ML19339C638

Attachment - VEGP U4 Amendment 168 (LAR-19-002)

ML19339C638
Person / Time
Site:	Vogtle
Issue date:	12/27/2019
From:	Chandu Patel NRC/NRR/VPOB
To:	Southern Nuclear Operating Co
Patel C
Shared Package
ML19337A667	List: ML19337A713 ML19337A741 ML19337A926 ML19337B139 ML19337B183 ML19337B326 ML19339C595 ML19339C638
References
LAR 19-002
Download: ML19339C638 (35)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 168 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO.52-026 Replace the following pages of the Facility Combined License No. NPF-92 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Facility Combined License No. NPF-92 REMOVE INSERT 7 7 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-46 C-46 C-183 C-183 C-193 C-193 C-201 C-201 C-205 C-205 C-211 C-211 C-222 C-222 C-236 C-236 C-242 C-242 C-248 C-248 C-253 C-253 C-258 C-258 C-262 C-262 C-265 C-265 C-269 C-269 C-271 C-271 C-275 C-275 C-278 C-278 C-280 C-280 C-283 C-283 continued on next page

Appendix C to Facility Combined License No. NPF-92 (contd)

REMOVE INSERT C-314 C-314 C-316 C-316 C-317 C-317 C-323 C-323 C-351 C-351 C-371 C-371 C-379 C-379 C-384 C-384 C-389 C-389 C-393 C-393 C-396 C-396 C-399 C-399

(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(b) SNC shall report any violation of a requirement in Section 2.D.(3),

Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.

(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 168, are hereby incorporated into this license.

(9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).

(10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:

(a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program

1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 168

Table 2.1.1-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 1 2.1.01.01 Not used per Amendment No. 168 2 2.1.01.02 Not used per Amendment No. 112 3 2.1.01.03 Not used per Amendment No. 85 4 2.1.01.04 2. The FHS has the refueling machine Inspection of the system will The FHS has the RM, the (RM), the fuel handling machine (FHM), be performed. FHM, and the new and spent and the new and spent fuel storage racks. fuel storage racks.

4. The RM and FHM/spent fuel handling The RM and FHM/SFHT The RM and FHM/SFHT tool (SFHT) gripper assemblies are gripper assemblies will be gripper assemblies will not designed to prevent opening while the tested by operating the open open while suspending a weight of the fuel assembly is suspended controls of the gripper while dummy test assembly.

from the grippers. suspending a dummy fuel assembly.

5. The lift height of the RM mast and FHM The RM and FHM will be The bottom of the dummy hoist(s) is limited such that the minimum tested by attempting to raise a fuel assembly cannot be required depth of water shielding is dummy fuel assembly. raised to within 24 ft, 6 in.

maintained. of the operating deck floor.

6. The RM and FHM are designed to i) Inspection will be i) The RM and FHM are maintain their load carrying and structural performed to verify that the located on the nuclear integrity functions during a safe shutdown RM and FHM are located on island.

earthquake. the nuclear island.

7. The new and spent fuel storage racks ii) Inspection will be ii) The new and spent fuel maintain the effective neutron performed to verify that the storage racks are located on multiplication factor required by 10 CFR new and spent fuel storage the nuclear island.

50.68 limits during normal operation, racks are located on the design basis seismic events, and design nuclear island.

basis dropped spent fuel assembly accidents over the spent fuel storage racks.

5 2.1.01.05 Not used per Amendment No. 112 6 2.1.01.06.i Not used per Amendment No. 112 7 2.1.01.06.ii 6. The RM and FHM are designed to ii) Type test, analysis, or a ii) A report exists and maintain their load carrying and structural combination of type tests and concludes that the RM and integrity functions during a safe shutdown analyses of the RM and FHM FHM can withstand seismic earthquake. will be performed. design basis dynamic loads without loss of load carrying or structural integrity functions.

C-46 Amendment No. 168

Table 2.3.1-1 Equipment Name Tag No. Display Control Function CCS Heat Exchanger Inlet Temperature CCS-121 Yes -

Sensor CCS Heat Exchanger Outlet Temperature CCS-122 Yes -

Sensor CCS Flow to Reactor Coolant Pump CCS-PL-V256A Yes -

(RCP) 1A Valve (Position Indicator)

CCS Flow to RCP 1B Valve (Position CCS-PL-V256B Yes -

Indicator)

CCS Flow to RCP 2A Valve (Position CCS-PL-V256C Yes -

Indicator)

CCS Flow to RCP 2B Valve (Position CCS-PL-V256D Yes -

Indicator)

Note: Dash (-) indicates not applicable.

Table 2.3.1-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 278 2.3.01.01 Not used per Amendment No. 168 279 2.3.01.02 Not used per Amendment No. 84 280 2.3.01.03.i 3. The CCS provides the nonsafety- i) Inspection will be performed i) A report exists and related functions of transferring heat for the existence of a report that concludes that the UA of each from the RNS during shutdown and the determines the heat transfer CCS heat exchanger is greater spent fuel pool cooling system during capability of the CCS heat than or equal to 14.0 million all modes of operation to the SWS. exchangers. Btu/hr-°F.

C-183 Amendment No. 168

Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 284 2.3.02.01 Not used per Amendment No. 168 285 2.3.02.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.3.2-1 as ASME Code Section the as-built components and design reports exist for the III are designed and constructed in piping as documented in the as-built components and accordance with ASME Code Section ASME design reports. piping identified in III requirements. Tables 2.3.2-1 and 2.3.2-2 as 2.b) The piping identified in Table ASME Code Section III.

2.3.2-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

3.a) Pressure boundary welds in Inspection of the as-built A report exists and concludes components identified in Table 2.3.2-1 pressure boundary welds will be that the ASME Code Section as ASME Code Section III meet ASME performed in accordance with III requirements are met for Code Section III requirements. the ASME Code Section III. non-destructive examination 3.b) Pressure boundary welds in piping of pressure boundary welds.

identified in Table 2.3.2-2 as ASME Code Section III meet ASME Code Section III requirements.

4.a) The components identified in Table A hydrostatic test will be A report exists and concludes 2.3.2-1 as ASME Code Section III performed on the components that the results of the retain their pressure boundary integrity and piping required by the hydrostatic test of the at their design pressure. ASME Code Section III to be components and piping 4.b) The piping identified in Table hydrostatically tested. identified in Tables 2.3.2-1 2.3.2-2 as ASME Code Section III and 2.3.2-2 as ASME Code retains its pressure boundary integrity at Section III conform with the its design pressure. requirements of the ASME Code Section III.

286 2.3.02.02b Not used per Amendment No. 84 287 2.3.02.03a Not used per Amendment No. 84 288 2.3.02.03b Not used per Amendment No. 84 289 2.3.02.04a Not used per Amendment No. 84 290 2.3.02.04b Not used per Amendment No. 84 C-193 Amendment No. 168

Table 2.3.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 318 2.3.03.01 Not used per Amendment No. 168 319 2.3.03.02 2. The ancillary diesel generator fuel Inspection will be performed for A report exists and concludes tank can withstand a seismic event. the existence of a report that the as-built ancillary verifying that the as-built diesel generator fuel tank and ancillary diesel generator fuel its anchorage are designed tank and its anchorage are using seismic Category II designed using seismic methods and criteria.

Category II methods and criteria.

320 2.3.03.03a 3.a) Each fuel oil storage tank provides Inspection of each fuel oil The volume of each fuel oil for at least 7 days of continuous storage tank will be performed. storage tank available to the operation of the associated standby standby diesel generator is diesel generator. greater than or equal to 55,000 gallons.

321 2.3.03.03b 3.b) Each fuel oil storage day tank Inspection of the fuel oil day The volume of each fuel oil provides for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of tank will be performed. day tank is greater than or operation of the associated standby equal to 1300 gallons.

diesel generator.

322 2.3.03.03c 3.c) The fuel oil flow rate to the day Testing will be performed to The flow rate delivered to tank of each standby diesel generator determine the flow rate. each day tank is 8 gpm or provides for continuous operation of the greater.

associated diesel generator.

323 2.3.03.03d 3.d) The ancillary diesel generator fuel Inspection of the ancillary diesel The volume of the ancillary tank is sized to supply power to long- generator fuel tank will be diesel generator fuel tank is term safety-related post accident performed. greater than or equal to monitoring loads and control room 650 gallons.

lighting through a regulating transformer and one PCS recirculation pump for four days.

324 2.3.03.04 4. Controls exist in the MCR to cause Testing will be performed on the Controls in the MCR operate the components identified in Table components in Table 2.3.3-1 to cause the components listed 2.3.3-1 to perform the listed function. using controls in the MCR. in Table 2.3.3-1 to perform the listed functions.

5. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.3.3-1 can be retrieved in the retrievability of parameters in Table 2.3.3-1 can be retrieved MCR. the MCR. in the MCR.

325 2.3.03.05 Not used per Amendment No. 112 C-201 Amendment No. 168

Table 2.3.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 326 2.3.04.01 Not used per Amendment No. 168 327 2.3.04.02.i 2. The FPS piping shown on Figure i) Inspection will be performed i) The piping shown on 2.3.4-2 remains functional following a to verify that the piping shown Figure 2.3.4-2 is located on safe shutdown earthquake. on Figure 2.3.4-2 is located on the Nuclear Island.

the Nuclear Island.

328 2.3.04.02.ii 2. The FPS piping shown on Figure ii) A reconciliation analysis ii) The as-built piping stress 2.3.4-2 remains functional following a using the as-designed and as- report exists and concludes safe shutdown earthquake. built piping information will be that the piping remains performed, or an analysis of the functional following a safe as-built piping will be shutdown earthquake.

performed.

329 2.3.04.03 Not used per Amendment No. 84 330 2.3.04.04.i 4. The FPS provides for manual fire i) Inspection of the passive i) The volume of the PCS fighting capability in plant areas containment cooling system tank above the standpipe containing safety-related equipment. (PCS) storage tank will be feeding the FPS and below the performed. overflow is at least 18,000 gal.

6. The FPS provides nonsafety-related Inspection of the containment The FPS has spray headers containment spray for severe accident spray headers will be performed. and nozzles as follows:

management. At least 44 nozzles at plant elevation of at least 260 feet, and 24 nozzles at plant elevation of at least 275 feet.

7. The FPS provides two fire water Inspection of each fire water The volume of water storage tanks, each capable of holding storage tank will be performed. dedicated to FPS use provided at least 100 percent of the water supply in each fire water storage tank necessary for FPS use. is at least 396,000 gallons.

331 2.3.04.04.ii 4. The FPS provides for manual fire ii) Testing will be performed by ii) Water is simultaneously fighting capability in plant areas measuring the water flow rate as discharged from each of the containing safety-related equipment. it is simultaneously discharged two highest fire-hose stations from the two highest fire-hose in plant areas containing stations and when the water for safety-related equipment at the fire is supplied from the PCS not less than 75 gpm.

storage tank.

332 2.3.04.05 5. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.3.4-1 can be retrieved in the retrievability of the parameters Table 2.3.4-1 can be retrieved MCR. in the MCR. in the MCR.

333 2.3.04.06 Not used per Amendment No. 112 334 2.3.04.07 Not used per Amendment No. 112 C-205 Amendment No. 168

Table 2.3.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 339 2.3.05.01 Not used per Amendment No. 168 340 2.3.05.02.i 2. The seismic Category I equipment i) Inspection will be performed i) The seismic Category I identified in Table 2.3.5-1 can withstand to verify that the seismic equipment identified in seismic design basis loads without loss Category I equipment identified Table 2.3.5-1 is located on the of safety function. in Table 2.3.5-1 is located on the Nuclear Island.

Nuclear Island.

ii) Type tests, analyses, or a ii) A report exists and combination of type tests and concludes that the seismic analyses of seismic Category I Category I equipment can equipment will be performed. withstand seismic design basis loads without loss of safety function.

iii) Inspection will be performed iii) A report exists and for the existence of a report concludes that the as-built verifying that the as-built equipment including equipment including anchorage anchorage is seismically is seismically bounded by the bounded by the tested or tested or analyzed conditions. analyzed conditions.

341 2.3.05.02.ii Not used per Amendment No. 84 342 2.3.05.02.iii Not used per Amendment No. 84 343 2.3.05.03a.i 3.a) The polar crane is single failure i) Validation of double design i) A report exists and proof. factors is provided for hooks concludes that the polar crane where used as load bearing is single failure proof. A components. Validation of certificate of conformance redundant factors is provided for from the vendor exists and load bearing components such concludes that the polar crane as: is single failure proof.

• Hoisting ropes

• Sheaves

• Equalizer assembly

• Holding brakes 344 2.3.05.03a.ii 3.a) The polar crane is single failure ii) Testing of the polar crane is ii) The polar crane shall be proof. performed. static-load tested to 125% of the rated load.

iii) Testing of the polar crane is iii) The polar crane shall lift a performed. test load that is 100% of the rated load. Then it shall lower, stop, and hold the test load.

345 2.3.05.03a.iii Not used per Amendment No. 112 C-211 Amendment No. 168

Table 2.3.6-3 Equipment Name Tag No. Display Control Function RNS Pump 1A (Motor) RNS-MP-01A Yes Start (Run Status)

RNS Pump 1B (Motor) RNS-MP-01B Yes Start (Run Status)

RNS Flow Sensor RNS-01A Yes -

RNS Flow Sensor RNS-01B Yes -

RNS Suction from Cask Loading RNS-PL-V055 Yes -

Pit Isolation Valve (Position Indicator)

RNS Pump Miniflow Isolation RNS-PL-V057A Yes -

Valve (Position Indicator)

RNS Pump Miniflow Isolation RNS-PL-V057B Yes -

Valve (Position Indicator)

Note: Dash (-) indicates not applicable.

Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 354 2.3.06.01 Not used per Amendment No. 168 355 2.3.06.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.3.6-1 as ASME Code Section the as-built components and design reports exist for the III are designed and constructed in piping as documented in the as-built components and accordance with ASME Code ASME design reports. piping identified in Section III requirements. Tables 2.3.6-1 and 2.3.6-2 as 2.b) The piping identified in Table ASME Code Section III.

2.3.6-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

3.a) Pressure boundary welds in Inspection of the as-built A report exists and concludes components identified in Table 2.3.6-1 pressure boundary welds will be that the ASME Code Section as ASME Code Section III meet ASME performed in accordance with III requirements are met for Code Section III requirements. the ASME Code Section III. non-destructive examination 3.b) Pressure boundary welds in piping of pressure boundary welds.

identified in Table 2.3.6-2 as ASME Code Section III meet ASME Code Section III requirements.

C-222 Amendment No. 168

Table 2.3.7-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 391 2.3.07.01 Not used per Amendment No. 168 392 2.3.07.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.3.7-1 as ASME Code the ASME as-built components design reports exist for the Section III are designed and constructed and piping lines as documented as-built components and in accordance with ASME Code in the ASME design reports. piping lines identified in Section III requirements. Tables 2.3.7-1 and 2.3.7-2 as 2.b) The piping lines identified in Table ASME Code Section III.

2.3.7-2 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

3. Pressure boundary welds in piping Inspection of the as-built A report exists and concludes lines identified in Table 2.3.7-2 as pressure boundary welds will be that the ASME Code Section ASME Code Section III meet ASME performed in accordance with III requirements are met for Code Section III requirements. the ASME Code Section III. non-destructive examination of pressure boundary welds.

4. The piping lines identified in Table A hydrostatic test will be A report exists and concludes 2.3.7-2 as ASME Code Section III performed on the piping lines that the results of the retain their pressure boundary integrity required by the ASME Code hydrostatic test of the piping at their design pressure. Section III to be hydrostatically lines identified in Table tested. 2.3.7-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.

393 2.3.07.02b Not used per Amendment No. 84 394 2.3.07.03 Not used per Amendment No. 84 395 2.3.07.04 Not used per Amendment No. 84 396 2.3.07.05.i 5. The seismic Category I components i) Inspection will be performed i) The seismic Category I identified in Table 2.3.7-1 can withstand to verify that the seismic components identified in seismic design basis loads without loss Category I components Table 2.3.7-1 are located on of safety functions. identified in Table 2.3.7-1 are the Nuclear Island.

located on the Nuclear Island.

ii) Type tests, analyses, or a ii) A report exists and combination of type tests and concludes that the seismic analyses of seismic Category I Category I equipment can equipment will be performed. withstand seismic design basis loads without loss of safety function.

C-236 Amendment No. 168

Table 2.3.8-1 Equipment Name Tag No. Display Control Function Service Water Pump A Discharge Temperature SWS-005A Yes -

Sensor Service Water Pump B Discharge Temperature SWS-005B Yes -

Sensor Service Water Cooling Tower Basin Level SWS-009 Yes -

Note: Dash (-) indicates not applicable.

Table 2.3.8-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 414 2.3.08.01 Not used per Amendment No. 168 415 2.3.08.02.i 2. The SWS provides the nonsafety- i) Testing will be performed to i) Each SWS pump can related function of transferring heat confirm that the SWS can provide at least 10,000 gpm of from the component cooling water provide cooling water to the cooling water through its CCS system to the surrounding atmosphere CCS heat exchangers. heat exchanger.

to support plant shutdown and spent fuel pool cooling.

3. Controls exist in the MCR to cause Testing will be performed on the Controls in the MCR operate the components identified in Table components in Table 2.3.8-1 to cause the components listed 2.3.8-1 to perform the listed function. using controls in the MCR. in Table 2.3.8-1 to perform the listed functions.

4. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.3.8-1 can be retrieved in the retrievability of parameters in Table 2.3.8-1 can be retrieved MCR. the MCR. in the MCR.

416 2.3.08.02.ii 2. The SWS provides the nonsafety- ii) Inspection will be performed ii) A report exists and related function of transferring heat for the existence of a report that concludes that the heat from the component cooling water determines the heat transfer transfer rate of each cooling system to the surrounding atmosphere capability of each cooling tower tower cell is greater than or to support plant shutdown and spent cell. equal to 170 million Btu/hr at fuel pool cooling. a 80.1°F ambient wet bulb temperature and a cold water temperature of 90°F.

417 2.3.08.02.iii 2. The SWS provides the nonsafety- iii) Testing will be performed to iii) The SWS tower basin related function of transferring heat confirm that the SWS cooling contains a usable volume of at from the component cooling water tower basin has adequate reserve least 230,000 gallons at the system to the surrounding atmosphere volume. basin low level alarm setpoint.

to support plant shutdown and spent fuel pool cooling.

C-242 Amendment No. 168

Table 2.3.9-2 Power Group Room Equipment Name Tag Number Function Number Location No.

Hydrogen Igniter 55 VLS-EH-55 Energize 1 Refueling cavity 11504 Hydrogen Igniter 56 VLS-EH-56 Energize 2 Refueling cavity 11504 Hydrogen Igniter 57 VLS-EH-57 Energize 2 Refueling cavity 11504 Hydrogen Igniter 58 VLS-EH-58 Energize 1 Refueling cavity 11504 Hydrogen Igniter 59 VLS-EH-59 Energize 2 Pressurizer compartment 11503 Hydrogen Igniter 60 VLS-EH-60 Energize 1 Pressurizer compartment 11503 Hydrogen Igniter 61 VLS-EH-61 Energize 1 Upper compartment-upper region 11500 Hydrogen Igniter 62 VLS-EH-62 Energize 2 Upper compartment-upper region 11500 Hydrogen Igniter 63 VLS-EH-63 Energize 1 Upper compartment-upper region 11500 Hydrogen Igniter 64 VLS-EH-64 Energize 2 Upper compartment-upper region 11500 Hydrogen Igniter 65 VLS-EH-65 Energize 1 IRWST roof vents 11500 Hydrogen Igniter 66 VLS-EH-66 Energize 2 IRWST roof vents 11500 Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 420 2.3.09.01 Not used per Amendment No. 168 421 2.3.09.02a 2.a) The hydrogen monitors identified Testing will be performed by A simulated test signal exists in Table 2.3.9-1 are powered by the providing a simulated test signal at the hydrogen monitors non-Class 1E dc and UPS system. in each power group of the identified in Table 2.3.9-1 non-Class 1E dc and UPS when the non-Class 1E dc and system. UPS system is provided the test signal.

422 2.3.09.02b 2.b) The components identified in Testing will be performed by A simulated test signal exists Table 2.3.9-2 are powered from their providing a simulated test signal at the equipment identified in respective non-Class 1E power group. in each non-Class 1E power Table 2.3.9-2 when the group. assigned non-Class 1E power group is provided the test signal.

423 2.3.09.03.i Not used per Amendment No. 112 C-248 Amendment No. 168

Table 2.3.10-2 Line Name Line No. ASME Section III Functional Capability Required WLS Drain from PXS WLS-PL-L062 Yes Yes Compartment A WLS Drain from PXS WLS-PL-L063 Yes Yes Compartment B WLS Drain from CVS WLS-PL-L061 Yes Yes Compartment Table 2.3.10-3 Equipment Name Tag No. Display Active Function WLS Effluent Discharge Isolation WLS-PL-V223 - Close Valve Reactor Coolant Drain Tank Level WLS-JE-LT002 Yes -

Letdown Flow from CVS to WLS WLS-JE-FT020 Yes -

WLS Auxiliary Building RCA WLS-400A Yes -

Floodup Level Sensor WLS Auxiliary Building RCA WLS-400B Yes -

Floodup Level Sensor Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 430 2.3.10.01 Not used per Amendment No. 168 431 2.3.10.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.3.10-1 as ASME Code Section the as-built components and design report exists for the as III are designed and constructed in piping as documented in the built components and piping accordance with ASME Code ASME design reports. identified in Tables 2.3.10-1 Section III requirements. and 2.3.10-2 as ASME Code 2.b) The piping identified in Table Section III.

2.3.10-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

C-253 Amendment No. 168

2.3.11 Gaseous Radwaste System Design Description The gaseous radwaste system (WGS) receives, processes, and discharges the radioactive waste gases received within acceptable off-site release limits during normal modes of plant operation including power generation, shutdown and refueling.

The WGS is as shown in Figure 2.3.11-1 and the component locations of the WGS are as shown in Table 2.3.11-3.

1. The functional arrangement of the WGS is as described in the Design Description of this Section 2.3.11.

2. The equipment identified in Table 2.3.11-1 can withstand the appropriate seismic design basis loads without loss of its structural integrity function.

3. The WGS provides the nonsafety-related functions of:

a. Processing radioactive gases prior to discharge.

b. Controlling the releases of radioactive materials in gaseous effluents.

c. The WGS is purged with nitrogen on indication of high oxygen levels in the system.

Table 2.3.11-1 Seismic Equipment Name Tag No. Category I WGS Activated Carbon Delay Bed A WGS-MV-02A No(1)

WGS Activated Carbon Delay Bed B WGS-MV-02B No(1)

WGS Discharge Isolation Valve WGS-PL-V051 No Note:

1. The WGS activated carbon delay beds (WGS-MV-02A and B) are designed to one-half SSE.

Table 2.3.11-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 449 2.3.11.01 Not used per Amendment No. 168 C-258 Amendment No. 168

2.3.12 Solid Radwaste System Design Description The solid radwaste system (WSS) receives, collects, and stores the solid radioactive wastes received prior to their processing and packaging by mobile equipment for shipment off-site.

The component locations of the WSS are as shown in Table 2.3.12-2.

1. The functional arrangement of the WSS is as described in the Design Description of this Section 2.3.12.

2. The WSS provides the nonsafety-related function of storing radioactive spent resins prior to processing or shipment.

Table 2.3.12-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 456 2.3.12.01 Not used per Amendment No. 168 457 2.3.12.02 2. The WSS provides the nonsafety- Inspection will be performed to A report exists and concludes related function of storing radioactive verify that the volume of each of that the volume of each of the solids prior to processing or shipment. the spent resin tanks, spent resin tanks, WSS-WSS-MV01A and MV01A and WSS-MV01B, is WSS-MV01B, is at least 250 ft3. at least 250 ft3.

Table 2.3.12-2 Component Name Tag No. Component Location WSS Spent Resin Tank A WSS-MV-01A Auxiliary Building WSS Spent Resin Tank B WSS-MV-01B Auxiliary Building 2.3.13 Primary Sampling System Design Description The primary sampling system collects samples of fluids in the reactor coolant system (RCS) and the containment atmosphere during normal operations.

The PSS is as shown in Figure 2.3.13-1. The PSS Grab Sampling Unit (PSS-MS-01) is located in the Auxiliary Building.

C-262 Amendment No. 168

Table 2.3.13-2 Equipment Name Tag No. Control Function Hot Leg 1 Sample Isolation Valve PSS-PL-V001A Transfer Open/Transfer Closed Hot Leg 2 Sample Isolation Valve PSS-PL-V001B Transfer Open/Transfer Closed Table 2.3.13-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 458 2.3.13.01 Not used per Amendment No. 168 459 2.3.13.02 2. The components identified in Table Inspection will be conducted of The ASME Code Section III 2.3.13-1 as ASME Code Section III are the as-built components as design reports exist for the as-designed and constructed in accordance documented in the ASME design built components identified in with ASME Code Section III reports. Table 2.3.13-1 as ASME Code requirements. Section III.

3. Pressure boundary welds in Inspection of the as-built A report exists and concludes components identified in Table 2.3.13-1 pressure boundary welds will be that the ASME Code Section as ASME Code Section III meet ASME performed in accordance with III requirements are met for Code Section III requirements. the ASME Code Section III. non-destructive examination of pressure boundary welds.

4. The components identified in Table A hydrostatic test will be A report exists and concludes 2.3.13-1 as ASME Code Section III performed on the components that the results of the retain their pressure boundary integrity required by the ASME Code hydrostatic test of the at their design pressure. Section III to be hydrostatically components identified in tested. Table 2.3.13-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.

460 2.3.13.03 Not used per Amendment No. 84 461 2.3.13.04 Not used per Amendment No. 84 C-265 Amendment No. 168

2.3.14 Demineralized Water Transfer and Storage System Design Description The demineralized water transfer and storage system (DWS) receives water from the demineralized water treatment system (DTS), and provides a reservoir of demineralized water to supply the condensate storage tank and for distribution throughout the plant. Demineralized water is processed in the DWS to remove dissolved oxygen. In addition to supplying water for makeup of systems which require pure water, the demineralized water is used to sluice spent radioactive resins from the ion exchange vessels in the chemical and volume control system (CVS), the spent fuel pool cooling system (SFS), and the liquid radwaste system (WLS) to the solid radwaste system (WSS).

The component locations of the DWS are as shown in Table 2.3.14-3.

1. The functional arrangement of the DWS is as described in the Design Description of this Section 2.3.14.

2. The DWS provides the safety-related function of preserving containment integrity by isolation of the DWS lines penetrating the containment.

3. The DWS condensate storage tank (CST) provides the nonsafety-related function of water supply to the FWS startup feedwater pumps.

4. Displays of the parameters identified in Table 2.3.14-1 can be retrieved in the main control room (MCR).

Table 2.3.14-1 Equipment Name Tag No. Display Control Function Condensate Storage Tank Water Level DWS-006 Yes -

Note: Dash (-) indicates not applicable.

Table 2.3.14-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 477 2.3.14.01 Not used per Amendment No. 168 478 2.3.14.02 Not used per Amendment No. 84 C-269 Amendment No. 168

3. Displays of the parameters identified in Table 2.3.15-1 can be retrieved in the main control room (MCR).

Table 2.3.15-1 Equipment Name Tag No. Display Control Function Instrument Air Pressure CAS-011 Yes -

Note: Dash (-) indicates not applicable.

Table 2.3.15-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 481 2.3.15.01 Not used per Amendment No. 168 482 2.3.15.02 Not used per Amendment No. 84 483 2.3.15.03 3. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.3.15-1 can be retrieved in the retrievability of parameters in Table 2.3.15-1 can be MCR. the MCR. retrieved in the MCR.

Table 2.3.15-3 Component Name Tag No. Component Location Instrument Air Compressor Package A CAS-MS-01A Turbine Building Instrument Air Compressor Package B CAS-MS-01B Turbine Building Instrument Air Dryer Package A CAS-MS-02A Turbine Building Instrument Air Dryer Package B CAS-MS-02B Turbine Building Service Air Compressor Package A CAS-MS-03A Turbine Building Service Air Compressor Package B CAS-MS-03B Turbine Building Service Air Dryer Package A CAS-MS-04A Turbine Building Service Air Dryer Package B CAS-MS-04B Turbine Building High Pressure Air Compressor and Filter CAS-MS-05 Turbine Building Package C-271 Amendment No. 168

Table 2.3.29-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 488 2.3.29.01 Not used per Amendment No. 168 489 2.3.29.02 2. The WRS collects liquid wastes from A test is performed by pouring The water poured into these the equipment and floor drainage of the water into the equipment and drains is collected either in the radioactive portions of the auxiliary floor drains in the radioactive auxiliary building radioactive building, annex building, and radwaste portions of the auxiliary drains sump or the WLS waste building and directs these wastes to a building, annex building, and holdup tanks.

WRS sump or WLS waste holdup tanks radwaste building.

located in the auxiliary building.

3. The WRS collects chemical wastes A test is performed by pouring The water poured into these from the auxiliary building chemical water into the auxiliary building drains is collected in the laboratory drains and the chemical laboratory and the chemical waste tank of the decontamination solution drains in the decontamination solution drains liquid radwaste system.

annex building and directs these wastes in the annex building.

to the chemical waste tank of the liquid radwaste system.

490 2.3.29.03 Not used per Amendment No. 112 491 2.3.29.04 4. The WWS stops the discharge from Tests will be performed to A simulated high radiation the turbine building sumps upon confirm that a simulated high signal causes the turbine detection of high radiation in the radiation signal from the turbine building sump pumps discharge stream to the oil separator. building sump discharge (WWS-MP-01A and B, and radiation monitor, WWS-021 WWSMP07A and B) to stop causes the sump pumps operating, stopping the spread (WWS-MP-01A and B, and of radiation outside of the WWSMP07A and B) to stop turbine building.

operating, stopping the spread of radiation outside of the turbine building.

C-275 Amendment No. 168

Table 2.4.1-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 492 2.4.01.01 Not used per Amendment No. 168 493 2.4.01.02 2. The FWS provides startup feedwater Testing will be performed to Each FWS startup feedwater flow from the CST to the SGS for heat confirm that each of the startup pump provides a flow rate removal from the RCS. feedwater pumps can provide greater than or equal to water from the CST to both 260 gpm to each steam steam generators. generator system at a steam generator secondary side pressure of at least 1106 psia.

3. Controls exist in the MCR to cause Testing will be performed on the Controls in the MCR operate the components identified in Table components in Table 2.4.1-1 to cause the components listed 2.4.1-1 to perform the listed function. using controls in the MCR. in Table 2.4.1-1 to perform the listed functions.

4. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.4.1-1 can be retrieved in the retrievability of parameters in Table 2.4.1-1 can be retrieved MCR. the MCR. in the MCR.

494 2.4.01.03 Not used per Amendment No. 112 495 2.4.01.04 Not used per Amendment No. 112 Table 2.4.1-3 Component Name Tag No. Component Location Startup Feedwater Pump A FWS-MP-03A Turbine Building Startup Feedwater Pump B FWS-MP-03B Turbine Building C-278 Amendment No. 168

2.4.2 Main Turbine System Design Description The main turbine system (MTS) is designed for electric power production consistent with the capability of the reactor and the reactor coolant system.

The component locations of the MTS are as shown in Table 2.4.2-2.

1. The functional arrangement of the MTS is as described in the Design Description of this Section 2.4.2.

2. a) Controls exist in the MCR to trip the main turbine-generator.

b) The main turbine-generator trips after receiving a signal from the PMS.

c) The main turbine-generator trips after receiving a signal from the DAS.

3. The overspeed trips for the AP1000 turbine are set for 110% and 111% (+/-1% each). Each trip is initiated electrically in separate systems. The trip signals from the two turbine electrical overspeed protection trip systems are isolated from, and independent of, each other.

Table 2.4.2-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 496 2.4.02.01 Not used per Amendment No. 168 497 2.4.02.02a 2.a) Controls exist in the MCR to trip Testing will be performed on the Controls in the MCR operate the main turbine-generator. main turbine-generator using to trip the main turbine-controls in the MCR. generator.

2.c) The main turbine-generator trips Testing will be performed using The main turbine-generator after receiving a signal from the DAS. real or simulated signals into the trips after receiving a signal DAS. from the DAS.

3) The trip signals from the two turbine ii) Testing of the as-built system ii) The main turbine-generator electrical overspeed protection trip will be performed using trips after overspeed signals systems are isolated from, and simulated signals from the are received from the speed independent of, each other. turbine speed sensors. sensors of the 110%

emergency electrical overspeed trip system, and the main turbine-generator trips after overspeed signals are received from the speed sensors of the 111% backup electrical overspeed trip system.

C-280 Amendment No. 168

Table 2.4.6-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 503 2.4.06.01 Not used per Amendment No. 168 504 2.4.06.02 2. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.4.6-1 can be retrieved in the retrievability of the parameters Table 2.4.6-1 can be retrieved MCR. in the MCR. in the MCR.

Table 2.4.6-3 Component Name Component Location Low Pressure Feedwater Heaters Turbine Building Deaerator Feedwater Heater and Storage Tank Turbine Building Main Condenser Shell A Turbine Building Main Condenser Shell B Turbine Building Main Condenser Shell C Turbine Building Condensate Pump A Turbine Building Condensate Pump B Turbine Building Condensate Pump C Turbine Building 2.4.7 Circulating Water System No entry for this system.

2.4.8 Auxiliary Steam Supply System No entry for this system.

2.4.9 Condenser Tube Cleaning System No entry for this system.

2.4.10 Turbine Island Chemical Feed System No entry for this system.

2.4.11 Condensate Polishing System No entry for this system.

C-283 Amendment No. 168

b) The Class 1E cables between the Incore Thermocouple elements and the connector boxes located on the integrated head package have sheaths.

c) For cables other than those covered by 3.b, separation is provided between IIS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.

4. Safety-related displays of the parameters identified in Table 2.5.5-1 can be retrieved in the main control room (MCR).

Table 2.5.5-1 Seismic ASME Code Qual. for Safety-Related Equipment Name Cat. I Classification Class 1E Harsh Envir. Display Incore Thimble Yes - Yes(1) Yes(1) Core Exit Assemblies (at least Temperature(1) three assemblies in each core quadrant)

Note: Dash (-) indicates not applicable.

1. Only applies to the safety-related assemblies. There are at least two safety-related assemblies in each core quadrant.

Table 2.5.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 564 2.5.05.01 Not used per Amendment No. 168 565 2.5.05.02.i 2. The seismic Category I equipment i) Inspection will be performed i) The seismic Category I identified in Table 2.5.5-1 can withstand to verify that the seismic equipment identified in seismic design basis dynamic loads Category I equipment identified Table 2.5.5-1 is located on the without loss of safety function. in Table 2.5.5-1 is located on the Nuclear Island.

Nuclear Island.

ii) Type tests, analyses, or a ii) A report exists and combination of type tests and concludes that the seismic analyses of seismic Category I Category I equipment can equipment will be performed. withstand seismic design basis dynamic loads without loss of safety function.

C-314 Amendment No. 168

2.5.6 Special Monitoring System Design Description The special monitoring system (SMS) monitors the reactor coolant system (RCS) for the occurrence of impacts characteristic of metallic loose parts. Metal impact monitoring sensors are provided to monitor the RCS at the upper and lower head region of the reactor pressure vessel, and at the reactor coolant inlet region of each steam generator.

1. The functional arrangement of the SMS is as described in the Design Description of this Section 2.5.6.

2. Data obtained from the metal impact monitoring sensors can be retrieved in the main control room (MCR).

Table 2.5.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 573 2.5.06.01 Not used per Amendment No. 168 574 2.5.06.02 2. Data obtained from the metal impact Inspection will be performed for Data obtained from the metal monitoring sensors can be retrieved in retrievability of data from the impact monitoring sensors can the MCR. metal impact monitoring sensors be retrieved in the MCR.

in the MCR.

2.5.7 Operation and Control Centers System No ITAAC for this system.

2.5.8 Radiation Monitoring System No entry. Radiation monitoring function covered in Section 3.5, Radiation Monitoring.

C-316 Amendment No. 168

2.5.9 Seismic Monitoring System Design Description The seismic monitoring system (SJS) provides for the collection of seismic data in digital format, analysis of seismic data, notification of the operator if the ground motion exceeds a threshold value, and notification of the operator (after analysis of data) that a predetermined cumulative absolute velocity (CAV) has been exceeded. The SJS has at least four triaxial acceleration sensor units and a time-history analyzer and recording system. The time-history analyzer and recording system are located in the auxiliary building.

1. The functional arrangement of the SJS is as described in the Design Description of this Section 2.5.9.

2. The SJS can compute CAV and the 5 percent of critical damping response spectrum for frequencies between 1 and 10 Hertz.

3. The SJS has a dynamic range of 0.001g to 1.0g and a frequency range of 0.2 to 50 Hertz.

Table 2.5.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 575 2.5.09.01 Not used per Amendment No. 168 576 2.5.09.02 2. The SJS can compute CAV and the 5 Type tests using simulated input A report exists and concludes percent of critical damping response signals, analyses, or a that the SJS time-history spectrum for frequencies between 1 and combination of type tests and analyzer and recording system 10 Hz. analyses, of the SJS time-history can record data at a sampling analyzer and recording system rate of at least 200 samples will be performed. per second, that the pre-event recording time is adjustable from less than or equal to 1.2 seconds to greater than or equal to 15.0 seconds, and that the initiation value is adjustable from less than or equal to 0.002g to greater than or equal to 0.02g.

577 2.5.09.03 3. The SJS has a dynamic range of Type tests, analyses, or a A report exists and concludes 0.001g to 1.0g and a frequency range of combination of type tests and that the SJS triaxial 0.2 to 50 Hertz. analyses, of the SJS triaxial acceleration sensors have a acceleration sensors will be dynamic range of at least performed. 0.001g to 1.0g and a frequency range of at least 0.2 to 50 Hertz.

C-317 Amendment No. 168

Table 2.6.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 578 2.6.01.01 Not used per Amendment No. 168 579 2.6.01.02.i 2. The seismic Category I equipment i) Inspection will be performed i) The seismic Category I identified in Table 2.6.1-1 can withstand to verify that the seismic equipment identified in seismic design basis loads without loss Category I equipment identified Table 2.6.1-1 is located on the of safety function. in Table 2.6.1-1 is located on the Nuclear Island.

Nuclear Island.

ii) Type tests, analyses, or a ii) A report exists and combination of type tests and concludes that the seismic analyses of seismic Category I Category I equipment can equipment will be performed. withstand seismic design basis loads without loss of safety function.

iii) Inspection will be performed iii) A report exists and for the existence of a report concludes that the as-built verifying that the as-built equipment including equipment including anchorage anchorage is seismically is seismically bounded by the bounded by the tested or tested or analyzed conditions. analyzed conditions.

580 2.6.01.02.ii Not used per Amendment No. 84 581 2.6.01.02.iii Not used per Amendment No. 84 582 2.6.01.03a 3.a) The Class 1E breaker control Testing will be performed on the A simulated test signal exists power for the equipment identified in ECS by providing a simulated at the Class 1E equipment Table 2.6.1-1 are powered from their test signal in each Class 1E identified in Table 2.6.1-1 respective Class 1E division. division. when the assigned Class 1E division is provided the test signal.

583 2.6.01.03b Not used per Amendment No. 84 584 2.6.01.04a Not used per Amendment No. 112 585 2.6.01.04b Not used per Amendment No. 84 C-323 Amendment No. 168

2.6.4 Onsite Standby Power System Design Description The onsite standby power system (ZOS) provides backup ac electrical power for nonsafety-related loads during normal and off-normal conditions.

The ZOS has two standby diesel generator units and the component locations of the ZOS are as shown in Table 2.6.4-2. The centerline of the diesel engine exhaust gas discharge is located more than twenty (20) feet higher than that of the combustion air intake.

1. The functional arrangement of the ZOS is as described in the Design Description of this Section 2.6.4.

2. The ZOS provides the following nonsafety-related functions:

a) On loss of power to a 6900 volt diesel-backed bus, the associated diesel generator automatically starts and produces ac power at rated voltage and frequency. The source circuit breakers and bus load circuit breakers are opened, and the generator is connected to the bus.

b) Each diesel generator unit is sized to supply power to the selected nonsafety-related electrical components.

c) Automatic-sequence loads are sequentially loaded on the associated buses.

3. Displays of diesel generator status (running/not running) and electrical output power (watts) can be retrieved in the main control room (MCR).

4. Controls exist in the MCR to start and stop each diesel generator.

Table 2.6.4-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 621 2.6.04.01 Not used per Amendment No. 168 C-351 Amendment No. 168

Table 2.7.1-3 Equipment Tag No. Display Control Function Division "B" and "D" Class 1E VBS-MA-05D Yes Start Electrical Room AHU D Fans VBS-MA-06D (Run Status)

Division "A" and "C" Class 1E VBS-MA-07A Yes Start Battery Room Exhaust Fans VBS-MA-07C (Run Status)

Division "B" and "D" Class 1E VBS-MA-07B Yes Start Battery Room Exhaust Fans VBS-MA-07D (Run Status)

MCR Ancillary Fans VBS-MA-10A No -

VBS-MA-10B Division B Room Ancillary Fan VBS-MA-11 No -

Division C Room Ancillary Fan VBS-MA-12 No -

Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 677 2.7.01.01 Not used per Amendment No. 168 678 2.7.01.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.7.1-1 as ASME Code the as-built components and design reports exist for the Section III are designed and constructed piping as documented in the as-built components and in accordance with ASME Code ASME design reports. piping identified in Section III requirements. Tables 2.7.1-1 and 2.7.1-2 as 2.b) The piping identified in Table ASME Code Section III.

2.7.1-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

3.a) Pressure boundary welds in Inspection of the as-built A report exists and concludes components identified in Table 2.7.1-1 pressure boundary welds will be that the ASME Code Section as ASME Code Section III meet ASME performed in accordance with III requirements are met for Code Section III requirements. the ASME Code Section III. nondestructive examination of 3.b) Pressure boundary welds in piping pressure boundary welds.

identified in Table 2.7.1-2 as ASME Code Section III meet ASME Code Section III requirements.

C-371 Amendment No. 168

Table 2.7.2-1 Control Equipment Name Tag No. Display Function CVS Pump Room Unit Cooler Fan B VAS-MA-07B Yes Start (Run Status)

RNS Pump Room Unit Cooler Fan A VAS-MA-08A Yes Start (Run Status)

RNS Pump Room Unit Cooler Fan B VAS-MA-08B Yes Start (Run Status)

Air-cooled Chiller Water Valve VWS-PL-V210 Yes Open (Position Status)

Air-cooled Chiller Water Valve VWS-PL-V253 Yes Open (Position Status)

Table 2.7.2-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 701 2.7.02.01 Not used per Amendment No. 168 702 2.7.02.02 Not used per Amendment No. 84 703 2.7.02.03a 3.a) The VWS provides chilled water Testing will be performed by The water flow to each to the supply air handling units serving measuring the flow rates to the cooling coil equals or exceeds the MCR, the Class 1E electrical rooms, chilled water cooling coils. the following:

and the unit coolers serving the RNS and CVS pump rooms. Coil Flow (gpm)

VBS MY C01A/B 96 VBS MY C02A/C 97 VBS MY C02B/D 52 VAS MY C07A/B 12.3 VAS MY C12A/B 8.2 VAS MY C06A/B 8.2

4. Controls exist in the MCR to cause Testing will be performed on the Controls in the MCR operate the components identified in Table components in Table 2.7.2-1 to cause the components listed 2.7.2-1 to perform the listed function. using controls in the MCR. in Table 2.7.2-1 to perform the listed functions.

5. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.7.2-1 can be retrieved in the retrievability of parameters in Table 2.7.2-1 can be retrieved MCR. the MCR. in the MCR.

C-379 Amendment No. 168

Table 2.7.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 707 2.7.03.01 Not used per Amendment No. 168 708 2.7.03.02a Not used per Amendment No. 84 709 2.7.03.02b Not used per Amendment No. 84 710 2.7.03.03 3. Controls exist in the MCR to cause Testing will be performed on the Controls in the MCR operate the components identified in components in Table 2.7.3-1 to cause the components listed Table 2.7.3-1 to perform the listed using controls in the MCR. in Table 2.7.3-1 to perform the function. listed functions.

4. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.7.3-1 can be retrieved in the retrievability of the parameters Table 2.7.3-1 can be retrieved MCR. in the MCR. in the MCR.

711 2.7.03.04 Not used per Amendment No. 112 Table 2.7.3-3 Component Name Tag No. Component Location Annex Building General Area AHU A VXS-MS-01A Annex Building Annex Building General Area AHU B VXS-MS-01B Annex Building Annex Building Equipment Room AHU A VXS-MS-02A Annex Building Annex Building Equipment Room AHU B VXS-MS-02B Annex Building MSIV Compartment A AHU-A VXS-MS-04A Auxiliary Building MSIV Compartment B AHU-B VXS-MS-04B Auxiliary Building MSIV Compartment B AHU-C VXS-MS-04C Auxiliary Building MSIV Compartment A AHU-D VXS-MS-04D Auxiliary Building Switchgear Room AHU A VXS-MS-05A Annex Building C-384 Amendment No. 168

Table 2.7.4-1 Equipment Name Tag No. Display Control Function Diesel Oil Transfer Module Enclosure A VZS-MY-V03A Yes Start Exhaust Fan (Run Status)

Diesel Oil Transfer Module Enclosure A VZS-MY-U03A Yes Energize Electric Unit Heater (Run Status)

Diesel Oil Transfer Module Enclosure B VZS-MY-V03B Yes Start Exhaust Fan (Run Status)

Diesel Oil Transfer Module Enclosure B VZS-MY-U03B Yes Energize Electric Unit Heater (Run Status)

Table 2.7.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 712 2.7.04.01 Not used per Amendment No. 168 713 2.7.04.02a Not used per Amendment No. 84 714 2.7.04.02b Not used per Amendment No. 84 715 2.7.04.02c Not used per Amendment No. 84 716 2.7.04.03 3. Controls exist in the MCR to cause Testing will be performed on the Controls in the MCR operate the components identified in components in Table 2.7.4-1 to cause the components listed Table 2.7.4-1 to perform the listed using controls in the MCR. in Table 2.7.4-1 to perform the function. listed functions.

4. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.7.4-1 can be retrieved in the retrievability of the parameters Table 2.7.4-1 can be retrieved MCR. in the MCR. in the MCR.

717 2.7.04.04 Not used per Amendment No. 112 C-389 Amendment No. 168

2.7.5 Radiologically Controlled Area Ventilation System Design Description The radiologically controlled area ventilation system (VAS) serves the fuel handling area of the auxiliary building, and the radiologically controlled portions of the auxiliary and annex buildings, except for the health physics and hot machine shop areas, which are provided with a separate ventilation system (VHS). The VAS consists of two subsystems: the auxiliary/annex building ventilation subsystem and the fuel handling area ventilation subsystem. The subsystems provide ventilation to maintain occupied areas, and access and equipment areas within their design temperature range. They provide outside air for plant personnel and prevent the unmonitored release of airborne radioactivity to the atmosphere or adjacent plant areas. The VAS automatically isolates selected building areas by closing the supply and exhaust duct isolation dampers and starts the containment air filtration system (VFS) when high airborne radioactivity in the exhaust air duct or high ambient pressure differential is detected.

The component locations of the VAS are as shown in Table 2.7.5-3.

1. The functional arrangement of the VAS is as described in the Design Description of this Section 2.7.5.

2. The VAS maintains each building area at a slightly negative pressure relative to the atmosphere or adjacent clean plant areas.

3. Displays of the parameters identified in Table 2.7.5-1 can be retrieved in the main control room (MCR).

Table 2.7.5-1 Equipment Tag No. Display Control Function Fuel Handling Area Pressure Differential Indicator VAS-030 Yes -

Annex Building Pressure Differential Indicator VAS-032 Yes -

Auxiliary Building Pressure Differential Indicator VAS-033 Yes -

Auxiliary Building Pressure Differential Indicator VAS-034 Yes -

Note: Dash (-) indicates not applicable.

Table 2.7.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 718 2.7.05.01 Not used per Amendment No. 168 C-393 Amendment No. 168

Table 2.7.6-1 Control Equipment Tag No. Display Function Containment Exhaust Fan A VFS-MA-02A Yes Start (Run Status)

Containment Exhaust Fan B VFS-MA-02B Yes Start (Run Status)

Containment Exhaust Fan A Flow Sensor VFS-011A Yes -

Containment Exhaust Fan B Flow Sensor VFS-011B Yes -

Table 2.7.6-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 723 2.7.06.01 Not used per Amendment No. 168 724 2.7.06.02.i Not used per Amendment No. 84 725 2.7.06.02.ii 2. The VFS provides the safety-related ii) Testing will be performed to ii) The containment vacuum functions of preserving containment demonstrate that remotely relief isolation valves integrity by isolation of the VFS lines operated containment vacuum (VFS-PL-V800A and penetrating containment and providing relief isolation valves open VFS-PL-V800B) open within vacuum relief for the containment within the required response 30 seconds.

vessel. time.

C-396 Amendment No. 168

2.7.7 Containment Recirculation Cooling System Design Description The containment recirculation cooling system (VCS) controls the containment air temperature and humidity during normal operation, refueling and shutdown.

The locations of the VCS are as shown in Table 2.7.7-3.

1. The functional arrangement of the VCS is as described in the Design Description of this Section 2.7.7.

2. Displays of the parameters identified in Table 2.7.7-1 can be retrieved in the main control room (MCR).

Table 2.7.7-1 Equipment Name Tag No. Display Containment Temperature Channel VCS-061 Yes Containment Fan Cooler Fan VCS-MA-01A Yes (Run Status)

VCS-MA-01C Yes (Run Status)

VCS-MA-01B Yes (Run Status)

VCS-MA-01D Yes (Run Status)

Note: Dash (-) indicates not applicable.

Table 2.7.7-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 731 2.7.07.01 Not used per Amendment No. 168 732 2.7.07.02 2. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.7.7-1 can be retrieved in the retrievability of the parameters Table 2.7.7-1 are retrieved in MCR. in the MCR. the MCR.

C-399 Amendment No. 168