zone PS-UCR-2012-010] Special Ventilation System not being credited.
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
.2, Table 5.2-3, 5.3 Ref (new), Table Update restores use of the classification "closed
-4 system outside of containment" in defining PS-UCR-2012-013] containment isolation.
.4.7 Station blackout discussion updated due to PS-UCR-2012-014] battery room heatup re-evaluation following a station blackout using GOTHIC.
.2.2.5 Update to discuss the ability for manual PS-UCR-2012-018] operation of the spent fuel pit crane hoist.
LOT, 14 LOF Renumbered Tables and Figures in Chapter 14 PS-UCR-2012-022] to be consistent with the rest of the Chapters in the USAR.
.2.2 Updated to permit automatic operation of Load PS-UCR-2010-033] Tap Changers on the Reserve Supply Transformer (RST) and Tertiary Supply Transformer (TAT) sources of offsite power.
[10 CFR 50.90 License Amendment Request 236 and License Amendment 209]
.2.5, 8.2.3.4 Updated due to installation of spare safety PS-UCR-2011-010] related battery charger.
.4.3 Updated to reflect a change in frequency for PS-UCR-2012-002] testing accumulator discharge check valves.
Refs, Table 4.3.1, Table 4.3.2 Updated cumulative fatigue usage factors PS-UCR-2012-006] associated with the Reactor Vessel Head Flange, Vessel Flange, and Closure Studs.
.1.5, Table 9.2-1 Updated reference to the ASME Code used for PS-UCR-2012-007] the design of the 1B Demineralizer Letdown Pre-filter
.1.2.3 Updated to remove reference to the hot full PS-UCR-2012-009] power moderator temperature coefficient being stated in the COLR since Improved TS removed it from the COLR. [10 CFR 50.90 License Amendment 207]
.4.1 Update the information for the Control PS-UCR-2012-004] Room/Relay Room temperature in the discussion about use of alternate cooling
[License Amendment 207]
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
.2.1, 9.3 Refs Updated based on NRC approval to use manual PS-UCR-2012-015] versus automatic actions to supply service water to the CC water heat exchangers via the main return valves during transfer to recirculation. [10 CFR 50.90 License Amendment Request 252 and License Amendment 211]
.2.2, 10.2.2.8 Updated the lake barge discussion within the PS-UCR-2011-018] Circulating Water intake structure description
.8 Modified to provide clarification that portions of PS-UCR-2012-005] the Station and Instrument Air System that interface with safety related components are safety related where required to maintain the associated safety related function.
.3.1, 9.6.7.2, 9.6.8, 9.6.8.1 Updated due to changing the EDG room PS-UCR-2011-006] ventilation damper actuators air supply to Instrument Air with compressed dry air bottle backup.
.2.7 Updated due to WCAP-15666-A, Rev. 1, PS-UCR-2011-008] evaluation extending RCP Motor flywheel inspection frequency to 20 years.
.2.2 Updated to describe the capability for automatic PS-UCR-2011-011] operation of Load Tap Changers on the Reserve Supply Transformer (RST) and Tertiary Supply Transformer (TST) sources of offsite power. [10 CFR 50.90 License Amendment Request 236 and License Amendment 209]
.8, 8.2.3.4, Table 8.2-3, Table 10A.4-2 Updated due to new calculated safeguards PS-UCR-2011-013] battery parameters and the installation of new non-safeguards batteries.
.4.3 Updated by adding details on relay room supply PS-UCR-2011-016] and exhaust damper position in response to high temperatures in the relay room.
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
.4.2, 9.6.5.6, 14.3.7 Updated details related to charcoal filter PS-UCR-2009-035] charcoal ignition hazard based on revised calculation results. Iodine release values revised due to implementing Alternate Source Term (AST).
.1, Table 15.7-1 Modified License Renewal details to correct PS-UCR-2011-002] reference to the current operating license.
.2.2.1 Modified details due to procurement of new PS-UCR-2010-047] Reactor Vessel Stud Tensioners ble 1.0-1, Figures: 1.2-1, 1.2-2, 1.2-3, 1.2-6, Updated Table 1.0-1 and associated USAR
-11, 4.2-1, 5.4-1, 5.8-5, 6.2-1, 6.2-2, 6.4-1, Figure changes (based on plant drawing
-3, 8.2-4, 8.2-5, 8.2-6, 8.2-7, 8.2-8, 8.2-9, changes) that occurred since USAR Rev. 22
-1, 9.2-2, 9.2-3, 9.2-4, 9.2-5, 9.3-1, 9.3-2, was issued.
-3, 9.3-4, 9.4-1, 9.6-1, 9.6-2, 9.6-3, 9.6-4,
-5, 9.6-6, 9.6-7, 10.2-1, 10.2-2, 10.2-3,
.2-4, 10.2-5, 10.2-6, 10.2-7, 10.2-8, 10.2-9,
.1-1, 11.1-2, 11.1-3, 11.1-4, 11.1-5, 11.1-6,
.2-1, 11.2-3 PS-UCR-2010-019]
.1, 8.2.2.3, 8.2.3.2 Updated to reflect bus alignment requirements PS-UCR-2010-027] prior to exceeding 200°F based on plant procedure revision and operating policies to protect against fast bus transfers.
.3, 8.2.1, 8.2.1.1, 8.2.2, 8.2.2.2, 8.2.3.5, Updated due to Switchyard Phase 2 changes ure 8.2-1 affecting off-site power supplies, replacing the PS-UCR-2010-030] Reserve Auxiliary Transformer (RAT),
installing the RAT Supply Transformer (RST),
installing the T-20 transformer, substation and switchyard reconfiguration, and substation-to-plant interface improvements.
.3.2, 8.2.3.3.1, 8.2 Refs, Table 8.2-1, Updated due to EDG loading changes as a ure 8.2-10 result of multiple plant design changes, PS-UCR-2009-079] corrective actions, and other impacts as detailed in calculation C11450, Rev. 2, and Addendum B.
.2.3, Table 10.1-1 Updated due to installation of new heater drain PS-UCR-2010-037] pump motors and variable frequency drives.
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
.2.4.1, Figure 7.6-1 Updated due to replacing selected PS-UCR-2010-046] high-pressure and low pressure fittings/seals on the Incore Instrumentation Seal Table; maintenance connection added.
.4.1, 9.6.4.2, 9.6.4.3, 11.2.4 Updated due to changing the power supply for PS-UCR-2011-007] the Control Room A/C Chiller Units to a non-safety related source and installing auto transfer logic for alternate cooling to the Control Room A/C system air handling units cooling coils.
A (all) (Figures & Tables inclusive) Updated due to reconstitution of the outside PS-UCR-2010-022] containment HELB analyses.
.2.2 Updated due to upgrading the Core Exit PS-UCR-2010-039] Thermocouple system, including replacement of existing connectors with multipin connectors and replacement of selected CET instruments and to reflect actual plant configuration resulting from CET failures.
.2.2.6, 6.4.2.1, 6.4 Refs, Table 6.4-2, B.12 Updated due to replacing/upgrading MOVs to w), B.12.1 (new), B.12.2 (new), B.12.3 ensure adequate design margin when w), B Refs implementing the Joint Owners Group (JOG)
PS-UCR-2011-009] Motor Operated Valve (MOV) evaluation methodology.
.10.2 Updated due to installation of new seismic PS-UCR-2010-024] monitoring instrumentation.
ble 6.4-3, 14.2.5.7 Updated due to changes to the MSLB accident PS-UCR-2011-001] analysis regarding the use of a conservative SI flow rate, assumed ICS spray nozzles, and removal of details from Table 6.4-3.
Refs, 3.2 Refs, 4.2 Refs, 6.3 Refs, Modify references due to changes to Technical Refs, 11.2 Refs, 14.0 Refs, 14.1 Refs, Report DOM-NAF-5 and due to inconsistent
.2 Refs, 14.3.5 Refs, Table B.7-1 referencing of documentation associated with PS-UCR-2011-004] License Amendment 172, Stretch Power Uprate.
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
ble 5.2-3, 6.6.1.1, 6.6.2, 6.6.3, 6.6.4, 6.6.4.1, Updated due to changes in AFW control
.5, 6.6.6, 7.7.6.2, 9.6.2.2, 10.2.2.6, including motor driven pump cross-connect
.1.10.1 piping and valves, removing MDAFW pump PS-UCR-2010-040] discharge flow restrictors and adding MD and TD AFW pump discharge cavitation venturis, removing AFW pump discharge pressure switches, TD pump discharge check valves, revising AFW suction pressure trip, and modifications to lube oil coolers and piping.
ble 5.2-3, 6.2.2.2.6, 6.2.2.3, Table 6.2-11, Updated to reflect the elimination of the air ure 6.2-4, B.10.4 void in the pipe section between MOVs PS-UCR-2010-034] SI-350A(B) and SI-351A(B) and resolve interrelated issues involving the pressurization of components and piping associated with valves SI-350A(B) and SI-351A(B).
ble 5.2-3, 6.2.2.3, 9.3.2.2 Updated as a result of multiple valve changes PS-UCR-2010-043] that: eliminate a source of RWST inleakage and a source of Train A RHR piping gas intrusion, modify RHR overpressure protection, and prevent the gas void upstream of SI-31 from affecting SI pump operation.
.4.3 Updated to describe SI Accumulator check PS-UCR-2010-056] valve forward flow testing.
.5, 4.1.5.1, 4.1.5.2, 4.1.5.3, 4.1.5.5, 4.1.5.6, Updated due to receipt of the Renewed
.5.7, 4.1.5.8, 4.1.5.10, 4.1.6, 4.1.7, Operating License; added Chapter 15 and Refs, Table 4.1-8, Table 9.2-2, revised multiple USAR pages reflecting the ble 11.1-1, Ch. 15 (new) additional twenty years added to the operating PS-UCR-2010-060] license.
.3, 6.6.6, 14.1.11.2 Updated to include the limiting value assumed PS-UCR-2010-061] for the time for the TDAFW Pump to reach full discharge pressure.
.7.2 Updated to reflect changes from DC PS-UCR-2010-064] KW-09-01016: changed the cooling water source of the Turbine Building Basement Fan Coil Units 1C and 1D from Circulating Water to Service Water and added discussion related to the installation of ventilation louvers and dampers for the Turbine Building.
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
ure 8.2-1 Updated Figure 8.2-1 to include installation of PS-UCR-2010-029] Breaker 2066E which was added to the 138kV section of the sub-station to improve reliability of offsite power supplies.
.7, 1.8, 14.2.3.2.4 Modified to more clearly identify the normal, PS-UCR-2010-058] auxiliary, standby, and emergency power sources; plus misc. editorial corrections.
ble B.2-1 Updated and Modified Table B.2-1, PS-UCR-2010-066] Classification of Structures, Systems and Components, to include the Diesel Generator fuel oil vent lines and supply lines to the day tanks.
ble 14.1.6-1, Table 14.1.6-2 Update due to revised Feedwater Malfunction PS-UCR-2010-054] Analysis with a reduced assumed low steam line pressure SI setpoint.
.1.6.2.2.1, 14.1.6.2.2.2, 14.2.5.2, 14.2.5.7, Modified to include limiting closed stroke ble 14.2.5-1 time for valves FW-12A(B) as per the PS-UCR-2010-062] Feedwater Malfunction Analysis and MSLB Analysis.
.2.1.3, 6.2.2.1.4, 6.4.2.1, 6.4.2.2.2, 6.4.3.3, Modified USAR details to include: additional
.4.2, Table 6.4-3 discussion on the use of recirculation spray as PS-UCR-2010-063] beyond design basis; adding the internal containment spray pumps to the discussion on meeting NPSH requirements when drawing from the RWST; the strainer perforation size for recirculation spray flow leaving the containment sump; the use of internal containment spray in response to MSLB.
[10 CFR 50.90 License Amendment, in part]
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
, 1.0 Refs, Table 1.0-2 (new), 1.3.5, 1.8, Updated as a result of ITS implementation:
.2.4, 3.1.2.6, 3.1.3.2, 4.2.8, 5.4.1, 5.4.1.1, new TS Mode definitions were added along
.1.5, 7.2.3.2.2, 7.7.4, 7.7.6, 8.2.3.4, with footnotes to the existing use of hot ble 8.2-2, Table 8.2-4 (new), 9.2.1.2, shutdown and consequential changes to
.1.3, 9.2.1.4, 9.2.3.5, 10.1.3, 10.2.2.2, select USAR Sections; added safeguards
.2.2.3, 10A.2.4.1, 10A.2.4.3, 10A.2.4.5, battery details addressing qualified life, design A.3.3.2, 10A3.4.2, 10A.3.5.4, 10A.3.5.11, margin, battery parameters, and the use of an A.4.3.2, 10A.4.4.2, 10A.5.2.2, alternate means of restoring terminal float A.11,12.4.2, 14.1.4.2, 14.1.4.2.2, 14.1.13.1, voltage; procedure descriptions in Chapter 12
.2.5.2, B.11.2, B.11.3 were revised. [10 CFR 50.90 License PS-UCR-2010-045] Amendment]
.3, 3.2.3.4.1, 4.2.8, Table 9.3-3, 11.1.2.4, Updated and modified as a result of ITS
.2.3.21, 14.1.5, 14.1.11.1 implementation: removed specific TS PS-UCR-2010-026] references, removed details that are redundant and unnecessary to information that can be found in the TS, relocated certain TS details into USAR. [10 CFR 50.90 License Amendment]
, 5.1.1, 5.2.1.5.4, 5.5.1, B.4.5 Updated as a result of ITS implementation:
PS-UCR-2010-048] relocate statements from TS 5.2.a.1, 5.2.b.1, 5.2.d, and 5.3.a and add Cold Shutdown to Section 5.2.1.5.4. [10 CFR 50.90 License Amendment]
.2.3.1, 3.2 Refs Updated as a result of ITS implementation:
PS-UCR-2010-055] re-evaluation of the Statistical Design Limit for DNB limiting events due to increased RCS flow uncertainty due to changing the RCS Total Flow Rate TS surveillance frequency; and reference changes that produce a removal of details that are not correct. [10 CFR 50.90 License Amendment, in part]
.3.1.1 Updated as a result of ITS implementation:
PS-UCR-2010-057] relocate TS 3.8.a.6 to USAR; direct communication between the control room and the operating floor of containment during changes in core geometry. [10 CFR 50.90 License Amendment]
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
ble 9.2-3, 9.5.1.1, 9.5.2.2.6, 9.5.3.1.2, Modified and Updates the USAR with
.3.2, 9.5.4, 9.5 Refs, Table 9.5-1, 9.6.2.2, miscellaneous information based on the
.2.2.3, 10.2.2.5, 10.2.2.8, 10.2.2.9, A.3.8.1, Design and Licensing Basis Integrated Review ble 5 (App A), Table 9 (App A), of various sections of the USAR performed by tachment 1, Table A-3, Table A-4, the Integrated Review Team.
ble A-5, E.2.1.6, E.3.3, Log Boring No. 40 41 (corrected to 60 & 61 respectively)
PS-UCR-2009-055]
ble 5.2-3, 5.3.3, 5.6, 5.6 Refs, Table 5.6-1 Updated USAR by adding containment PS-UCR-2010-059] penetration table that designate the type of leakage test required and revised the related text. This change was made based on a commitment made in License Amendment Request 52. The other related table associated with containment penetrations was revised to clarify the Operating and Post-LOCA function for some penetrations.
ble 5.2-3, 5.3.1.1, 5.3.2 Updated and Modified Table 5.2-3 Reactor PS-UCR-2009-071] Containment Vessel Penetrations to reflect the current design and licensing basis and to improve ease of usage.
.4.3.2.1, 9.3.4.3.2.2, 9.3 Refs Updates the USAR with the general details PS-UCR-2010-025] associated with the implementation of changes made in response to Generic Letter 88-17, Loss of Decay Heat Removal.
.7, 1.8, 6.1.1.4, 6.3.1.1, Table 6.3-1, 6.4.1, Modified various sections of the USAR for
.1.5, 6.4.2.1, 6.4.3.1, 6.4.3.1, 6.4.3.4, clarification to more clearly describe the ble 6.4-3, 14.2.5.7, 14.3.5.2, 14.3.5.2.2 current licensing basis relationship between PS-UCR-2010-049] the Containment Safeguard Systems; Containment Air Cooling and Internal containment Spray.
.4.3.2.1 Modified the USAR for the analysis PS-UCR-2010-050] assumptions for Low Temperature Over Pressure (LTOP) that were approved by the NRC by License Amendment 130.
2.1 Modified the USAR to correct an editorial PS-UCR-2010-051] error created in Revision 20.
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
.1.1, 6.3 Refs, 6.4.1, 6.4.3.4, 6.4 Refs Modifications performed made improvements PS-UCR-2010-053] to the changes incorporated by KPS-UCR 2010-049 and included the related references to License Amendment Request 195 and License Amendment 172.
.4.3 Modifications performed include clarifying PS-UCR-2010-065] the conditions where the accumulator block valves are positioned and removes a redundant statement that was included in a previous section.
, 1.2.3, 5.3.1.1, 5.3.2, 7.2.1.4, 7.2.1.9.2, Editorial changes made for clarification.
Refs, 7.7.3, 7.7.4, 7.7.6, 7.7.6.1, 7.7.6.1.1, Updates made include deleting reference to
.6.2, 8.1.1.2, 8.2.2.8, 8.2.3.2, 8.2.3.5, the Main Feedwater control valves due to the Refs, 11.3.1.1, 11.3.3, 12.3.3, 12.4.1, plant modification that removed the valve
.4.2, 12.4.3, 12.4.4, 12.4.5, 12.4.6, 12.4.7, hand wheels which now prevents local manual
.6, 12.6 Refs, Appendix C operation. Added missing details related to PS-UCR-2009-033] Safeguard Bus Under Voltage Protection including Degraded Grid Voltage.
.5 (new), 8.2 Refs Chapter 8 updated by adding new section PS-UCR-2009-058] 8.2.5. This section describes the Environmental Qualification requirements, KPS methods of compliance and the relevant EQ Program elements.
ble 5.2-3, 5.3.2 Updated Table 5.2-3 for containment PS-UCR-2010-028] penetration number 9 to correct technical errors related to line size and penetration classification.
.1, 5.7.1.4 Editorial change made to the containment leak PS-UCR-2010-041] rate value due error made by USAR Change Request R21-026.
ble 4.2.1 Editorial change made to Table 4.2-1 related to PS-UCR-2010-042] reactor vessel materials of construction due errors made by USAR Change Request R19-038 and USAR reformatting for Revision 20.
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
.3.1, 11.3.1.1 Revise section 11.3.1 to provide an accurate PS-UCR-2010-044] description of the processes in place for the control of special and by-product material including the storage of radiation sources.
.3.3, 5.8.2.1, 5.8.2.2, 5.8.2.4, 5.8.2.7, Modified and updated USAR Chapter 14
.2.8, 5.8.2.9, 5.8.2.10, 5.8.2.11, 5.8.2.12, Safety Analysis based on the results of the
.2.12.1, 5.8.2.13, 5.8.2.14, 5.8.2.15.1, design and licensing basis review of USAR
.2.16, Table 5.8-1, Table 5.8-2, Table 5.8-3, Chapter 14, Safety Analysis.
ble 5.8-4, Table 5.8-5, Figure 5.8-1, ure 5.8-2, Figure 5.8-3, 6.2.1.1, 9.2.1.3,
.3.1.2, 14.0.1, 14.0.3, 14.0.4, 14.1.4.3.3,
.1.7.4, 14.1.7.5, 14.1.7.6, Figures 14.1.5-1 ough Figure 14.1.5-5, Figures 14.1.7-1 ough 14.1.7-18, 14.2.4.1, 14.2.5.11,
.2.6.1, 14.2.6.2, 14.2.6.4, 14.3.3.1,
.3.3.3.1, 14.3.3.5, 14.3.5.1.1, 14.3.5.1.2,
.3.5.2.2, 14.3.3 Refs, Table 14.3.3-6, ble 14.3-6, Figure 14.3-9, Figure 14.3-21 CR R22-017]
.1, 5.2.1.5.1, 5.2.1.7, 5.2.1.7.1, 5.2.1.10, Modification included various editorial
.1.16, 5.2.2.5.1, 5.4, 5.9.2, 5.9.2.1, 8.2.3.1, changes for clarification and updated the
.2.1.3, 11.2.2.1.1, 11.2.2.1.2, 11.2.2.1.3, physical dimensions for the Spent Fuel Pool.
.2.2.1.4, 11.2.2.2, 11.2.2.2.1, 11.2.2.2.2,
.2.2.2.3, 11.2.2.2.4, B.3 PS-UCR-2009-030]
.3, 7.7.6.1.4, 8.2.1, 8.2.2.7, 8.2.2.9, Modification included various editorial
.2.10, 8.2.3.5, 9.5.2.2.4, 10.1.1 changes for clarification and updated technical PS-UCR-2009-032] details on the design and operation of plant electrical systems including the substation.
, 7.7.5, 9.6.1, 9.6 Refs Modification included various editorial PS-UCR-2009-037] changes for clarification resulting from the design and licensing basis review process.
.8, 9.6.8.1, 9.6.8.2, 9.6.8.3, 9.6.8.4 Update included a new section describing the PS-UCR-2009-054] general design and operation of the Station and Instrument Air System including the plant response to Generic Letter 88-14.
Changes Made under the provisions of 10 CFR 50.59 ction except where indicated in brackets.
.4.1, 5.5.5, Table 14.2.6-4, 14.3.6.1.2, Updated the flow rate for Shield Building ble 14.3-8 Ventilation fans based on the results of a PS-UCR-2009-070] revised engineering calculation.
.2.2, 8.2.3.2 Update included a description of the current PS-UCR-2010-002] operational requirements for the Containment Fan Coil Units.
, 1.1, 1.3, 1.3.2, 1.3.3, 1.3.4, 1.3.5, 1.3.6, Modification included various editorial
.7, 1.3.9, 1.8, 4.2.3, Figure 5.2-14, 5.5.5, changes for clarification and updated sections
.3.1, 6.5.1, 7.2.1.9, 8.1.1.2, 8.1.1.2.1, 1.3 and 1.8 related to General Design Criteria
.2.3.21.111.2.3.26, 11.3.1, 11.3.3, 14.0 Refs, and removed the Historical designation for
.3.5.1.7, 14.3.5.2.4, 14.3.6.1.2, these sections.
ure 14.3-24, Figure 14.3-25, Figure 14.3-6, 4, H.4.2, H.4.4.2, H.4.5 PS-UCR-2010-003]
ble B.2-1 Updated Table B.2-1 Classification of PS-UCR-2010-013] Structures, Systems and Components to include systems and components not previously listed and revise the Design Classification where necessary.
.4.4, 8.2.4.5, 8.2.4.6, 8.2.4.8, 8.2.4.9, Adds technical detail related to the systems
.4.10 required and the method used for decay heat PS-UCR-2010-017] removal to cope with a Station Blackout (SBO) event.
.3.5.1.2 Corrected an editorial error that incorrectly PS-UCR-2010-018] referred to a WCAP as a document considered incorporated by reference into the USAR.
.1.4.2.1, 14.1.4.2.2, 14.1.4.2.3, 14.1.4.3.3 Updated Chapter 14, section 14.1.4 Chemical PS-UCR-2010-020] and Volume Control System Malfunction based on a revised engineering calculation.
Refs Modified reference letter for License PS-UCR-2010-021] Amendment 199 with the correct date and nomenclature.
ble 5.2-3 Updated Table 5.2-3 Reactor Containment PS-UCR-2010-023] Vessel Penetrations to identify the credited components associated with each penetration.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
ble 5.2-3, 6.2.1.4, 6.2.2.1.1, 6.2.2.2.1, Incorporated the details associated with the
.2.2.7, 6.2.2.3, 6.2.4.2, 6.2.4.3 plant modification installed on containment 22-029] penetration 35 Safety Injection and Accumulator Test Line.
ble 9.3-3, 9.3.1.3, 9.3.4.3.3 Incorporated the changes resulting from the PS-UCR-2009-017] design and licensing bases review of the Spent Fuel Pool Cooling System.
.2.1, 9.6.2.2, 9.6 Refs Update included the details associated with the PS-UCR-2009-028] plant response to the water hammer and two phase flow concerns identified in Generic Letter 96-06.
.6, 5.2.1.31, 6.6.3, 10.1.4, Table 10.1-1, Incorporated the changes resulting from the 2.2.1, 10.2.2.3, 10.2.2.5, 10.2.2.10, 10.2.5, design and licensing bases review of the Main 2.5.1 Steam, Feedwater and Condensate Systems.
PS-UCR-2009-036]
.2.13, Table 9.3-3, 14.3.5 Refs Update changes the boron concentration for PS-UCR-2009-045] the spent fuel pool to be consistent with current Technical Specifications.
.3.4.1, 5.8.2.6, 5.8.2.15, 5.8.2.15.1, Incorporated the changes resulting from the
.2.15.2, 5.8.2.15.3, 6.3.2.3, 11.1.2.1.1, design and licensing bases review of the Waste 1.2.11, 11.1.2.12, 11.1.2.17, 11.1.3.1, Disposal System.
1.3.2, 11.1.3.3, Table 11.1-1, Table 11.1-2, ble 11.1-3, Table 11.1-4, Table 11.1-5, ble 11.1-6, 11.2.2.1, 11.2.2.7, 11.2.2.8, 2.3.22, 11.2.3.24, 11.2.3.26, 11.2.4, 2 Refs, Table 11.2-9, Figure 11.2-5, ure 11.2-6, D.5.2, D.5.3, D.5.4, D.5.5 PS-UCR-2009-051]
.3, 7.2.3.3, 7.3.1, 7.3.3.2, 7.4 Refs, 7.7.2, Update changes the upper load limit for design
.1.1, 10.1.2, 14.1.7.1 load changes to reflect the design capability of PS-UCR-2009-052] the automatic reactor control system and removes a specific value for DNBR and replaces it with a generic term.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
(new section) Incorporated the changes resulting from the PS-UCR-2009-059] design and licensing bases review of the Plant Process Computer System. The changes include a more complete and comprehensive description that describes the functions, design basis, components of the system and interfaces with associated systems.
.2, 9.2.2.11, 9.2.2.32 Modification included various editorial PS-UCR-2009-061] changes for clarification and standardization of format.
ble 1.0-1, Figures 1.1-1, 1.2-1, 1.2-2, 1.2-3, Replace 44 figures listed in Table 1.0-1 with
-4, 6.2-1, 6.2-2, 6.4-1, 8.2-5, 8.2-3, 8.2-9, the current revision and update table with
-5, 9.2-2, 9.2-3, 9.3-4, 9.3-1, 9.3-2, 9.4-1, current revision number.
-1, 9.6-2, 9.6-5, 9.6-6, 9.6-7, 10.2-1, 10.2-2, 2-3, 10.2-4, 10.2-8, 10.2-7, 10.2-9, 11.1-5, 1-6, 11.1-1, 11.2-1, 11.2-2, 10A.3-2, A.3-3, 10A.3-4, 10A.3-9, 10A.4-2, 10A.4-3, A.4-4, 10A.4-5, 10A.4-9, 10A.5-2, 10A.6-2 PS-UCR-2009-062]
.3.4, 8.2.4.5 Update performed to change the descriptions PS-UCR-2009-063] of battery sizing to include non-safeguard battery BRD-101.
.2.2, 3.2 Refs Modification included editorial changes to PS-UCR-2009-072] include applicable references related to Nuclear Fuel for consistency with Improved Technical Specifications.
.1.5, 8.2.3.5, B.11.1, B.11.2, B.11.4, Incorporated the changes resulting from the 1 Refs, Figure B.11.1 design and licensing bases review of Internal PS-UCR-2009-073] Flooding.
.3.3, 7.5.3.3.4, 7.5 Refs Updated the current integrated dose to which PS-UCR-2009-077] the electrical penetrations inside containment are qualified.
, 2.4 Modification references the location in the PS-UCR-2010-004] USAR where the definition of Low Population Zone for the plant can be found.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.1, Table 4.1-7, 5.2.1.27, 6.3.3.6, 7.2.1.4, Modification included various editorial
.3.2.4, 7.2.3.4, 7.5.2.2.2, 7.6.2.2, 7.6.2.3, changes for clarification and standardization of
.2.3.1, 8.2.2.6, 8.2.2.9, 9.3.1.3, 11.2.3.1, format.
3.1.3, 14.0.4.1, 14.1.3.1, Table B.2-1 PS-UCR-2010-005]
pendix 14A, Appendix 14B, Appendix 14C, Modification included various editorial pendix F, Appendix G, Figure H.4-1, changes for clarification and standardization of ure H.4-2 format.
PS-UCR-2010-006]
pendix E (all) Modification included various editorial PS-UCR-2010-007] changes for clarification and standardization of format.
.1, 4.2.8, 7.2.1.5, 7.6.3, 9.6.3.1, 11.2.2.1, Modification included various editorial 2.3.26 changes made in preparation for the PS-UCR-2010-008] implementation Improved Technical Specifications.
.4.1, 9.5.1.1, 9.5 Refs Modification included various editorial PS-UCR-2010-009] changes for clarification and standardization of format.
pendix A (all) Modification included various editorial PS-UCR-2010-010] changes for clarification and standardization of format.
ble 6.2-13, 6.2 Refs Modification included various editorial PS-UCR-2010-011] changes for clarification and standardization of format.
.2.3, 6.2.4.1, 6.2 Refs, 6.4.4.1, 6.4 Refs, Incorporated the details associated with the
.5, 9.3 Refs plant response to issues identified in Generic PS-UCR-2010-012] Letter 2008-1.
.2.2.10 Update includes defining the accuracy of the PS-UCR-2010-014] wide range sump level monitor instrument to be consistent with the current design basis calculation.
Modification included adding the Technical PS-UCR-2010-015] Requirement Manual and the Fire Protection Program into the USAR as documents incorporated by reference.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
2.3.25 Modification revised text to refer to PS-UCR-2010-016] 10 CFR 20.1003 for a complete definition of an airborne radioactivity area.
.2.35, 9.2.3.2, Table 9.2-1 Incorporated the changes resulting from the PS-UCR-2009-004] design and licensing bases review of the Chemical and Volume Control System.
ure 8.2-1 Incorporated the details related to the plant PS-UCR-2009-014] modification made to the 138Kv east bus in the plant substation that added a bus extension and manual disconnect switches.
.1.1, Figure 8.2-1 Incorporated the details related to the plant PS-UCR-2009-016] modification made to the 138Kv Lines F-84 and Y-51 in the plant substation that added two breakers and four manual disconnect switches to connect each line to both the east and west buses.
.1, 8.2.1.1, 8.2.2.2, 8.2.3.5 Incorporated the details related to the plant PS-UCR-2009-019] modification made to in the plant substation that and off-site supply that added the Tertiary Supply Transformer, two new gas circuit breakers, replaced one oil circuit breaker with a gas circuit breaker and removed one oil circuit breaker and replaced it with bus work, and replaced the Tertiary Auxiliary Transformer.
ure 8.2-1 Incorporated the details related to the plant PS-UCR-2009-021] modification made to the in the plant substation that added a manual disconnect switch in the 138Kv line to the auto transformer.
.1, 8.2.1.1 Incorporated the details related to the plant PS-UCR-2009-024] modification that replaced oil circuit breaker G-1 with a new gas circuit breaker and relocated the breaker to a new mini-substation.
2.3, 11.1.2.2, 11.1.2.18 Incorporated the changes resulting from the PS-UCR-2009-027] design and licensing bases review of the Steam Generator Blowdown System.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.3, 8.2.1, 8.2.1.1, 8.2.2.2 Incorporated the integrated details related to PS-UCR-2009-041] the plant modifications made to the plant substation that describes the plant to substation interface, the new substation control houses and the related dc distribution system.
.1.4, 7.2.1.9.2, 7.2 Refs Added a qualification reference for the PS-UCR-2009-049] replacement isolation amplifiers installed in the plant.
.2.3, 6.2 Refs Added a reference to the analysis associated PS-UCR-2009-060] with air transport from the void between the containment sump valves SI-350A(B) and SI-351A(B).
ble 4.1-9 Revised the ASME Code reference with the PS-UCR-2009-064] applicable Addenda for the pressurizer.
.2.2 Revised the description of the Core Exit PS-UCR-2009-065] Thermocouples to include details related to current status and availability.
8.2, B.8.3 Revision made to reflect the current PS-UCR-2009-066] applicability of NUREG-0612 to the cranes in the plant.
.2.2 Revised the details related to the vital bus PS-UCR-2009-067] supply capability of the Reserve Auxiliary Transformer and Tertiary Auxiliary Transformer.
ble 5.2-3 Revised table with the normal operating PS-UCR-2009-069] position for three Reactor Coolant System sample valves.
.10 Removed the historical status formatting for PS-UCR-2009-075] section and revised text with current system terminology.
.2.4 Incorporated the details related to the plant PS-UCR-2009-076] modification that replaced the instrument bus transformers.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
0, 14.1.1, 14.1.2, 14.1.3, 14.1.4, 14.1.6, Updated USAR Section 14 to document the 1.8, 14.1.9, 14.1.11, 14.1.13, 14.2.5, safety analyses of certain non- LOCA bles 14.1.1-1, Table 14.1.1-2, transients and accidents performed with ble 14.1.2-1, Table 14.1.2-2, Table 14.1.4-1, Dominion analysis methods. These transients ble 14.1.6-1, Table 14.1.6-2, Table 14.1.8-1, and accidents were reanalyzed using an ble 14.1.8-2, Table 14.1.8-3, Table 14.1.8-4, approved methodology. This USAR change ble 14.1.9-1. Table 14.1.9-2, Table 14.1.9-3, and the completion of Cycle 29, the Dominion ble 14.1.11-1, Table 14.1.13-1, safety analyses becomes the analyses of record ures 14.1.1-1 through 14.1.1-5, (AOR) for KPS.
ures 14.1.2-1 through 14.1.2-3, ures 14.1.4-1 through 14.1.4-5, ures 14.1.5-1 through 14.1.5-5, ure 14.1.6-1 through 14.1.6-10, ures 14.1.8-1 through 14.1.8-33, ures 14.1.9-1 through 14.1.9-16, ures 14.1.11-1 through 14.1.11-6, ures 14.1.13-1 through 14.1.13-6, ble 14.2.5-1, Figure 14.2.5-3 through 2.5-20 22-014]
ure 1.1-2 Revised Figure 1.1-2 to include details 21-016] associated with the Independent Fuel Storage Installation.
apter 3 Chapter 3, Reactor revised in its entirety.
21-043] Changes included the removal of obsolete information added Dominion core and safety analysis methods as well as current fuel design and thermal performance criteria and analysis methods.
.2.3 Incorporated the details related to the plant 21-100] modification that reconfigured the seismic support components in the north spent fuel pool to provide clearance for the placement of the spent fuel shipping cask.
.1.2.2, 10.2.2.3, 10.2.3, 11.2.1.1, 11.2.3.1, Incorporate the changes resulting from the 2.3.3. 11.2.3.4, 11.2.3.5, 11.2.3.6, 11.2.3.13, design and licensing bases review of the 2.3.15, 11.2.3.17, 11.2.3.19, Table 11.2-7, Radiation Monitoring System.
ble 11.2-8 22-010]
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
, 4.1.2.4, 4.1.5.10, 4.1.5.12, 4.1.6, Incorporate the changes resulting from the ble 4.1-2, Table 4.1-3, Table 4.1-4, design and licensing bases review of the ble 4.1-9, Table 4.1-7, 4.2.1, 4.2.2.10, Reactor Coolant System
.5.4, 4.2 Refs, Table 4.2-1, Table 4.2-2, ure 4.2-2, Figure 4.2-9, 4.4.1.1, 4.4.1.6 22-025]
.8, 3.2.3.4.1, 5.2.1.35, Table 5.2-3, 5.4, Incorporate the changes resulting from the
.1, 5.4.1.1, 5.4.2, 5.4.2.1, 5.4.3.1, 5.4.3.3, design and licensing bases review of the Refs, 6.1.1, 6.3.1.1, 6.3.2.1, 6.3.2.2, Reactor Building Ventilation System.
.2.3, 6.3.2.6.2, 6.3.2.6.3, 6.3.2.6.4,
.4.2.1, 6.4.1 PS-UCR-2009-001]
.1.5, Table 6.3-3, 7.2.2.2, 10.2.2.6, 10.2.2.7, Incorporate the changes resulting from the 3.2, 14.0.4.1, 14.0.4.2, 14.1.6.1, 14.1.6.2, design and licensing bases review of the Main 1.6.3.2, 14.2.5.1 Feedwater System.
PS-UCR-2009-008]
.8, 1.5.5, 1.6.1, 5.1.1, 5.2.1.4.2, 5.2.2.1, Incorporate the changes resulting from the
.2.3.12, 5.3.2, Table 5.4-1, 5.5.1, 5.5.1.1, design and licensing bases review of the Shield
.2, 5.5.3, 5.5.4.2, 5.5.6.1, 5.5.6.2, 5.5 Refs, Building Ventilation System.
.1, 9.6.5.3, 9.6.5.5, 9.6.5.6, 9.6.5.7, 9.6.5.8,
.5.9, 9.6.6, 9.6 Refs, 14.3.6.1, H.1, H.2, 3.1, H.3.4, Table H.3-2 PS-UCR-2009-012]
.3.4, 7.2.3.5, 8.2.3.1, 8.2.3.5, 9.6.2.1, Incorporate the changes resulting from the
.2.2, 9.6.3.1, 9.6.3.2, 9.6.4.1, 9.6.5.3, design and licensing bases review of the
.6.3, 9.6.7, 9.6.7.1, 9.6.7.2, Figure 9.6-5 Turbine Building and Screenhouse Ventilation PS-UCR-2009-022] System.
.6, 9.6.6.1, 9.6.6.2, 9.6.6.3 Incorporate the changes resulting from the PS-UCR-2009-023] design and licensing bases review of the Technical Support Center Ventilation System.
.2.1 Incorporate the changes resulting from the PS-UCR-2009-038] design and licensing bases review of the Rod Control System.
.2.1 Incorporate the changes resulting from the PS-UCR-2009-039] design and licensing bases review of the Nuclear Instrumentation System.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
pendix 14A cover, Appendix 14B cover, Incorporate the changes resulting from the pendix 14C cover design and licensing bases review of PS-UCR-2009-040] Chapter 14 that resulted in deleting appendices 14A, 14B and 14C.
.1.3 Revised wording to more clearly reflect the PS-UCR-2009-042] analysis performed for License Amendment 150.
2.1, 1.2.5, 9.5.2.1.2, 9.5.2.1.3, 9.5.2.1.4, Incorporate the changes resulting from the
.2.1.5, 9.5.2.1.6, 9.5.2.2, 9.5.2.2.1, design and licensing bases review of the Fuel
.2.2.2, 9.5.2.2.3, 9.5.2.2.4, 9.5.2.2.5, Handling System.
.2.2.6, 9.5.2.2.7, 9.5.2.2.8, 9.5.2.2.9,
.3.1.2, 9.5.3.1.3, 9.5.3.2, 9.5.4, 9.5.5, Refs PS-UCR-2009-043]
.2.2, 3.1.3, 3.2.1.1.1, Table 3.2-1, 4.1.5.1, Incorporate the changes resulting from the
.5.4, 4.2.8, 5.5.5, 5.7.1.4, 8.2.3.1, 9.3.4.3.2, Improved Technical Specification Team 4.3 review of the USAR.
PS-UCR-2009-044]
ure 2.2-1, Figure 2.3-1, Figure 2.3-2, Replaced various USAR deteriorated figures ure 2.4-1, Figure 2.4-2, Figure 2.7-6, with legible replacements.
ure 4.2-5, Figure 9.5-1, Figure 10.2-10, ure 11.2-5, Figure 11.2-6 PS-UCR-2009-046]
.2 Revised the text to reflect that the boric acid PS-UCR-2009-047] evaporator bypass hose would only be used if the projected doses are within Off-Site Dose Calculation Manual and Technical Specifications limits.
.2, 7.1 Revised text to include a reference to General PS-UCR-2009-048] Design Criteria number 12 and other editorial changes.
.1.3, 7.2.2.4.1, 7.2.2.4.3, 7.2.2.4.4, Various editorial changes.
.2.4.5, 7.2.2.4.9, 7.2.2.4.10, 7.2.2.4.11,
.2.4.13, 7.2.2.4.14, 7.2.2.4.16, Table 7.2-1, ble 7.2-2, 7.7.6.1, 10.3.2 PS-UCR-2009-050]
Refs, Table 5.2-3 Revised table to provide added detail related to PS-UCR-2009-053] the position of valve SI-203A-1.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
ble 9.2-2 Revised table with a typical value for the boric PS-UCR-2009-056] acid tank volume required to achieve cold shutdown.
ble 10A.5-2 Revise Needed Equipment List for CVCS PS-UCR-2009-057] Letdown Rupture high energy line break evaluation.
.2.5, 8.2.2.6, 8.2.3.4, 8.2.4.5 Incorporate the changes resulting from the PS-UCR-2009-010] design and license basis review of the DC Electrical Supply and Distribution System.
.2, 1.9, Figure 2.4-1, Figure 2.4-2, 2.7.2.3, Editorial changes that properly formatted
.3, Figure 2.7-2, 2.8, 3.2.2.1, 3.2.2.2, Chapter 13 and changed KNPP to KPS
.2.7, 3.2.2.9, 3.2.3.1.5, 5.9, 5.9.2.18.2, throughout the USAR where appropriate.
.2.18.3, 6.2.2.2.8, 7.2.3.2.4, 7.2.3.4, 8.2.4.2, 2.2.1, 14.0.4, 14.0.4.1, 14.0.4.2, 14.0.5, 1.3.2.1, 14.1.3.2.2, 14.1.7.2, 14.1.7.3, 1.9.2, 14.1.12, 14.2.6.2, 14.3.2.2.1, 14.3.3, 3.3.2, 14.3.3.3, 14.3.3.3.1, 14.3.3.3.10, 3.3.4, 14.3.3.5, 14.3.3.6, 14.3.3.6.1, 3.3.6.2, 14.3.4, 14.3.5.1, 14.3.8, 14.3.9, ble 14.3.3-5, Table 14.3.3-7, ble 14.3.3-9,10, Figure 14.3.3-1, ure 14.3.3-2, Figure 14.3.3-3, ure 14.3.3-4, Figure 14.3.3-5, ure 14.3.3-6, Figure 14.3.3-7, ure 14.3.3-8, Figure 14.3.3-9, ure 14.3.3-10, Figure 14.3.3-11, ure 14.3.3-12, Figure 14.3.3-13, ure 14.3.3-14, B Refs, Table D.3-1, ble D.3-2, Table D.8-4, Chapter 13 (all)
PS-UCR-2009-015]
.2.3, 5.8.2.6, 5.8 Refs Remove reference to the use of Hydrogen PS-UCR-2009-020] Recombiners based on changes to 10CFR50.44 and approved License Amendment 174.
.2.4, 8.2.2.7 Incorporate the changes resulting from the PS-UCR-2009-025] design and license basis review of the 480 VAC Electrical Supply and Distribution System.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.2.3 Incorporate the changes resulting from the PS-UCR-2009-026] design and license basis review of the Station and Instrument Air System.
8.3, Appendix B Refs Provides a description of the seismic analysis PS-UCR-2009-029] methodology for the Auxiliary Building Crane.
.2.12, 9.5 Refs Editorial change to correct an error created by PS-UCR-2009-031] UCR R22-030.
4.2 Eliminated requirement related to IPEOP PS-UCR-2009-034] reviews based on approved License Amendment 193.
.1.27, 5.2 Refs Revision included added detail related to CR R21-071] Generic Letter 96-06 issues.
.2.15 Added a section to the fuel handling system CR R21-101] portion of the USAR to describe the systems added to the plant to support the loading of spent fuel dry storage canisters.
.1.4, 7.2.1.5, 7.2.2.1, 7.2.2.3.6, 7.2.2.4.8, Incorporate the changes resulting from the
.2.4.9, 7.2.2.4.10, 7.2.2.4.20, 7.2.3.1, design and license basis review of the Reactor
.3.2.3.1, 7.2.3.2.3.2, 7.2.3.2.4, 7.2.3.2.4.1, Protection System.
.3.2.4.2, 7.2.3.2.5, 7.2.3.2.6, 7.2.3.2.7,
.3.2.8, 7.2.3.4, Table 7.2-1, Table 7.2-2 CR R22-003]
.2.1, 3.1.2.2, 3.1.2.3, 3.1 Refs, 3.2.1.2.10, Incorporate the changes resulting from the
.3.1.1, 3.2.3.2.1.1, 3.2.3.2.5, 3.2.3.2.6, design and license basis review of Chapter 3
.3.2.10, 3.2.3.4.2, 3.2.3.4.3, 3.2.3.4.7, Reactor of the USAR.
.3.4.9, 3.2.3.4.11.1, 3.2.3.4.11.2,
.3.4.11.3, 3.2 Refs, 3.3.2, 3.3 Refs CR R22-004]
.1.1, 7.5.2.2.1, 7.5.2.2.2, 7.5.2.2.3, Incorporate the changes resulting from the
.2.2.4, 7.5.2.2.5, 7.5.2.2.6, 7.5.2.2.7, design and license basis review of the
.2.2.8, 7.5.2.2.9, 7.5.2.2.10, 7.5.2.2.10.1, Engineered Safety Features System.
.2.2.10.2, 7.5.2.2.11, 7.5.3.3, 7.5.3.3.2 CR R22-009]
, 7.7.1, 9.6.3.2, 9.6.4.1, 9.6.4.2, 9.6.4.3, Incorporate the changes resulting from the 2.1.1, 11.2.4 design and license basis review of the Control CR R22-018] Room HVAC System.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.2.2, 10.2.2.8 Incorporate the changes resulting from the CR R22-032] design and license basis review of the Circulating Water System.
ble 8.2-1, 9.2.2.20 Incorporate the details related to the plant 21-067] modification that replaced the drives for the Chemical and Volume Control system charging pumps.
.8, 2.7.5, 2.7 Refs, 5.1.1, Table 5.2-6, Incorporate the changes resulting from the
.3.2, 9.6.3.1, 9.6.3.2, 9.6.5.2, 9.6.5.3, design and licensing basis integrated review of
.5.5, 9.6.5.6, 9.6.5.9, 11.1.4, H.1, H.2 the Auxiliary Building Ventilation and the 22-001] Auxiliary Building Special Ventilation systems.
.1.4, 6.2.2.1.1, 6.2.2.1.4, 6.2.2.2.1, Incorporate the changes resulting from the
.2.2.3, 6.2.2.2.6, 6.2.2.2.11, 6.2.3.1, 6.2.3.4, design and licensing basis integrated review of
.3.7, 6.2.3.10, 6.2.4.3, 6.2.4.4, 7.5.2.4, the Safety Injection System.
.3.3.3 22-005]
.2.1.2, 6.2.2.2.5, Table 6.2-7, Table 6.2-13, Incorporate the changes resulting from the
.1.2.11, 9.3.3.2.3, 9.3.4.3.2 design and licensing basis integrated review of 22-011] the Residual Heat Removal System.
.1.2.10, 9.0, 9.3.2.1, 9.3.3.1.2, 9.3.4.2.1, Incorporate the changes resulting from the
.4.2.1, 9.3.4.3.2, 9.3.5 design and licensing basis integrated review of 22-020] the Component Cooling Water System.
.1, 2.6.2, 2.6.3.3, 2.6 Refs, 2.7.2.5, Incorporate the changes resulting from the 0 Refs design and licensing basis integrated review of 22-021] Chapter 2 that included the most current data available for the site.
, 2.6.2.1, 2.6.3.3, 2.6.4.1, Table 2.6-3, Incorporate the changes resulting from the ble 2.6-4, 2.7.2, Table 2.7-1, Table 2.7-2, design and licensing basis integrated review of ble 2.7-3, Table 2.7-4, Table 2.7-5, Chapter 2 that included the most current data ble 2.7-6, Table 2.7-7, Table 2.7-8, available for the site.
ure 2.7-1, Figure 2.7-2, Figure 2.7-3, ure 2.7-4, Figure 2.7-5, Figure 2.7-6, ure 2.7-7, Figure 2.7-8, Table 2.10-1 22-026]
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.5.1, 4.1.7, 4.1 Refs, 4.2.5.4, 4.2 Refs, Updated and clarified information related to
.1.1, 4.4 Refs, Table 4.4-2, 5.9.2, 5.9 Refs, reactor vessel integrity and fatigue criteria
.4.3.2, 9.3 Refs including neutron fluence, thermal 22-028] stratification and pressurized thermal shock.
.2, 2.6.2.4, 2.7.1, 2.7.2.4, 2.7.3, 2.7 Refs, Incorporate the changes resulting from the 0 design and licensing basis integrated review of 22-033] Chapter 2 that included the most current data available for the site.
.1.4 Clarified the description related to the CR 2009-003] inter-relationship between the Internal Containment Spray and the Containment Air Cooling systems.
ure 14.1.4-1, Figure 14.1.4-2, Editorial change that removed figures that are ure 14.1.4-3, Figure 14.1.4-4, no longer applicable that were not deleted in ure 14.1.4-5 USAR change request R18-023.
CR 2009-005]
ble 1.0-1, Figure 1.1-1, Figure 1.1-2, Revised the site map and related text to include ble B.2-1 the Augmented Water Building.
CR 2009-007]
2.3.21.1, 11.2 Refs Incorporated the details associated with the use CR 2009-009] of Weighting Factors in determining external dose.
.1, 7.3.2, 7.3.2.1, 7.3.2.2, 7.3.3.4, 7.7.2, Editorial change that eliminated multiple use
.3 of acronyms.
CR 2009-011]
.1.2.5 Revised text to clarify the method used to CR 2009-013] quantify leakage in containment using containment sump pump run time.
.4.4, 8.2.3.1, 8.2.3.3.1, 8.2.4.1, 8.2.4.3, Incorporate changes resulting from the design
.4.12 and licensing bases review of the Emergency 22-002] Diesel Generators including details relating to License Amendment 83.
ble B.2-1 Added the Fuel Transfer System as a Class III 22-006] system.
.2, 6.6.4, 6.6 Refs Incorporate changes resulting from the design 22-007] and licensing bases review of the Auxiliary Feedwater System including details relating to IE Bulletin 85-01 and Generic Letter 88-03.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
ure 11.2-1, Figure 11.2-2, Figure 11.2-3, Editorial errors corrected on figures and ure 11.2-4 replaced with revised drawings.
22-008]
Refs, Table 8.2-3 Revised Charging Pump Room operating 22-012] temperature limit based on NUMARC 87-00 guidance.
ure 6.2-3 Revised and replaced figure inadvertently 22-015] missed in USAR Change Request R20-069.
.2.4.8 Revised text to provide the basis for not 22-019] crediting the Negative Rate Trip in the Safety Analysis.
2.2.8 Incorporated detail related to a modification to 22-022] the Circulating Water System intake structure.
.3.3 Remove reference to and discussion related to 22-023] equipment that never existed in the plant.
Refs Incorporate the results of License Amendment 22-024] 199, Accumulator boron concentration change from 1900 ppm to 2400 ppm.
.1.4, 7.2.1.5 Move information to the appropriate location 22-027] to correct error created by USAR Change Request R18-003.
.2.12, 9.5.3.3, 9.5.4, 9.5 Refs, Table 9.5-2, Incorporate the results of License Amendment 2.1.1 200, Installing a single failure proof Auxiliary 22-030] Building Crane and removal of the restriction on carrying heavy loads over the spent fuel pool.
2.3.24 Revised the discussion on the maintenance of 22-031] Respiratory Protection Equipment to reflect current plant practice.
.3.1, 8.2 Refs Incorporate the results of License CR-2009-006] Amendment 203 that revises the fuel oil storage Technical Specification requirements for the Emergency Diesel Generators.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
ble 1.0-1, 6.5.1.2.13, Figure 9.6-2 Changes made to reflect plant modification 21-054] that replaced a flow instrument with a different type.
.2.5, 8.2.3.4, Table 8.2.2 Added details associated with plant 21-063] modification that replaced the station batteries BRA-101 and BRB-101.
.2.2 Changes are made to the discussion of the way 21-070] bypass flow around the RHR heat exchangers is controlled.
, 7.2.1.4, 14.3.1.4, 14.3.3 Changes made to the discussion of the small 21-074] break LOCA to clarify that certain small break LOCAs could cause RCS depressurization even though pressurizer level is maintained.
Also two erroneous references to another section of the USAR are removed and several editorial changes are included.
.3.4, 8.2.4.5 Changes based on revised calculation results 21-078] for battery and battery charger sizing.
8.1, B.8.2, B.8.3, B.8 Refs Revised based on Action Item B.4 of NEI 21-080] Industry Initiative on Heavy Load Lifts ble 8.2-2 Changes made to reflect revised battery 21-081] electrical calculations due plant modification that replaced the station batteries BRA-101 and BRB-101.
.1.4, 7.2.1.9.2, 7.2 Refs Revised to reflect plant modification that 21-084] replaced Foxboro Instruments with NUS Instruments.
.1.23.1 Added new type and grade for containment 21-090] penetrations.
ble 6.3-3 Removed information on the containment fan 21-094] coil units that could become obsolete due to repair activities and added a footnote to the table that directs the reader to the most current performance data.
ble B.2-1 Changes made to correct errors created during 21-096] USAR reformatting for Revision 20.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.1 Incorporate information related to plant 21-099] modification that replaced the Main Transformers ble 14.3.3-1 Changed Local to LOCA 21-104]
.3.3.1, 3.2 Refs Revised to document that the peak fuel rod 21-105] average burnup limit is 62 GWD/MTU for the 422 V+ fuel design based on License Amendment 198.
ble B.7-6 Correct administrative and technical error 21-106] created by inclusion of UCR R20-068 into the USAR.
.3.2 Delete incorrect redundant delay time and refer 21-112] to the location of the correct information.
.2.4 Revised to reflect changes to the flashing 21-048] system between the Shield Building and the Auxiliary Building.
ble 11.2-7 The changes made to reflect a name change of 21-049] the area and the associated instrument description.
.3, 6.2.2.1.1, 6.2.2.2.6, 6.2.2.3, 6.6.4.1, Incorporate missing details related to KPS 10.4 responses to Generic Letter 95-07 as required 21-057] by 10CFR50.71(e).
ure 4.2-11 Revised to reflect the new lithium control 21-089] program.
ble 5.2-3, 6.3.1.1, 6.4.1.5, 6.4.2.2.2, Incorporate changes resulting from the design
.2.2.4, 6.4.3.1, 6.4.3.4, 6.4.3.6, 6.4.4.4, and licensing bases review of the Internal Refs, Table 6.4-2, Table 6.4-3 Containment Spray System.
21-102]
.2.1.2, 6.2.3.5, 6.2.3.9.1, 6.2 Refs, Revised to reflect GSI-191 (Generic Letter ble 6.2-13, 9.3.3.2 2004-02) resolution activities.
21-108]
.2.1.3, 6.2.2.1.4, 6.2.2.1.5, 9.3.3 thru 9.3.5 Corrected paragraph numbering errors 21-110] introduced in Revision 20.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.3.5, 8.2 Refs, App B TOC, App B LOF, Incorporate details on specific protective 1.4, B.11.5, B.11 Refs, Figure B.11-1, features installed to mitigate internal flooding.
ure B.11-2 21-111]
.3.2, 8.2.3.3.1, 8.2.4.3, 8.2 Refs, Revised table, figure and text based on revised ble 8.2-1, Figure 8.2-10 electrical calculation.
21-113]
ble 1.0-1, Figures 1.2-1, 1.2-11, 1.2-2, 1.2-3, Replace 63 figures listed in Table 1.0-1 with
-4, 1.2-5, 1.2-6, 1.2-7, 1.2-8, 4.2-1, 5.4-1, the current revision and update table with
-5, 6.2-1, 6.2-2, 8.2-3, 8.2-5, 8.2-9, 9.2-2, current revision.
-3, 9.2-4, 9.2-5, 9.3-1, 9.3-2, 9.3-3, 9.3-4,
-1, 9.5-2, 9.6-1, 9.6-2, 9.6-3, 9.6-5, 9.6-6,
-7, 10.2-1, 10.2-2, 10.2-3, 10.2-4, 10.2-6, 2-7, 10.2-8, 10.2-9, 10A.3-2, 10A.3-3, A.3-4, 10A.3-5, 10A.3-6, 10A.3-7, 10A.4-2, A.4-3, 10A.4-4, 10A.4-5, 10A.4-6, 10A.4-7, A.5-2, 10A.6-2, 11.1-1, 11.1-2, 11.1-3, 1-4, 11.1-5, 11.2-1, 11.2-2, 11.2-3, 11.2-4 21-103]
.2.2.3, 6.3.2.4, 6.3.3.4, Table 6.3-3, Incorporate changes resulting from the design
.2.3.6, 9.6.2.1 and licensing bases review of the Service 21-098] Water System.
-2 Revised to describe the basis for the minimum 20-026] recirculation flow requirements for the Auxiliary Feedwater pumps.
2.3.15, Table 11.2-7 Revise Rad Monitor verbal description from 21-003] I&C Shop to Aux Bldg 626' elevation as a result of a plant modification.
.2.12, 9.5.3.3, 9.5.4, B.3, Table B.7-1, B.8 Revised to support first part of the upgrade of 21-029] the Auxiliary Building crane to single failure proof design.
.3.4 Revised based on the plant modification that 21-039] replaced the RHR pumps seal water coolers.
.3.2.2 Revised text to remove reference to RTD 21-045] bypass manifold local flow indicators. These indicators were eliminated as part of a plant modification.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.3.5 Added description of drain hole provided in 21-050] the trench barriers that matches the original as-built configuration. Adding the clarification aligns the description with the preceding paragraphs in the same section.
TOC, B.5, B.11, B.11.1, B.11.2, B.11.3, Revised section to correct formatting error 1.4, Refs created where letters were changed to 21-052] numbers. Added new section B.11 based on License Amendment 197 and added new references.
2.1, Refs Corrected administrative error to refer to the 21-058] correct reference and added discussion on how the station addressed Bulletin 80-11.
2.3.15 Added details related to local portable cart 21-059] mounted beta air monitors to more correctly describe the configuration.
ure 6.3-1, 14.1.8.4.3, 14.3.2 through Correct administrative error due to 3.11, 14.3 Refs, Tables 14.3.5-1 through 8, reformatting this section where a high level bles 14.3.3-1 through 14, Tables 14.3.5-1 step was renumbered incorrectly.
ough 12 21-060]
TOC, 1.0 Refs, 1.5.1, 1.6 Refs, 1.8 Refs, Modified references into standard format with TOC, 2.6 Refs, 2.7 Refs, 2.10 Refs, 4.0 reference listed after related section and add C, 5.0 TOC, 5.2 Refs, 5.4 Refs, 5.7 Refs, missing references.
.2.11, 5.9.2.14, 5.9.2.16, 5.9.2.21, 5.9 Refs, TOC, 6.1 Refs, 6.2 Refs, Table 6.2-5, Refs, 6.4.4.4, 6.4 Refs, 6.5 Refs, 6.6.2, Refs, 8.2.4.12, 9.0 TOC, 9.3.1.2, 9.3 Refs, Refs, 9.5 Refs, 9.6.1, 9.6 Refs, 12.6.2, 0 Refs, B.2.1, B Refs 21-061]
ble 8.2-2 Revised table to show the current major 21-064] safeguard battery loads based on revised calculation.
ble 11.2-7 Correct typographical errors related to the 21-066] range of R-40 and R-41 (Containment Hi Radiation Monitors).
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.2, 9.6.2.1, 9.6.3.2, 9.6.4.1, 9.6.5.6 Revised sections to show Spray water is from 21-069] the Service Water System for the applicable plant ventilation systems.
, 3.2.1.2.1, 3.2.1.2.3, 3.2.1.2.7, 3.2.2.3, Updated section to reflect the Cycle 29 Reload
.2.4, 3.2.2.5, 3.2.2.6, 3.2.2.7, 3.2.3.2.8, Core Design and Reload Safety Evaluation and Refs, Table 3.2-1, Table 3.2-2 the implementation of the IFBA fuel design.
21-072]
1.4.3.3 Added detail that describe the specific 21-075] guidance for actions to be taken when the Lo-Lo insertion limit alarm is received as required by License Amendment 110.
.3.5 Revised text to change meter to totalizer to 21-076] reflect the current design.
ble 5.2-3 Correct error created during reformatting 21-079] where Penetration Class designations changed from letters to numbers.
ble B.2-1 Added HP loading dock installed under a plant 21-082] modification.
TOC, 5.8.1, 5.8.2, Table 5.8-1, Table 5.8-2, Relocate USAR Section 14.3.7 to USAR ble 5.8-3, Table 5.8-4, Table 5.8-5, Section 5.8 as section 5.8.2 and add relevant ure 5.8-1, Figure 5.8-2, Figure 5.8-3, information from the NRC documents ure 5.8-4, Figure 5.8-5, 14.0 TOC, 14.3.8, associated with the revision of 10CFR50.44 3.5 Refs, 14.3.6 Refs, Table 14.3-10, dated October 23, 2003. This change ble 14.3-11, Table 14.3-12, Table 14.3-13, eliminated the design basis LOCA hydrogen ble 14.3-14, Figure 14.3-27, Figure 14.3-28, release from 10CFR50.44.
ure 14.3-29, Figure 14.3-30, Figure 14.3-31 21-083]
ble 6.2-4 Revises the Operating Temperature lower limit 21-087] in the Accumulator Design Parameters table.
.4 Revision to reflect the results of replacement 21-088] of safeguards undervoltage logic scheme electro-mechanical relays with solid-state relays requiring external DC control power.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
6.3, B Refs Updated to include the Design Basis for SSC 21-091] for Tornado Missile Protection Criteria and includes a description and references for the evaluation of peripheral SSC (EDG exhaust ducts and EDG fuel oil vent lines) for tornado effects.
1.4.2.1, 14.1.4.2.2 Restore information that was inadvertently 21-092] removed related to nuclear instrumentation available for the operator to detect boron concentration changing in the RCS associated with the analysis of a Chemical and Volume Control System Malfunction in the USAR.
ble B.2-1 Revises table to change the New Fuel Storage 21-093] from Class I to New Fuel Storage Racks, Class I*.
.2.5 Revise section to show the operator response 21-095] to Low - Low Rod Insertion Limit Alarm based on License Amendment 110 (T. S.
3-10.d.2.A).
ble 1.1-1 Corrected errors in plant drawing to USAR 21-056] figure cross-reference.
, 1.2.8, 1.3.4, 1.3.7, 1.5.5, 1.6.1, 1.8, 5.1.1, Editorial changes to system and component
.2.3, 5.4.3.5, 6.1.1.1, 6.1.1.4, 6.1.1.5, descriptions to be consistent with the plant
.2.1, 6.2.2.2.1, 6.3.1.1, 6.3.1.2, 6.3.1.3, database.
.1.4, 6.3.2.1, 6.3.2.2, 6.4, 6.4.1, 6.4.1.1,
.1.2, 6.4.1.3, 6.4.1.4, 6.4.1.5, 6.4.1.7,
.2.1, 6.4.2.1.2, 6.4.2.2, 6.4.2.2.1, 6.4.2.2.2,
.2.2.4, 6.4.2.2.5, 6.4.2.2.6, 6.4.2.3, 6.4.3.1,
.3.4, 6.4.3.5, 6.4.3.6, 6.4.4.1, 6.4.4.2,
.4.4, Table 6.4-1, 6.4-2, & 6.4-3, 7.2.1.2,
.1.3, 9.3.2.1, 9.6.5.1, 14.3.5.1.2, ble B.2-1, H.1 21-023]
.5, 1.3.7, 6.1.1.4, 14.1.10.1 Editorial change to current plant terminology.
21-044]
.1 Revised the description of meteorological 21-004] instrumentation type and availability.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.5.4, 4.1.5.10 Revised the description of the plant design 21-012] load rejection capability. Revised the description related to current plant practices associated with primary side leak tests.
Corrected the steam generator minimum temperature for secondary side hydrostatic test before initial startup.
ble 4.1-1 Revised value for reactor coolant system 21-027] volume as a result of steam generator replacement.
.1.2 Revised leak rate text to include the time frame 21-034] to be consistent with a statement in a subsequent section.
.4.2, 5.7.1.4, 11.2.4, 11.2 Refs, 14.1.8.3.1, Revised the description of the plant design 1.8.4, 14.1.8.4.1, 14.1.8.4.2, 14.1.8.4.3, basis radiological accident analysis based on 1.8.4.4, 14.1.9.1, Table 14.1.8-4, 14.2, license amendment 190.
2.1.2, 14.2.1.3, 14.2.1.4, 14.2.3.1.3, 2.3.1.4, 14.2.3.2.3, 14.2.3.2.4, 14.2.4.3, 2.4.4, 14.2.5.9, 14.2.5.10, 14.2.6.5, 2.6.6, 14.2.6.7, 14.2.7, 14.2 Refs, bles 14.2.1-1, 14.2.3-1, 14.2.4-1, 14.2.5-2, 2.6-3, & 14.2.6-4, 14.3.5, 14.3.5.1.2, 3.5.1.3, 14.3.5 Refs, Table 14.3-7, 14.3-8, 14.3-9, D.2, Tables D.3-1 & D.8-5,
- p. D Refs 21-026]
.2.4 Deleted reference to an ACI design method 21-035] that does not exist since it combines words from both methods.
.2.2.1, Tables 6.2-4 & 6.2-5 Revised text and associated tables to describe 21-041] the maximum boron concentration relationship between the safety injection accumulators and the refueling water storage tank. Included reference for the maximum boron concentration.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.2.2.2, Table 6.2-5, Ch 6 Refs, Table 9.3-2 Revised text and associated tables for license 20-045] amendment LA192 related to refueling water storage tank minimum and maximum boron concentration. Added new reference for LA192 safety evaluation.
ble 6.2-10, 9.6.2.1 Corrected terminology related to safety 21-022] injection pump lube oil coolers.
.1, 6.4.2.1.1, 6.4.3.1, 6.4.3.4, 6.4 Refs, Incorporated details associated with license 3.4.2.2, 14.3.4 Refs amendment 184 related to containment spray 21-046] flow path. Added references for LA184 SER.
.2.2 Clarified which portions of the internal 21-024] containment spray system are Class I and which are Class III.
Refs Added two references related to license 21-031] amendment 183.
.2.3.9, 7.5.2.3.10, 7.5 Refs Revised the description and application of the 21-019] containment sump level instrumentation.
Corrected letter reference number.
.2.48.2.2.1, 8.2.2.4, 8.2.2.5, 8.2.2.6, 8.2.3.1 Corrected reference figure numbers.
21-055]
.2.3, 8.2.3.2 Revised the source loading sequence 21-002] description to reflect current operation practices and procedural changes.
.3.2 Removed technical data from text and referred 21-011] to its location in the section table.
.3.3.1, Table 8.2-1, Figure 8.2-10, 9.3.2.17 Revised diesel generator loading data due to 21-006] the removal of the SFP cooling pumps from the loading sequence.
.3.4 Editorial change to reference identification.
21-042]
.4.3, 8.2.4.12, 8.2 Refs Revised description of QA Classification 21-053] change for the Technical Support Center diesel generator and included two related references.
.2, 9.2.2.38, 11.1.2.1.1, Figure 11.1-7 Revised description of the alternate path 21-037] around the boric acid evaporator/gas stripper.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
ble 9.5-1 Revised fuel handling data for the new fuel 21-021] storage pit.
.4.1, 9.6.4.2, 9.6.4.3 Revised the description of the control room air 21-009] conditioning system operation.
all & 9.9 all Deleted Sections 9.8 and 9.9 which are 21-025] redundant to Sections 5.8 and 5.9.
2.2.10, 10.4 Revised to include current technical reference 21-017] for turbine valve testing.
A.2.3.8 Transferred limiting condition and surveillance 21-033] requirements for steam exclusion from the USAR to technical requirements manual.
1.1.1, 11.1.2.1.1, 11.2.3, 11.2.3.21.1, Made editorial changes. Added detail on 2.3.26, 11.2.3.27, 11.2.4, 11.2.5 personnel radiation monitoring equipment.
21-013] Revised description to reflect current personnel radiation monitoring practices and procedures.
Added reference to off-site dose calculation manual (ODCM) for radiological releases.
1.1.1, 11.1.2.3, 11.1.3.2 Revised description of the handling and 21-038] disposal of gases in plant systems.
2.4.2, 14.2.4.3, 14.2.4.6, 14.2 Refs Clarified the safety analysis assumption 21-040] regarding the atmospheric steam dump use during a steam generator tube rupture.
2.4.5 Clarified the method available for steam 21-030] generator relief with a loss of off-site power.
2.5.2, 14.2.5.7 Clarified the analysis assumptions related to 21-014] high head safety injection head and flow degradation.
3.4.2.5 Editorial Change.
21-036]
bles 14.3.4-2, 14.3.4-3, & 14.3-7 Added notes to clarify the data provided in the 21-018] associated tables.
ble 14.3.4-4 Editorial change to table to remove header and 21-010] add LHSI which was inadvertently left out.
ble 14.3.4-5 Revised safety injection accumulator volume 21-008] terminology from gallon to cubic feet.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
2.1, Table B.2-1 Revised reference to a new level that was 21-028] added to an existing plant structure.
Revision 2004/07 Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
Updated applicable descriptions throughout to change bars)[R20-0XX] reflect the transfer of the facility from NMC to Dominion (e.g., KNPP changed to KPS)
Changed from Section to Chapter terminology Removed notations associated with previously deleted material and applied sequential numbering to paragraphs, tables, figures, and references Substituted consistent expressions in text (e.g.,
% changed to percent)
Applied consistent typeface and page layouts Improved consistency of measurement notation (e.g., time, mass, velocity), including abbreviations
, 2.2, 2.4, 2.5, 2.6.4, 2.7, 3.3.3, 4.2.2.6, Corrected typographical errors.
.1.6, Figure 4.2-11, 6.2.2.2.14, 7.5.3.3,
.3.3.4, 7.5.3.3.5, 7.7.5, 9.3.3.8, 9.6.1,
.5.6, Figure 10.2-11, 10A.1.2, 10A.3.3.6, 1.2.1.1, 11.1.2.4, 11.1.3.2, 11.2.3.22, 2.3.24, 11.2.3.26, Table 11.2-7, 12.3.2, 3.3, 12.4.7, 14.1.4.2, 14.1.5, 14.1.8, 1.8.3.1, 14.1.11.1, 14.3.4.1.2, 14.3.4.2, 3.5.1, 14.3.7.8, 14C.2.1, 3.2.3.2.1.1, ble 3.2.1, 5.9.2.18.3, 7.2.1.9.1, 10.2 Refs, ble 10A.3-2, Table 10A.4-2, ure 10A.4-10, 11.3.2, Table 13.1-1, 2.1.3, 14.3.3.1, 14.3.4 Refs, Table 14.3-1, A Refs, 14C.1.4, Table D.8-1, Attachment 1,
.1, H.2, H.4.2 20-079]
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.8, 8.2.3.4, Table 8.2-2 Clarified the description of the station batteries 20-016] and loss of all ac power.
.1, 12.4.1, 12.6 Improved the description of regional land use, 20-006] administrative directives, surveillance procedures, and safety review & administrative control.
.2 Clarified lake storm surge probable maximum 20-093] water level and controlled seepage into the screenhouse.
.2 Clarified elevation of screenhouse access 20-088] tunnel ramp.
.3.4.1, Table 4.2-4, 14.2.6 Replaced the reactor vessel closure head 20-040] including the control rod drive mechanisms.
Refs, 3.3 Refs Incorporated the revised reactor test program.
20-044]
Refs, Table B.7-1 Reflected current version of reactor vessel 20-039] head design report.
ble 4.1-9, 4.4.1.1, 5.2.1.29, 5.3.2, Allowed use of ASME III code allowables ble 10.1-2, Table 11.1-2, App. B.3, instead of USAS B31.1.
ble B.7-2, Table B.7-3, Table B.7-6 20-068]
.2.2 Inserted text regarding foreign obligations.
20-024]
.2.7 Corrected the description of use of component 20-034] cooling water supplied to the reactor coolant pumps.
ure 4.2-1 Modified reactor makeup water line.
20-010]
.4.2 Provided additional description of the reactor 20-083] vessel low temperature overpressure protection system.
.16 Updated description of Inservice Inspection 20-020] Program for fourth 10-year interval.
.2.1.2, 6.6 Refs, Table 6.2-6, Figure 6.2-4, Revised the description of the containment 3.2.3.1, Table 14.3.3-3 recirculation sump strainer.
20-069]
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.3.8, Table 6.2-12 Updated the description of the residual heat 20-027] removal system with respect to LOCA containment analysis and containment sump recirculation mode.
.1.2.13, 9.3.2.3, 10.2.2.8 Corrected typographical errors.
20-000]
.2 Clarified the description of auxiliary feedwater 20-067] pump operation.
.2, 6.6 Refs Revised the description of auxiliary feedwater 20-002] pump recirculation flow.
.2, 6.6.3, 9.6.2.2, Figure 10.2-3 Installed new suction pressure trip switches 19-046] and rerouted supply piping to the auxiliary feedwater pumps.
.3 Clarified the loss of normal feedwater accident 20-092] analysis assumptions for auxiliary feedwater pump operation.
, 13.1.3, 13.5 Reflected compliance with the Quality 20-084] Assurance Program Description.
.2.2 Revised the description of the core exit 20-022] thermocouples.
.2.2, 7.6.2.3, and 7.6.2.3.1 Corrected the description of control room 20-019] displays.
.2.2.1 Added the safety injection signal input for start 20-076] of component cooling pumps.
.6.1.3, 7.7.6.1.5, 7.7.6.2 Completed the list of indications and controls 20-077] located on the dedicated shutdown panel.
.6.2 Revised the description of the main feedwater 20-078] control valves.
.3.2 Revised the diesel generator loading 20-008] description.
.3.3.1 Added the description of non-safety related 20-046] loads assigned to the emergency buses.
.4.4 Updated the condensate inventory.
20-043]
.4.5 Clarified the description of the Class 1E 20-072] battery capacity.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
.4.7, Table 8.2-3 Clarified room and area temperature limits in 20-086] the event of station blackout.
.2.28, Table 9.2-2 Revised the quantity of boric acid required to 20-041] achieve cold shutdown.
.3.7, 11.2.3.1.8, 11.2.3.15 Revised the radiation monitor check source 20-048] response.
.1.3, 9.3.3.6, 9.3 Refs Provided additional description of spent fuel 20-047] pool cooling system operation.
.2.7 Replaced the flanged opening on the 20-075] component cooling surge tank with a capped connection.
.2.8 Provided a limit stop on a component cooling 20-028] water flow control valve to prevent pump runout.
.4 Corrected the description of use of component 20-085] cooling water to cool safety injection pumps.
ble 9.3-4 Corrected typographical error involving a 20-074] footnote notation.
.3.2, 12.2, 12.3.2, 12.4.1, 12.4.2, 12.4.3, Reflected compliance with the Dominion 4.4, 12.4.5, 12.4.6, 12.5, 12.6, 13.4.1, App. Nuclear Facility Quality Assurance Program Description.
20-036]
.1.1 Added statement of compliance with 20-009] 10 CFR 50.68.
.1.1 Provided editorial clarification of prevention 20-080] of fuel storage criticality.
ure 9.6-6 Modified the description of the control room 20-015] air conditioning system.
2.2.8 Installed float switches to provide circulating 20-007] water pump internal flooding trip.
2.2.10 Reduced the shaft speed that actuates the 20-091] turbine overspeed trip.
ure 10.2-9 Provided an alternate source of deionized 20-003] water to the self-regenerating suppressor in the in-line ion chromatograph.
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
4 Changed test frequency of mechanical trip 20-089] system from monthly to periodically.
A.2.1.2 Revised method of evaluation for high energy 19-045] line break analysis and break location selection.
ble 10A.2-3 Corrected damper nomenclature and 20-087] numbering. Corrected the actuation train for the control room outside air bypass damper.
ction 10A.12 Reinserted the description of jet impingement 20-005] load analysis that was inadvertently omitted.
bles 10A.3-1, 10A.3-3, 10A.4-1, 10A.5-2, Corrected references to motor control centers.
d 10A.6-2 20-004]
ure 10A.4-1 Corrected the description of the B feedwater 20-017] bypass line.
A.14, Table 10A.14-1 Added evaluation of condensate piping 20-014] downstream of the steam generator blowdown heat exchangers as a high energy line.
1.2.4 Revised the description of spent resin 20-033] containers.
ble 11.2-7 Changed the sensitivity values for radiation 20-042] monitoring channels R-16 and R-20.
1, 12.4.1, 12.4.3, 12.4.7, 12.6 Updated organizational and administrative 20-011] descriptions to reflect the transfer of Kewaunee Power Station from NMC to Dominion.
0.1, 14.0.4.1, 14.1.9.2, 14.1.11.2.5, Incorporated the fuel transition and stretch 1.13.2.6, 14.1 Refs power uprate. [10 CFR 50.90 License 20-038] Amendment]
1.11.3, 14.1.13.3, Table 14.1.12-1 Corrected the safety analysis input parameter 20-030] for pressurizer volume.
2.5.8, 14.2.5.11, 14.3.4.11, 14.3.4.1.1, Clarified the description of the containment 3.4.2, 14.3.4.2.4, 14.3.4.3 integrity safety analysis acceptance criteria.
20-018]
Changes Made under the provisions of 10 CFR 50.59 except tion where indicated in brackets.
3.1.4, 14.3.1.4, 14.3.1.5.1, 14.3.1.6, Incorporated the Reload Transition Safety 3.1.9, 14.3.1 Refs Report SBLOCA analysis. [10 CFR 50.90 20-037] License Amendment]
3.5.1, Reference 14.3.5.1, Table 14.3-7 Clarified the description of ECCS leakage to 20-029] the Auxiliary Building and updated the reference to the appropriate license amendment.
ure 14.3-25 Improved legibility of the graphs axis labels.
20-025]
ure 14.3-42 Deleted figure previously superceded by power 20-032] uprate containment integrity analysis.
ction B.2.1.6 Modified Doors 142 and 143 for tornado 20-070] atmospheric pressure change relief.
ction B.2.1.6 Installed breakaway pins on Door 49.
20-071]
ble B.2-1 Added note to clarify the classification of 20-021] structures, systems, and components.
3 Clarified the use of code editions with 20-090] documentation of reconciliation.
ble D.1-1 Corrected the activity values for Kr-85 and 20-073] Kr-85m.
Updated Safety Analysis Report Table of Contents tion Title Page VOLUME I eral Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . TOC-i of Effective Pages . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . LEP-1 APTER 1 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-1 1.0 Introduction and Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-1 1.1 Site and Environment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.1-1 1.2 Summary Plant Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.2-1 1.3 General Design Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.3-1 1.4 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.4-1 1.5 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.5-1 1.6 Research and Development Requirements. . . . . . . . . . . . . . . . . . . . . 1.6-1 1.7 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.7-1 1.8 Atomic Energy Commission (AEC) General Design Criteria . . . . . . 1.8-1 1.9 Facility Safety Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.9-1 APTER 2 SITE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-1 2.1 Summary and Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1-1 2.2 Location . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2-1 2.3 Topography. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.3-1 2.4 Population. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4-1 2.5 Land Use. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.5-1 2.6 Hydrology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.6-1 2.7 Meteorology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.7-1 2.8 Environmental Radioactivity Program . . . . . . . . . . . . . . . . . . . . . . . . 2.8-1 2.9 Geology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.9-1 2.10 Seismology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.10-1
Updated Safety Analysis Report Table of Contents (continued) tion Title Page APTER 3 REACTOR FUEL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1 3.1 Design Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1 3.2 Reactor Design . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-1 3.3 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-1 APTER 4 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.4-1 APTER 5 CONTAINMENT SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1-1 5.1 Containment System Concept . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1-1 5.2 Containment System Structure Design. . . . . . . . . . . . . . . . . . . . . . . . 5.2-1 5.3 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.3-1 5.4 Containment Vessel Air Handling System. . . . . . . . . . . . . . . . . . . . . 5.4-1 5.5 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.5-1 5.6 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.6-1 5.7 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.7-1 5.8 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.8-1 5.9 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.9-1 VOLUME II APTER 6 ENGINEERED SAFETY FEATURES . . . . . . . . . . . . . . . . . . . . . . . . . 6.1-1 6.1 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1-2 6.2 Safety Injection System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.2-1 6.3 Containment Air Cooling System . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.3-1 6.4 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.4-1 6.5 Leakage Detection and Provisions for the Primary and Auxiliary Coolant Loops . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.5-1 6.6 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.6-1
Updated Safety Analysis Report Table of Contents (continued) tion Title Page APTER 7 INSTRUMENTATION AND CONTROL . . . . . . . . . . . . . . . . . . . . . . 7.1-1 7.1 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.1-1 7.2 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.2-1 7.3 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.3-1 7.4 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.4-1 7.5 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.5-1 7.6 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.6-1 7.7 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.7-1 7.8 Plant Process Computer System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.8-1 APTER 8 ELECTRICAL SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.1-1 8.1 Design Basis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.1-1 8.2 Electrical System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8.2-1 APTER 9 AUXILIARY AND EMERGENCY SYSTEMS . . . . . . . . . . . . . . . . . . 9.1-1 9.1 General Design Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.1-1 9.2 Chemical and Volume Control System . . . . . . . . . . . . . . . . . . . . . . . 9.2-1 9.3 Auxiliary Coolant System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.3-1 9.4 deleted. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.4-1 9.5 Fuel Handling System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.5-1 9.6 Facility Services . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.6-1 9.7 Equipment and System Decontamination . . . . . . . . . . . . . . . . . . . . . 9.7-1 VOLUME III APTER 10 STEAM AND POWER CONVERSION SYSTEM . . . . . . . . . . . . . . . 10.1-1 10.1 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.1-1 10.2 System Design and Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.2-1 10.3 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.3-1
Updated Safety Analysis Report Table of Contents (continued) tion Title Page 10.4 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.4-1 Appendix 10A Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10A-i APTER 11 WASTE DISPOSAL AND RADIATION PROTECTION SYSTEM. 11.1-1 11.1 Waste Disposal System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.1-1 11.2 Radiation Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.2-1 11.3 Radioactive Materials Safety . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.3-1 APTER 12 CONDUCT OF OPERATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.1-1 12.1 General . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.1-1 12.2 Organization and Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . 12.2-1 12.3 Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.3-1 12.4 Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.4-1 12.5 Records and Reports. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12.5-1 12.6 Safety Review and Administrative Control . . . . . . . . . . . . . . . . . . . 12.6-1 APTER 13 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13.13-1 VOLUME IV APTER 14 SAFETY ANALYSIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.0-1 14.1 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.1-1 14.2 Standby Safety Features Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . 14.2-1 14.3 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14.3-1 Appendix 14A Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14A-i Appendix 14B Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14B-i Appendix 14C Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14C-i APTER 15 PROGRAMS AND ACTIVITIES THAT MANAGE THE
Updated Safety Analysis Report Table of Contents (continued) tion Title Page EFFECTS OF AGING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15-1 15.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15-1 15.2 Aging management. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15-3 15.3 Programs that Manage the Effects of Aging . . . . . . . . . . . . . . . . . . . 15-5 15.4 Time-Limited Aging Analyses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15-31 15.5 TLAA Support programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15-40 15.6 Exemptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15-43 15.7 License Renewal Commitments . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15-43 PENDIX A GEOLOGY & SEISMOLOGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-i A.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1 A.2 Geology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-2 A.3 Engineering Seismology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-7 A.4 Preliminary Earth Work and Foundation Evaluation. . . . . . . . . . . . A-15 Attachment 1Field Explorations And Laboratory Tests . . . . . . . . . . . . . . A-47 Attachment 2Definition of Seismic Terminology . . . . . . . . . . . . . . . . . . . A-83 Attachment 3Principal Sources of Data. . . . . . . . . . . . . . . . . . . . . . . . . . . A-85 PENDIX B SPECIAL DESIGN PROCEDURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-i B.1 Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-1 B.2 Classification of Structures and Components . . . . . . . . . . . . . . . . . . B-1 B.3 Design Codes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-10 B.4 Loads . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-11 B.5 Protection of Class I Items . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-14 B.6 Design Criteria for Structures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-15 B.7 Design Criteria for Components . . . . . . . . . . . . . . . . . . . . . . . . . . . B-33 B.8 Protection Against Crane Toppling and Control of Heavy Loads . . B-50 B.9 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-53 B.10 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-55 B.11 Internal Flooding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-55
Updated Safety Analysis Report Table of Contents (continued) tion Title Page B.12 Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-59 PENDIX C QUALITY ASSURANCE PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . C-i PENDIX D DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-i PENDIX E FOUNDATION DESIGN CRITERIA. . . . . . . . . . . . . . . . . . . . . . . . . . . . E-i E.1 Foundation Concept . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E-1 E.2 Report on Foundation Conditions1 . . . . . . . . . . . . . . . . . . . . . . . . . . E-9 E.3 Settlement Measurements During Construction . . . . . . . . . . . . . . . E-28 PENDIX F DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F-i PENDIX G EMERGENCY PLAN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-i PENDIX H DELETED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-i
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-1 15-62 Revision 2511/26/14 Appendix A rst Page Last Page Revision i A-vi Revision 2511/26/14 1 A-86 Revision 2511/26/14 Appendix B rst Page Last Page Revision i B-vi Revision 2511/26/14 1 B-62 Revision 2511/26/14 Appendix C rst Page Last Page Revision i C-ii Revision 2511/26/14 1 C-2 Revision 2511/26/14 Appendix D rst Page Last Page Revision i D-ii Revision 2511/26/14 Appendix E rst Page Last Page Revision i E-viii Revision 2511/26/14 1 E-114 Revision 2511/26/14 Appendix F rst Page Last Page Revision i F-ii Revision 2511/26/14 Appendix G rst Page Last Page Revision i G-ii Revision 2511/26/14 1 G-2 Revision 2511/26/14 Appendix H rst Page Last Page Revision i H-ii Revision 2511/26/14
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