ML18019A861

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Attachment - Vogtle Electric Generating Plant Unit 4 LAR 17-038
ML18019A861
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/06/2018
From: Jordan Hoellman
NRC/NRO/DNRL/LB4
To: Whitley B
Southern Nuclear Operating Co
hoellman j/415-5481
Shared Package
ML18019A854 List:
References
LAR 17-038, EPID L-2017-LLA-0389
Download: ML18019A861 (125)
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Text

ATTACHMENT TO LICENSE AMENDMENT NO. 112 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-2 C-2 C-46 C-46 C-47 C-47 C-64 C-64 C-64a C-64a C-65 C-65

--- C-65a C-66 C-66 C-67 C-67 C-77 C-77 C-79 C-79 C-99 C-99 C-110 C-110 C-111 C-111

--- C-111a

--- C-111b C-112 C-112 C-113 C-113 C-133 C-133

--- C-133a C-134 C-134 C-139 C-139

REMOVE INSERT

--- C-139a C-140 C-140 C-141 C-141 C-161 C-161 C-162 C-162

--- C-162a C-163 C-163 C-177 C-177 C-177a C-177a

--- C-177b C-178 C-178 C-179 C-179 C-183 C-183

--- C-183a C-184 C-184 C-195 C-195

--- C-195a C-196 C-196 C-197 C-197 C-201 C-201 C-205 C-205 C-211 C-211 C-212 C-212

--- C-212a C-213 C-213 C-226 C-226

--- C-226a C-227 C-227 C-228 C-228 C-238 C-238 C-242 C-242 C-243 C-243 C-248 C-248 C-249 C-249

--- C-249a

REMOVE INSERT C-255 C-255 C-256 C-256 C-267 C-267 C-273 C-273 C-274 C-274 C-275 C-275 C-278 C-278 C-280 C-280

--- C-280a C-281 C-281 C-287 C-287

--- C-287a C-288 C-288 C-289 C-289 C-299 C-299

--- C-299a C-300 C-300 C-301 C-301 C-302 C-302 C-312 C-312 C-313 C-313 C-323 C-323 C-324 C-324

--- C-324a C-340 C-340

--- C-340a

--- C-340b C-341 C-341 C-342 C-342 C-343 C-343

--- C-343a C-344 C-344 C-352 C-352

--- C-352a C-353 C-353

REMOVE INSERT C-354 C-354 C-355 C-355 C-356 C-356 C-357 C-357 C-360 C-360 C-361 C-361 C-362 C-362 C-363 C-363 C-364 C-364

--- C-364a C-365 C-365 C-373 C-373 C-374 C-374

--- C-374a C-379 C-379 C-380 C-380 C-384 C-384 C-389 C-389 C-394 C-394

--- C-394a C-396 C-396

--- C-396a C-397 C-397 C-439 C-439

--- C-439a C-440 C-440 C-447 C-447

--- C-447a

(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR 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 hours1 days <br />0.143 weeks <br />0.0329 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. 112, 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. 112

2.3.10 Liquid Radwaste System ...................................................................................... C-250 2.3.11 Gaseous Radwaste System ................................................................................. C-258 2.3.12 Solid Radwaste System ....................................................................................... C-262 2.3.13 Primary Sampling System .................................................................................... C-262 2.3.14 Demineralized Water Transfer and Storage System ........................................... C-269 2.3.15 Compressed and Instrument Air System ............................................................. C-270 2.3.16 Potable Water System .......................................................................................... C-272 2.3.17 Waste Water System ............................................................................................ C-272 2.3.18 Plant Gas System ................................................................................................. C-272 2.3.19 Communication System ....................................................................................... C-272 2.3.20 Turbine Building Closed Cooling Water System .................................................. C-274 2.3.21 Secondary Sampling System ............................................................................... C-274 2.3.22 Containment Leak Rate Test System .................................................................. C-274 2.3.23 This section intentionally blank ............................................................................ C-274 2.3.24 Demineralized Water Treatment System ............................................................. C-274 2.3.25 Gravity and Roof Drain Collection System........................................................... C-274 2.3.26 This section intentionally blank ............................................................................ C-274 2.3.27 Sanitary Drainage System .................................................................................... C-274 2.3.28 Turbine Island Vents, Drains, and Relief System ................................................ C-274 2.3.29 Radioactive Waste Drain System ......................................................................... C-274 C.2.3.30 Storm Drain System .......................................................................................... C-277 C.2.3.31 Raw Water System ........................................................................................... C-277 C.2.3.32 Yard Fire Water System ................................................................................... C-277 2.4 Steam and Power Conversion Systems .................................................................. C-277 2.4.1 Main and Startup Feedwater System ................................................................... C-277 2.4.2 Main Turbine System............................................................................................ C-280 2.4.3 Main Steam System ............................................................................................. C-282 2.4.4 Steam Generator Blowdown System ................................................................... C-283 2.4.5 Condenser Air Removal System .......................................................................... C-283 2.4.6 Condensate System ............................................................................................. C-283 C-2 Amendment No. 112

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 1. The functional arrangement of the FHS Inspection of the as-built The as-built FHS conforms is as described in the Design Description of system will be performed. with the functional this Section 2.1.1. arrangement as described in the Design Description of this Section 2.1.1.

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. 112

Table 2.1.1-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 8 2.1.01.07.i 7. The new and spent fuel storage racks i) Analyses will be performed i) The calculated effective maintain the effective neutron to calculate the effective neutron multiplication factor multiplication factor required by 10 CFR neutron multiplication factor for the new and spent fuel 50.68 limits during normal operation, in the new and spent fuel storage racks meets the design basis seismic events, and design storage racks during normal requirements of basis dropped spent fuel assembly conditions. 10 CFR 50.68(1) limits under accidents over the spent fuel storage racks. normal conditions.

9 2.1.01.07.ii Not used per Amendment No. 112 10 2.1.01.07.iii 7. The new and spent fuel storage racks iii) Seismic analysis of the iii) A report exists and maintain the effective neutron new and spent fuel storage concludes that the new and multiplication factor required by 10 CFR racks will be performed. spent fuel racks can 50.68 limits during normal operation, withstand seismic design design basis seismic events, and design basis dynamic loads and basis dropped spent fuel assembly maintain the calculated accidents over the spent fuel storage racks. effective neutron multiplication factor required by 10 CFR 50.68(1) limits.

11 2.1.01.07.iv 7. The new and spent fuel storage racks iv) Analysis of the spent fuel iv) A report exists and maintain the effective neutron storage racks under design concludes that the spent fuel multiplication factor required by 10 CFR basis dropped spent fuel racks can withstand design 50.68 limits during normal operation, assembly loads will be basis dropped spent fuel design basis seismic events, and design performed. assembly loads and maintain basis dropped spent fuel assembly the calculated effective accidents over the spent fuel storage racks. neutron multiplication factor required by 10 CFR 50.68(1) limits.

Note:

1. The requirements of 10 CFR 50.68 are summarized as follows:
  • For new fuel storage racks:

- The effective neutron multiplication factor (K-effective) must not exceed 0.95 when flooded with unborated water and

- K-effective must not exceed 0.98 with optimum moderator conditions.

  • For spent fuel storage racks:

- If methodology does not take credit for soluble boron:

  • K-effective must not exceed 0.95 when flooded with unborated water.

- Or if methodology takes credit for soluble boron:

  • K-effective must not exceed 0.95 when flooded with borated water and
  • K-effective must remain below 1.0 when flooded with unborated water.

C-47 Amendment No. 112

Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 33 2.1.02.08d.ii 8.d) The RCS provides automatic ii) Inspections and associated ii) The calculated flow depressurization during design basis analysis of each fourth-stage resistance for each group of events. ADS valve group (four valves fourth-stage ADS valves and and associated piping piping with all valves open connected to each hot leg) is:

will be conducted to verify Loop 1:

the line routing is consistent Sub-loop A: < 5.91x10-7 ft/gpm2 with the line routing used for Sub-loop C: < 6.21x10-7 ft/gpm2 design flow resistance Loop 2:

calculations. Sub-loop B: < 4.65x10-7 ft/gpm2 Sub-loop D: < 6.20x10-7ft/gpm2 34 2.1.02.08d.iii 8.d) The RCS provides automatic iii) Inspections of each iii) The as-manufactured depressurization during design basis fourth-stage ADS valve will flow area through each events. be conducted to determine the fourth-stage ADS valve is >

as-manufactured flow area 67 in2.

through each valve.

35 2.1.02.08d.iv 8.d) The RCS provides automatic iv) Type tests and analysis iv) A report exists and depressurization during design basis will be performed to concludes that the effective events. determine the effective flow flow area through each stage area through each stage 1,2,3 1 ADS valve > 4.6 in2 and ADS valve. each stage 2,3 ADS valve is

> 19 in2.

36 2.1.02.08d.v 8.d) The RCS provides automatic v) Inspections of the v) The minimum elevation depressurization during design basis elevation of the ADS stage 4 of the bottom inside surface events. valve discharge will be of the outlet of these valves conducted. is greater than plant elevation 110 feet.

vi) Inspections of the ADS vi) The discharge of the stage 4 valve discharge will ADS stage 4 valves is be conducted. directed into the steam generator compartments.

viii) Inspection of the viii) The centerline of the elevation of each ADS connection of the sparger sparger will be conducted. arms to the sparger hub is

< 11.5 feet below the IRWST overflow level.

37 2.1.02.08d.vi Not used per Amendment No. 112 38 2.1.02.08d.vii 8.d) The RCS provides automatic vii) Inspection of each ADS vii) The flow area through depressurization during design basis sparger will be conducted to the holes in each ADS events. determine the flow area sparger is > 274 in2.

through the sparger holes.

C-64 Amendment No. 112

Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 39 2.1.02.08d.viii Not used per Amendment No. 112 40 2.1.02.08e 8.e) The RCS provides emergency letdown Inspections of the reactor A report exists and during design basis events. vessel head vent valves and concludes that the capacity inlet and outlet piping will be of the reactor vessel head conducted. vent is sufficient to pass not less than 8.2 lbm/sec at 1250 psia in the RCS.

C-64a Amendment No. 112

Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 41 2.1.02.09a 9.a) The RCS provides circulation of Testing and analysis to The calculated post-fuel coolant to remove heat from the core. measure RCS flow with four load RCS flow rate is reactor coolant pumps > 301,670 gpm.

operating at no-load RCS pressure and temperature conditions will be performed.

Analyses will be performed to convert the measured pre-fuel load flow to post-fuel load flow with 10-percent steam generator tube plugging.

42 2.1.02.09b.i 9.b) The RCS provides the means to i) Inspections will be i) Pressurizer heater backup control system pressure. performed to verify the rated groups A and B each has a capacity of pressurizer heater rated capacity of at least 168 backup groups A and B. kW.

43 2.1.02.09b.ii 9.b) The RCS provides the means to ii) Tests will be performed to ii) Controls in the MCR control system pressure. verify that the pressurizer operate to cause the spray valves can open and pressurizer spray valves to close when operated from the open and close.

MCR.

44 2.1.02.09c 9.c) The pressurizer heaters trip after a Testing will be performed to The pressurizer heaters signal is generated by the PMS. confirm trip of the pressurizer identified in Table 2.1.2-3 heaters identified in trip after a signal is Table 2.1.2-3. generated by the PMS.

45 2.1.02.10 Not used per Amendment No. 112 46 2.1.02.11a.i 11.a) Controls exist in the MCR to cause i) Testing will be performed i) Controls in the MCR the remotely operated valves identified in on the squib valves identified operate to cause a signal at Table 2.1.2-1 to perform active functions. in Table 2.1.2-1 using controls the squib valve electrical in the MCR without stroking leads which is capable of the valve. actuating the squib valve.

47 2.1.02.11a.ii 10. Safety-related displays identified in Inspection will be performed Safety-related displays Table 2.1.2-1 can be retrieved in the MCR. for retrievability of the safety- identified in Table 2.1.2-1 related displays in the MCR. can be retrieved in the MCR.

11.a) Controls exist in the MCR to cause ii) Stroke testing will be ii) Controls in the MCR the remotely operated valves identified in performed on the other operate to cause the Table 2.1.2-1 to perform active functions. remotely operated valves remotely operated valves listed in Table 2.1.2-1 using (other than squib valves) to controls in the MCR. perform active functions.

C-65 Amendment No. 112

Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 11.b) The valves identified in Table 2.1.2-1 ii) Testing will be performed ii) The other remotely as having PMS control perform an active on the other remotely operated valves identified in safety function after receiving a signal operated valves identified in Table 2.1.2-1 as having from the PMS. Table 2.1.2-1 using real or PMS control perform the simulated signals into the active function identified in PMS. the table after receiving a signal from PMS.

iii) Testing will be performed iii) These valves open to demonstrate that remotely within the following times operated RCS valves after receipt of an actuation RCS-V001A/B, V002A/B, signal:

V003A/B, V011A/B, V001A/B < 40 sec V012A/B, V013A/B open V002A/B, V003A/B <100 sec within the required response V011A/B < 30 sec times. V012A/B, V013A/B < 60 sec 12.b) After loss of motive power, the Testing of the remotely Upon loss of motive power, remotely operated valves identified in operated valves will be each remotely operated Table 2.1.2-1 assume the indicated loss of performed under the valve identified in Table motive power position. conditions of loss of motive 2.1.2-1 assumes the power. indicated loss of motive power position.

48 2.1.02.11b.i 11.b) The valves identified in Table 2.1.2-1 i) Testing will be performed i) The squib valves receive as having PMS control perform an active on the squib valves identified a signal at the valve safety function after receiving a signal in Table 2.1.2-1 using real or electrical leads that is from the PMS. simulated signals into the capable of actuating the PMS without stroking the squib valve.

valve.

C-65a Amendment No. 112

Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 49 2.1.02.11b.ii Not used per Amendment No. 112 50 2.1.02.11b.iii Not used per Amendment No. 112 51 2.1.02.11c.i 11.c) The valves identified in Table 2.1.2-1 i) Testing will be performed i) The squib valves receive as having DAS control perform an active on the squib valves identified a signal at the valve safety function after receiving a signal in Table 2.1.2-1 using real or electrical leads that is from DAS. simulated signals into the capable of actuating the DAS without stroking the squib valve.

valve.

52 2.1.02.11c.ii 11.c) The valves identified in Table 2.1.2-1 ii) Testing will be performed ii) The other remotely as having DAS control perform an active on the other remotely operated valves identified in safety function after receiving a signal operated valves identified in Table 2.1.2-1 as having from DAS. Table 2.1.2-1 using real or DAS control perform the simulated signals into the active function identified in DAS. the table after receiving a signal from DAS.

53 2.1.02.12a.i 12.a) The automatic depressurization i) Tests or type tests of i) A test report exists and valves identified in Table 2.1.2-1 perform motor-operated valves will be concludes that each motor-an active safety-related function to change performed that demonstrate operated valve changes position as indicated in the table. the capability of the valve to position as indicated in operate under its design Table 2.1.2-1 under design conditions. conditions.

ii) Inspection will be ii) A report exists and performed for the existence of concludes that the as-built a report verifying that the as- motor-operated valves are built motor-operated valves bounded by the tests or type are bounded by the tests or tests.

type tests.

54 2.1.02.12a.ii Not used per Amendment No. 84 C-66 Amendment No. 112

Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 55 2.1.02.12a.iii 12.a) The automatic depressurization iii) Tests of the motor- iii) Each motor-operated valves identified in Table 2.1.2-1 perform operated valves will be valve changes position as an active safety-related function to change performed under pre- indicated in Table 2.1.2-1 position as indicated in the table. operational flow, differential under pre-operational test pressure and temperature conditions.

conditions.

56 2.1.02.12a.iv 12.a) The automatic depressurization iv) Tests or type tests of squib iv) A test report exists and valves identified in Table 2.1.2-1 perform valves will be performed that concludes that each squib an active safety-related function to change demonstrate the capability of valve changes position as position as indicated in the table. the valve to operate under its indicated in Table 2.1.2-1 design conditions. under design conditions.

v) Inspection will be v) A report exists and performed for the existence of concludes that the as-built a report verifying that the as- squib valves are bounded by built squib valves are bounded the tests or type tests.

by the tests or type tests.

57 2.1.02.12a.v Not used per Amendment No. 84 58 2.1.02.12a.vi Not used per Amendment No. 84 59 2.1.02.12a.vii Not used per Amendment No. 84 60 2.1.02.12a.viii 12.a) The automatic depressurization viii) See item 8.d.iii in this viii) See item 8.d.iii in this valves identified in Table 2.1.2-1 perform table. table.

an active safety-related function to change position as indicated in the table.

61 2.1.02.12a.ix 12.a) The automatic depressurization ix) See item 8.d.iv in this ix) See item 8.d.iv in this valves identified in Table 2.1.2-1 perform table. table.

an active safety-related function to change position as indicated in the table.

62 2.1.02.12b Not used per Amendment No. 112 C-67 Amendment No. 112

Table 2.1.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 68 2.1.03.01 1. The functional arrangement of the RXS Inspection of the as-built The as-built RXS conforms is as described in the Design Description of system will be performed. with the functional this Section 2.1.3. arrangement as described in the Design Description of this Section 2.1.3.

69 2.1.03.02a 2.a) The reactor upper internals rod guide Inspection of the as-built The as-built RXS will arrangement is as shown in Figure 2.1.3-1. system will be performed. accommodate the fuel assembly and control rod drive mechanism pattern shown in Figure 2.1.3-1.

2.b) The control assemblies (rod cluster Inspection of the as-built The as-built RXS will and gray rod) and drive rod arrangement is system will be performed. accommodate the control as shown in Figure 2.1.3-2. assemblies (rod cluster and gray rod) and drive rod arrangement shown in Figure 2.1.3-2.

70 2.1.03.02b Not used per Amendment No. 112 71 2.1.03.02c 2.c) The reactor vessel arrangement is as Inspection of the as-built The as-built RXS will shown in Figure 2.1.3-3. system will be performed. accommodate the reactor vessel arrangement shown in Figure 2.1.3-3.

72 2.1.03.03 3. The components identified in Table Inspection will be conducted The ASME Code Section III 2.1.3-1 as ASME Code Section III are of the as-built components as design reports exist for the designed and constructed in accordance documented in the ASME as-built components with ASME Code Section III requirements. design reports. identified in Table 2.1.3-1 as ASME Code Section III.

4. Pressure boundary welds in components Inspection of as-built pressure A report exists and identified in Table 2.1.3-1 as ASME Code boundary welds will be concludes that the ASME Section III meet ASME Code Section III performed in accordance with Code Section III requirements. the ASME Code Section III. requirements are met for non-destructive examination of pressure boundary welds.
5. The pressure boundary components (RV, A hydrostatic test will be A report exists and CRDMs, and incore instrument QuickLoc performed on the components concludes that the results of assemblies) identified in Table 2.1.3-1 as of the RXS required by the the hydrostatic test of the ASME Code Section III retain their ASME Code Section III to be pressure boundary pressure boundary integrity at their design hydrostatically tested. components (RV, CRDMs, pressure. and incore instrument QuickLoc assemblies) conform with the requirements of the ASME Code Section III.

73 2.1.03.04 Not used per Amendment No. 84 74 2.1.03.05 Not used per Amendment No. 84 C-77 Amendment No. 112

Table 2.1.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 77 2.1.03.06.iii Not used per Amendment No. 84 78 2.1.03.07.i 7. The reactor internals will withstand the i) A vibration type test will be i) A report exists and effects of flow induced vibration. conducted on the (first unit) concludes that the (first unit) reactor internals reactor internals have no representative of AP1000. observable damage or loose parts as a result of the vibration type test.

ii) A pre-test inspection, a ii) The as-built reactor flow test and a post-test internals have no observable inspection will be conducted damage or loose parts.

on the as-built reactor internals.

10. The reactor lower internals assembly is Inspection of the reactor At least eight capsules are in equipped with holders for at least eight lower internals assembly for the reactor lower internals capsules for storing material surveillance the presence of capsules will assembly.

specimens. be performed.

79 2.1.03.07.ii Not used per Amendment No. 112 80 2.1.03.08 8. The reactor vessel direct vessel injection An inspection will be The throat area of the direct nozzle limits the blowdown of the RCS conducted to verify the flow vessel injection line nozzle following the break of a direct vessel area of the flow limiting flow limiting venturi is less injection line. venturi within each direct than or equal to 12.57 in2.

vessel injection nozzle.

81 2.1.03.09a.i Not used per Amendment No. 84 82 2.1.03.09a.ii Not used per Amendment No. 84 83 2.1.03.09b 9.b) The Class 1E components identified Testing will be performed by A simulated test signal in Table 2.1.3-1 are powered from their providing simulated test exists for Class 1E respective Class 1E division. signals in each Class 1E equipment identified in division. Table 2.1.3-1 when the assigned Class 1E division is provided the test signal.

84 2.1.03.09c Not used per Amendment No. 84 85 2.1.03.10 Not used per Amendment No. 112 86 2.1.03.11 11. The RPV beltline material has a Manufacturing tests of the A report exists and Charpy upper-shelf energy of no less than Charpy V-Notch specimen of concludes that the initial 75 ft-lb. the RPV beltline material will RPV beltline Charpy upper-be performed. shelf energy is no less than 75 ft-lb.

C-79 Amendment No. 112

Table 2.2.1-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 110 2.2.01.09 9. Safety-related displays identified in Inspection will be performed Safety-related displays Table 2.2.1-1 can be retrieved in the MCR. for retrievability of the safety- identified in Table 2.2.1-1 related displays in the MCR. can be retrieved in the MCR.

10.a) Controls exist in the MCR to cause Stroke testing will be Controls in the MCR those remotely operated valves identified performed on remotely operate to cause remotely in Table 2.2.1-1 to perform active operated valves identified in operated valves identified in functions. Table 2.2.1-1 using the Table 2.2.1-1 to perform controls in the MCR. active safety functions.

10.b) The valves identified in Table 2.2.1-1 Testing will be performed on The remotely operated as having PMS control perform an active remotely operated valves valves identified in Table safety function after receiving a signal listed in Table 2.2.1-1 using 2.2.1-1 as having PMS from the PMS. real or simulated signals into control perform the active the PMS. function identified in the table after receiving a signal from PMS.

111 2.2.01.10a Not used per Amendment No. 112 112 2.2.01.10b Not used per Amendment No. 112 113 2.2.01.10c 10.c) The valves identified in Table 2.2.1-1 Testing will be performed on The remotely operated as having DAS control perform an active remotely operated valves valves identified in safety function after receiving a signal listed in Table 2.2.1-1 using Table 2.2.1-1 as having from DAS. real or simulated signals into DAS control perform the the DAS. active function identified in the table after receiving a signal from DAS.

114 2.2.01.11a.i 11.a) The motor-operated and check valves i) Tests or type tests of i) A test report exists and identified in Table 2.2.1-1 perform an motor-operated valves will be concludes that each motor-active safety-related function to change performed to demonstrate the operated valve changes position as indicated in the table. capability of each valve to position as indicated in operate under design Table 2.2.1-1 under design conditions. conditions.

ii) Inspection will be ii) A report exists and performed for the existence of concludes that the as-built a report verifying that the motor-operated valves are as-built motor-operated valves bounded by the tests or type are bounded by the tests or tests.

type tests.

C-99 Amendment No. 112

Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 133 2.2.02.06b 6.b) The Class 1E components Testing will be performed by A simulated test signal exists at identified in Table 2.2.2-1 are providing a simulated test signal the Class 1E components powered from their respective in each Class 1E division. identified in Table 2.2.2-1 when Class 1E division. the assigned Class 1E division is provided the test signal.

134 2.2.02.06c Not used per Amendment No. 84 135 2.2.02.07a.i Not used per Amendment No. 112 136 2.2.02.07a.ii Not used per Amendment No. 112 137 2.2.02.07a.iii 7.a) The PCS delivers water from iii) Inspection will be performed iii) The elevations of the the PCCWST to the outside, top to determine the PCCWST standpipes above the tank floor of the containment vessel. standpipes elevations. are:

- 16.8 ft +/- 0.2 ft

- 20.3 ft +/- 0.2 ft

- 24.1 ft +/- 0.2 ft 7.f) The PCS provides a flow path ii) Inspection of the PCCWST ii) The volume of the PCCWST is for long-term water makeup from will be performed. greater than 756,700 gallons.

the PCCWST to the spent fuel pool.

8.a) The PCCAWST contains an Inspection of the PCCAWST will The volume of the PCCAWST is inventory of cooling water be performed. greater than 780,000 gallons.

sufficient for PCS containment cooling from hour 72 through day 7.

C-110 Amendment No. 112

Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 138 2.2.02.07b.i 7.a) The PCS delivers water from i) Testing will be performed to i) When tested, each one of the the PCCWST to the outside, top measure the PCCWST delivery three flow paths delivers water at of the containment vessel. rate from each one of the three greater than or equal to:

parallel flow paths. - 469.1 gpm at a PCCWST water level of 27.4 ft + 0.2, - 0.0 ft above the tank floor

- 226.6 gpm when the PCCWST water level uncovers the first (i.e. tallest) standpipe

- 176.3 gpm when the PCCWST water level uncovers the second tallest standpipe

- 144.2 gpm when the PCCWST water level uncovers the third tallest standpipe ii) Testing and or analysis will be ii) When tested and/or analyzed performed to demonstrate the with all flow paths delivering and PCCWST inventory provides an initial water level at 27.4 + 0.2, 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> of adequate water flow. - 0.00 ft, the PCCWST water inventory provides greater than or equal to 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> of flow, and the flow rate at 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> is greater than or equal to 100.7 gpm.

7.b) The PCS wets the outside i) Testing will be performed to i) A report exists and concludes surface of the containment vessel. measure the outside wetted that when the water in the The inside and the outside of the surface of the containment vessel PCCWST uncovers the standpipes containment vessel above the with one of the three parallel flow at the following levels, the water operating deck are coated with an paths delivering water to the top delivered by one of the three inorganic zinc material. of the containment vessel. parallel flow paths to the containment shell provides coverage measured at the spring line that is equal to or greater than the stated coverages.

- 24.1 +/- 0.2 ft above the tank floor; at least 90% of the perimeter is wetted.

- 20.3 +/- 0.2 ft above the tank floor; at least 72.9% of the perimeter is wetted.

- 16.8 +/- 0.2 ft above the tank floor; at least 59.6% of the perimeter is wetted.

ii) Inspection of the containment ii) A report exists and concludes vessel exterior coating will be that the containment vessel conducted. exterior surface is coated with an inorganic zinc coating above elevation 135'-3".

C-111 Amendment No. 112

Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria iii) Inspection of the containment iii) A report exists and concludes vessel interior coating will be that the containment vessel conducted. interior surface is coated with an inorganic zinc coating above 7' above the operating deck.

7.c) The PCS provides air flow Inspections of the air flow path Flow paths exist at each of the over the outside of the segments will be performed. following locations:

containment vessel by a natural - Air inlets circulation air flow path from the - Base of the outer annulus air inlets to the air discharge - Base of the inner annulus structure. - Discharge structure 7.d) The PCS drains the excess Testing will be performed to With a water level within the water from the outside of the verify the upper annulus drain upper annulus 10" + 1" above the containment vessel through the flow performance. annulus drain inlet, the flow rate two upper annulus drains. through each drain is greater than or equal to 525 gpm.

7.e) The PCS provides a flow path ii) Testing will be performed to ii) With a water supply connected for long-term water makeup to the measure the delivery rate from the to the PCS long-term makeup PCCWST. long-term makeup connection to connection, each PCS the PCCWST. recirculation pump delivers greater than or equal to 100 gpm when tested separately.

9. Safety-related displays Inspection will be performed for Safety-related displays identified identified in Table 2.2.2-1 can be retrievability of the safety-related in Table 2.2.2-1 can be retrieved retrieved in the MCR. displays in the MCR. in the MCR.

10.a) Controls exist in the MCR Stroke testing will be performed Controls in the MCR operate to to cause the remotely operated on the remotely operated valves cause remotely operated valves valves identified in Table 2.2.2-1 identified in Table 2.2.2-1 using identified in Table 2.2.2-1 to to perform active functions. the controls in the MCR. perform active functions.

10.b) The valves identified in Testing will be performed on the The remotely operated valves Table 2.2.2-1 as having PMS remotely operated valves in Table identified in Table 2.2.2-1 as control perform an active safety 2.2.2-1 using real or simulated having PMS control perform the function after receiving a signal signals into the PMS. active function identified in the from the PMS. table after receiving a signal from the PMS.

11.a) The motor-operated valves iii) Tests of the motor-operated iii) Each motor-operated valve identified in Table 2.2.2-1 valves will be performed under changes position as indicated in perform an active safety-related preoperational flow, differential Table 2.2.2-1 under function to change position as pressure, and temperature preoperational test conditions.

indicated in the table. conditions.

11.b) After loss of motive power, Testing of the remotely operated After loss of motive power, each the remotely operated valves valves will be performed under remotely operated valve identified identified in Table 2.2.2-1 assume the conditions of loss of motive in Table 2.2.2-1 assumes the the indicated loss of motive power power. indicated loss of motive power position. position.

C-111a Amendment No. 112

Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 139 2.2.02.07b.ii Not used per Amendment No. 112 140 2.2.02.07b.iii Not used per Amendment No. 112 141 2.2.02.07c Not used per Amendment No. 112 142 2.2.02.07d Not used per Amendment No. 112 C-111b Amendment No. 112

Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 143 2.2.02.07e.i Not used per Amendment No. 84 144 2.2.02.07e.ii Not used per Amendment No. 112 145 2.2.02.07f.i 7.f) The PCS provides a flow i) Testing will be performed to i) With the PCCWST water level path for long-term water makeup measure the delivery rate from the at 27.4 ft + 0.2, - 0.0 ft above the from the PCCWST to the spent PCCWST to the spent fuel pool. bottom of the tank, the flow path fuel pool. from the PCCWST to the spent fuel pool delivers greater than or equal to 118 gpm.

8.b) The PCS delivers water from Testing will be performed to With PCCAWST aligned to the the PCCAWST to the PCCWST measure the delivery rate from the suction of the recirculation and spent fuel pool PCCAWST to the PCCWST and pumps, each pump delivers simultaneously. spent fuel pool simultaneously. greater than or equal to 100 gpm to the PCCWST and 35 gpm to the spent fuel pool simultaneously when each pump is tested separately.

146 2.2.02.07f.ii Not used per Amendment No. 112 147 2.2.02.08a Not used per Amendment No. 112 148 2.2.02.08b Not used per Amendment No. 112 149 2.2.02.08c Not used per Amendment No. 84 150 2.2.02.09 Not used per Amendment No. 112 151 2.2.02.10a Not used per Amendment No. 112 C-112 Amendment No. 112

Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 152 2.2.02.10b Not used per Amendment No. 112 153 2.2.02.10c 10.c) The valves identified in Testing will be performed on the The remotely operated valves Table 2.2.2-1 as having DAS remotely operated valves listed in identified in Table 2.2.2-1 as control perform an active safety Table 2.2.2-1 using real or having DAS control perform the function after receiving a signal simulated signals into the DAS. active function identified in the from the DAS. table after receiving a signal from the DAS.

154 2.2.02.11a.i 11.a) The motor-operated valves i) Tests or type tests of motor- i) A test report exists and identified in Table 2.2.2-1 operated valves will be performed concludes that each motor-perform an active safety-related to demonstrate the capability of operated valve changes position function to change position as the valve to operate under its as indicated in Table 2.2.2-1 indicated in the table. design conditions. under design conditions.

ii) Inspection will be performed ii) A report exists and concludes for the existence of a report that the capability of the as-built verifying that the capability of the motor-operated valves bound the as-built motor-operated valves tested conditions.

bound the tested conditions.

155 2.2.02.11a.ii Not used per Amendment No. 84 156 2.2.02.11a.iii Not used per Amendment No. 112 157 2.2.02.11b Not used per Amendment No. 112 Table 2.2.2-4 Component Name Tag No. Component Location PCCWST PCS-MT-01 Shield Building PCCAWST PCS-MT-05 Yard Recirculation Pump A PCS-MP-01A Auxiliary Building Recirculation Pump B PCS-MP-01B Auxiliary Building C-113 Amendment No. 112

Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 180 2.2.03.08c.i.04 8.c) The PXS provides RCS makeup, i) A low-pressure injection test i) The injection line flow boration, and safety injection during and analysis for each CMT, each resistance from each source is design basis events. accumulator, each IRWST as follows:

injection line, and each 4. Containment Recirculation:

containment recirculation line The calculated flow resistance will be conducted. Each test is for each containment initiated by opening isolation recirculation line between the valve(s) in the line being tested. containment and the reactor Test fixtures may be used to vessel is:

simulate squib valves. Line A: 1.33 x 10-5 ft/gpm2

4. Containment Recirculation: and A temporary water supply will Line B: 1.21 x 10-5 ft/gpm2.

be connected to the recirculation lines. All valves in these lines will be open during the test.

Sufficient flow will be provided to open the check valves.

181 2.2.03.08c.ii 8.c) The PXS provides RCS makeup, ii) A low-pressure test and ii) The flow resistance from boration, and safety injection during analysis will be conducted for the cold leg to the CMT is design basis events. each CMT to determine piping 7.21 x 10-6 ft/gpm2.

flow resistance from the cold leg to the CMT. The test will be performed by filling the CMT via the cold leg balance line by operating the normal residual heat removal pumps.

182 2.2.03.08c.iii 8.c) The PXS provides RCS makeup, iii) Inspections of the routing of iii) These lines have no boration, and safety injection during the following pipe lines will be downward sloping sections design basis events. conducted: between the connection to the

- CMT inlet line, cold leg to RCS and the high point of the high point line.

- PRHR HX inlet line, hot leg to high point C-133 Amendment No. 112

Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 183 2.2.03.08c.iv.01 8.c) The PXS provides RCS makeup, iv) Inspections of the elevation iv) The maximum elevation boration, and safety injection during of the following pipe lines will of the top inside surface of design basis events. be conducted: these lines is less than the elevation of:

1. IRWST injection lines; 1. IRWST bottom inside IRWST connection to DVI surface nozzles v) Inspections of the elevation of v) The elevation of the bottom the following tanks will be inside tank surface is higher conducted: than the direct vessel injection nozzle centerline by the following:
2. IRWST 2. IRWST 3.4 ft 184 2.2.03.08c.iv.02 8.c) The PXS provides RCS makeup, iv) Inspections of the elevation iv) The maximum elevation boration, and safety injection during of the following pipe lines will of the top inside surface of design basis events. be conducted: these lines is less than the
2. Containment recirculation elevation of:

lines; containment to IRWST 2. IRWST bottom inside lines surface C-133a Amendment No. 112

Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 185 2.2.03.08c.iv.03 8.c) The PXS provides RCS makeup, iv) Inspections of the elevation iv) The maximum elevation boration, and safety injection during of the following pipe lines will of the top inside surface of design basis events. be conducted: these lines is less than the

3. CMT discharge lines to DVI elevation of:

connection 3. CMT bottom inside surface 186 2.2.03.08c.iv.04 8.c) The PXS provides RCS makeup, iv) Inspections of the elevation iv) The maximum elevation boration, and safety injection during of the following pipe lines will of the top inside surface of design basis events. be conducted: these lines is less than the

4. PRHR HX outlet line to SG elevation of:

connection 4. PRHR HX lower channel head top inside surface 187 2.2.03.08c.v.01 8.c) The PXS provides RCS makeup, v) Inspections of the elevation v) The elevation of the boration, and safety injection during of the following tanks will be bottom inside tank surface is design basis events. conducted: higher than the direct vessel

1. CMTs injection nozzle centerline by the following:
1. CMTs 7.5 ft 188 2.2.03.08c.v.02 Not used per Amendment No. 112 189 2.2.03.08c.vi.01 8.c) The PXS provides RCS makeup, vi) Inspections of each of the vi) The calculated volume of boration, and safety injection during following tanks will be each of the following tanks is design basis events. conducted: as follows:
1. CMTs 1. CMTs 2487 ft3 190 2.2.03.08c.vi.02 8.c) The PXS provides RCS makeup, vi) Inspections of each of the vi) The calculated volume of boration, and safety injection during following tanks will be each of the following tanks is design basis events. conducted: as follows:
2. Accumulators 2. Accumulators 2000 ft3 191 2.2.03.08c.vi.03 8.c) The PXS provides RCS makeup, vi) Inspections of each of the vi) The calculated volume of boration, and safety injection during following tanks will be each of the following tanks is design basis events. conducted: as follows:

3.- IRWST 3. IRWST > 73,100 ft3 between the tank outlet connection and the tank overflow C-134 Amendment No. 112

Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 202 2.2.03.09a.ii 9.a) The PXS provides a function to ii) Inspections of the as-built ii) The combined total flow cool the outside of the reactor vessel reactor vessel insulation will be area of the water inlets is not during a severe accident. performed. less than 6 ft2. The combined total flow area of the steam outlet(s) is not less than 12 ft2.

A report exists and concludes that the minimum flow area between the vessel insulation and reactor vessel for the flow path that vents steam is not less than 12 ft2 considering the maximum deflection of the vessel insulation with a static pressure of 12.95 ft of water.

203 2.2.03.09a.iii 9.a) The PXS provides a function to iii) Inspections will be iii) A flow path with a flow cool the outside of the reactor vessel conducted of the flow path(s) area not less than 6 ft 2 exists during a severe accident. from the loop compartments to from the loop compartment to the reactor vessel cavity. the reactor vessel cavity.

204 2.2.03.09b 9.b) The accumulator discharge check An inspection of the accumulator The accumulator discharge valves (PXS-PL-V028A/B and and CMT discharge check valves check valves are of a different V029A/B) are of a different check is performed. check valve type than the valve type than the CMT discharge CMT discharge check valves.

check valves (PXS-PL-V016A/B and V017A/B).

205 2.2.03.09c 9.c) The equipment listed in Type tests, analyses, or a A report exists and concludes Table 2.2.3-6 has sufficient thermal lag combination of type tests and that the thermal lag of this to withstand the effects of identified analyses will be performed to equipment is greater than the hydrogen burns associated with severe determine the thermal lag of this value required.

accidents. equipment.

C-139 Amendment No. 112

Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 206 2.2.03.10 10. Safety-related displays of the Inspection will be performed for Safety-related displays parameters identified in Table 2.2.3-1 the retrievability of the safety- identified in Table 2.2.3-1 can can be retrieved in the MCR. related displays in the MCR. be retrieved in the MCR.

11.a) Controls exist in the MCR to ii) Stroke testing will be ii) Controls in the MCR cause the remotely operated valves performed on remotely operated operate to cause remotely identified in Table 2.2.3-1 to perform valves other than squib valves operated valves other than their active function(s). identified in Table 2.2.3-1 using squib valves to perform their the controls in the MCR. active functions.

11.b) The valves identified in Table ii) Testing will be performed on ii) Remotely operated valves 2.2.3-1 as having PMS control perform the remotely operated valves other than squib valves their active function after receiving a other than squib valves identified perform the active function signal from the PMS. in Table 2.2.3-1 using real or identified in the table after a simulated signals into the PMS. signal is input to the PMS.

iii) Testing will be performed to iii) These valves open within demonstrate that remotely 20 seconds after receipt of an operated PXS isolation valves actuation signal.

PXS-V014A/B, V015A/B, V108A/B open within the required response times.

12.b) After loss of motive power, the Testing of the remotely operated After loss of motive power, remotely operated valves identified in valves will be performed under each remotely operated valve Table 2.2.3-1 assume the indicated the conditions of loss of motive identified in Table 2.2.3-1 loss of motive power position. power. assumes the indicated loss of motive power position.

13. Displays of the parameters Inspection will be performed for Displays identified in Table identified in Table 2.2.3-3 can be retrievability of the displays 2.2.3-3 can be retrieved in the retrieved in the MCR. identified in Table 2.2.3-3 in the MCR.

MCR.

207 2.2.03.11a.i 11.a) Controls exist in the MCR to i) Testing will be performed on i) Controls in the MCR cause the remotely operated valves the squib valves identified in operate to cause a signal at the identified in Table 2.2.3-1 to perform Table 2.2.3-1 using controls in squib valve electrical leads their active function(s). the MCR, without stroking the that is capable of actuating the valve. squib valve.

208 2.2.03.11a.ii Not used per Amendment No. 112 C-139a Amendment No. 112

Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 209 2.2.03.11b.i 11.b) The valves identified in i) Testing will be performed on i) Squib valves receive an Table 2.2.3-1 as having PMS control the squib valves identified in electrical signal at the valve perform their active function after Table 2.2.3-1 using real or electrical leads that is capable receiving a signal from the PMS. simulated signals into the PMS of actuating the valve after a without stroking the valve. signal is input to the PMS.

210 2.2.03.11b.ii Not used per Amendment No. 112 211 2.2.03.11b.iii Not used per Amendment No. 112 212 2.2.03.11c.i 11.c) The valves identified in i) Testing will be performed on i) Squib valves receive an Table 2.2.3-1 as having DAS control the squib valves identified in electrical signal at the valve perform their active function after Table 2.2.3-1 using real or electrical leads that is capable receiving a signal from the DAS. simulated signals into the DAS of actuating the valve after a without stroking the valve. signal is input to the DAS.

213 2.2.03.11c.ii 11.c) The valves identified in ii) Testing will be performed on ii) Remotely operated valves Table 2.2.3-1 as having DAS control the remotely operated valves other than squib valves perform their active function after other than squib valves identified perform the active function receiving a signal from the DAS. in Table 2.2.3-1 using real or identified in Table 2.2.3-1 simulated signals into the DAS. after a signal is input to the DAS.

214 2.2.03.12a.i 12.a) The squib valves and check i) Tests or type tests of squib i) A test report exists and valves identified in Table 2.2.3-1 valves will be performed that concludes that each squib perform an active safety-related demonstrate the capability of the valve changes position as function to change position as valve to operate under its design indicated in Table 2.2.3-1 indicated in the table. condition. under design conditions.

ii) Inspection will be performed ii) A report exists and for the existence of a report concludes that the as-built verifying that the as-built squib squib valves are bounded by valves are bounded by the tests the tests or type tests.

or type tests.

215 2.2.03.12a.ii Not used per Amendment No. 84 C-140 Amendment No. 112

Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 216 2.2.03.12a.iv 12.a) The squib valves and check iv) Exercise testing of the check iv) Each check valve changes valves identified in Table 2.2.3-1 valves with active safety position as indicated in perform an active safety-related functions identified in Table 2.2.3-1 function to change position as Table 2.2.3-1 will be performed indicated in the table. under preoperational test pressure, temperature, and fluid flow conditions.

217 2.2.03.12b Not used per Amendment No. 112 218 2.2.03.13 Not used per Amendment No. 112 Table 2.2.3-5 Component Name Tag No. Component Location Passive Residual Heat Removal Heat PXS-ME-01 Containment Building Exchanger (PRHR HX)

Accumulator Tank A PXS-MT-01A Containment Building Accumulator Tank B PXS-MT-01B Containment Building Core Makeup Tank (CMT) A PXS-MT-02A Containment Building CMT B PXS-MT-02B Containment Building IRWST PXS-MT-03 Containment Building IRWST Screen A PXS-MY-Y01A Containment Building IRWST Screen B PXS-MY-Y01B Containment Building IRWST Screen C PXS-MY-Y01C Containment Building Containment Recirculation Screen A PXS-MY-Y02A Containment Building Containment Recirculation Screen B PXS-MY-Y02B Containment Building pH Adjustment Basket 3A PXS-MY-Y03A Containment Building pH Adjustment Basket 3B PXS-MY-Y03B Containment Building pH Adjustment Basket 4A PXS-MY-Y04A Containment Building pH Adjustment Basket 4B PXS-MY-Y04B Containment Building C-141 Amendment No. 112

Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 237 2.2.04.08b.i Not used per Amendment No. 84 238 2.2.04.08b.ii 8.b) During design basis events, the ii) Inspection will be performed ii) A report exists to indicate SGS limits steam generator blowdown for the existence of a report the installed flow limiting and feedwater flow to the steam confirming that the area of the orifice within the SG main generator. flow limiting orifice within the steam line discharge nozzle SG main steam outlet nozzle will does not exceed 1.4 sq. ft.

limit releases to the containment.

239 2.2.04.08c Not used per Amendment No. 84 240 2.2.04.09a.i Not used per Amendment No. 112 241 2.2.04.09a.ii 9.a) Components within the main ii) Testing will be performed to ii) The pumps identified in steam system, main and startup confirm the trip of the pumps Table 2.2.4-3 trip after a signal feedwater system, and the main turbine identified in Table 2.2.4-3. is generated by the PMS.

system identified in Table 2.2.4-3 provide backup isolation of the SGS to limit steam generator blowdown and feedwater flow to the steam generator.

242 2.2.04.09b.i Not used per Amendment No. 84 243 2.2.04.09b.ii 9.b) During shutdown operations, the ii) Type tests and/or analyses ii) A report exists and SGS removes decay heat by delivery of will be performed to demonstrate concludes that each power-startup feedwater to the steam generator the ability of the power-operated operated relief valve will and venting of steam from the steam relief valves to discharge steam relieve greater than 300,000 generators to the atmosphere. from the steam generators to the lb/hr at 1106 psia +/-10 psi.

atmosphere.

244 2.2.04.10 Not used per Amendment No. 112 C-161 Amendment No. 112

Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 245 2.2.04.11a Not used per Amendment No. 112 246 2.2.04.11b.i Not used per Amendment No. 112 247 2.2.04.11b.ii Not used per Amendment No. 112 248 2.2.04.12a.i 12.a) The motor-operated valves i) Tests or type tests of motor- i) A test report exists and identified in Table 2.2.4-1 perform an operated valves will be concludes that each motor-active safety-related function to change performed to demonstrate the operated valve changes position as indicated in the table. capability of the valve to operate position as indicated in Table under its design conditions. 2.2.4-1 under design conditions.

ii) Inspection will be performed ii) A report exists and for the existence of a report concludes that the as-built verifying that the as-built motor-operated valves are motor-operated valves are bounded by the tests or type bounded by the tests or type tests.

tests.

249 2.2.04.12a.ii Not used per Amendment No. 84 250 2.2.04.12a.iii 9.a) Components within the main steam i) Testing will be performed to i) The valves identified in system, main and startup feedwater confirm closure of the valves Table 2.2.4-3 close after a system, and the main turbine system identified in Table 2.2.4-3. signal is generated by the identified in Table 2.2.4-3 provide PMS.

backup isolation of the SGS to limit steam generator blowdown and feedwater flow to the steam generator.

10. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.2.4-1 can be retrieved in the retrievability of the safety- identified in Table 2.2.4-1 can MCR. related displays in the MCR. be retrieved in the MCR.

11.a) Controls exist in the MCR to Stroke testing will be performed Controls in the MCR operate cause the remotely operated valves on the remotely operated valves to cause the remotely operated identified in Table 2.2.4-1 to perform listed in Table 2.2.4-1 using valves to perform active safety active functions. controls in the MCR. functions.

11.b) The valves identified in Table i) Testing will be performed on i) The remotely-operated 2.2.4-1 as having PMS control perform the remotely operated valves valves identified in Table an active safety function after receiving listed in Table 2.2.4-1 using real 2.2.4-1 as having PMS control a signal from PMS. or simulated signals into the perform the active function PMS. identified in the table after receiving a signal from the PMS.

ii) Testing will be performed to ii) These valves close within demonstrate that remotely the following times after operated SGS isolation valves receipt of an actuation signal:

SGS-V027A/B, V040A/B, V027A/B < 44 sec V057A/B, V250A/B close V040A/B, V057A/B < 5 sec within the required response V250A/B < 5 sec times.

C-162 Amendment No. 112

Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 12.a) The motor-operated valves iii) Tests of the motor-operated iii) Each motor-operated valve identified in Table 2.2.4-1 perform an valves will be performed under changes position as indicated active safety-related function to change pre-operational flow, differential in Table 2.2.4-1 under pre-position as indicated in the table. pressure, and temperature operational test conditions.

conditions.

12.b) After loss of motive power, the Testing of the remotely operated After loss of motive power, remotely operated valves identified in valves will be performed under each remotely operated valve Table 2.2.4-1 assume the indicated loss the conditions of loss of motive identified in Table 2.2.4-1 of motive power position. power. assumes the indicated loss of motive power position.

Motive power to SGS-PL-V040A/B and SGS-PL-V057A/B is electric power to the actuator from plant services.

C-162a Amendment No. 112

Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 251 2.2.04.12b Not used per Amendment No. 112 Table 2.2.4-5 Component Name Tag No. Component Location Main Steam Line Isolation Valve SGS-PL-V040A Auxiliary Building Main Steam Line Isolation Valve SGS-PL-V040B Auxiliary Building Main Feedwater Isolation Valve SGS-PL-V057A Auxiliary Building Main Feedwater Isolation Valve SGS-PL-V057B Auxiliary Building Main Feedwater Control Valve SGS-PL-V250A Auxiliary Building Main Feedwater Control Valve SGS-PL-V250B Auxiliary Building Turbine Stop Valves MTS-PL-V001A Turbine Building MTS-PL-V001B MTS-PL-V003A MTS-PL-V003B Turbine Control Valves MTS-PL-V002A Turbine Building MTS-PL-V002B MTS-PL-V004A MTS-PL-V004B Main Feedwater Pumps FWS-MP-02A Turbine Building FWS-MP-02B FWS-MP-02C Feedwater Booster Pumps FWS-MP-01A Turbine Building FWS-MP-01B FWS-MP-01C C-163 Amendment No. 112

Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 259 2.2.05.05a.i 5.a) The seismic Category I equipment i) Inspection will be performed i) The seismic Category I identified in Table 2.2.5-1 can withstand to verify that the seismic equipment identified in seismic design basis loads without loss Category I equipment and valves Table 2.2.5-1 is located on the of safety function. identified in Table 2.2.5-1 are 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.

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.

260 2.2.05.05a.ii Not used per Amendment No. 84 261 2.2.05.05a.iii Not used per Amendment No. 84 262 2.2.05.05b Not used per Amendment No. 84 263 2.2.05.06a 6.a) The Class 1E components Testing will be performed by A simulated test signal exists identified in Table 2.2.5-1 are powered providing a simulated test signal at the Class 1E equipment from their respective Class 1E division. in each Class 1E division. identified in Table 2.2.5-1 when the assigned Class 1E division is provided the test signal.

264 2.2.05.06b Not used per Amendment No. 84 265 2.2.05.07a.i 7.a) The VES provides a 72-hour i) Testing will be performed to i) The air flow rate from the supply of breathable quality air for the confirm that the required amount VES is at least 60 scfm and occupants of the MCR. of air flow is delivered to the not more than 70 scfm.

MCR.

iii) MCR air samples will be iii) The MCR air is of taken during VES testing and breathable quality.

analyzed for quality.

7.b) The VES maintains the MCR i) Testing will be performed with i) The MCR pressure pressure boundary at a positive pressure VES flow rate between 60 and boundary is pressurized to with respect to the surrounding areas. 70 scfm to confirm that the MCR greater than or equal to 1/8-in.

is capable of maintaining the water gauge with respect to required pressurization of the the surrounding area.

pressure boundary.

C-177 Amendment No. 112

Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria ii) Air leakage into the MCR will ii) Air leakage into the MCR be measured during VES testing is less than or equal to 10 cfm.

using a tracer gas.

7.d) The system provides a passive Testing will be performed to The air flow rate at the outlet recirculation flow of MCR air to confirm that the required amount of the MCR passive filtration maintain main control room dose rates of air flow circulates through the system is at least 600 cfm below an acceptable level during VES MCR passive filtration system. greater than the flow operation. measured by VES-003A/B.

8. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.2.5-1 can be retrieved in the retrievability of the safety- identified in Table 2.2.5-1 can MCR. related displays in the MCR. be retrieved in the MCR.

9.a) Controls exist in the MCR to cause Stroke testing will be performed Controls in the MCR operate remotely operated valves identified in on remotely operated valves to cause remotely operated Table 2.2.5-1 to perform their active identified in Table 2.2.5-1 using valves identified in Table functions. the controls in the MCR. 2.2.5-1 to perform their active safety functions.

9.b) The valves identified in Table Testing will be performed on The remotely operated valves 2.2.5-1 as having PMS control perform remotely operated valves listed identified in Table 2.2.5-1 as their active safety function after in Table 2.2.5-1 using real or having PMS control perform receiving a signal from the PMS. simulated signals into the PMS. the active safety function identified in the table after receiving a signal from the PMS.

10. After loss of motive power, the Testing of the remotely operated After loss of motive power, remotely operated valves identified in valves will be performed under each remotely operated valve Table 2.2.5-1 assume the indicated loss the conditions of loss of motive identified in Table 2.2.5-1 of motive power position. power. assumes the indicated loss of motive power position.
11. Displays of the parameters Inspection will be performed for The displays identified in identified in Table 2.2.5-3 can be retrievability of the parameters Table 2.2.5-3 can be retrieved retrieved in the MCR. in the MCR. in the MCR.
12. The background noise level in the The as-built VES will be The background noise level in MCR does not exceed 65 dB(A) at the operated, and background noise the MCR does not exceed 65 operator workstations when VES is levels in the MCR will be dB(A) at the operator work operating. measured at the operator work stations when the VES is stations with the plant not operating.

operating.

C-177a Amendment No. 112

Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 266 2.2.05.07a.ii 7.a) The VES provides a 72-hour ii) Analysis of storage capacity ii) The calculated storage supply of breathable quality air for the will be performed based on capacity is greater than or occupants of the MCR. manufacturers data. equal to 327,574 scf.

267 2.2.05.07a.iii Not used per Amendment No. 112 268 2.2.05.07b.i Not used per Amendment No. 112 269 2.2.05.07b.ii Not used per Amendment No. 112 C-177b Amendment No. 112

Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 270 2.2.05.07c 7.c) The heat loads within the MCR, An analysis will be performed to A report exists and concludes the I&C equipment rooms, and the determine that the heat loads that: the heat loads within Class 1E dc equipment rooms are from as-built equipment within rooms identified in Table within design basis assumptions to limit the rooms identified in 2.2.5-4 are less than or equal the heatup of the rooms identified in Table 2.2.5-4 are less than or to the specified values or that Table 2.2.5-4. equal to the design basis an analysis report exists that assumptions. concludes:

- The temperature and humidity in the MCR remain within limits for reliable human performance for the 72-hour period.

- The maximum temperature for the 72-hour period for the I&C rooms is less than or equal to 120°F.

- The maximum temperature for the 72-hour period for the Class 1E dc equipment rooms is less than or equal to 120°F.

271 2.2.05.07d Not used per Amendment No. 112 272 2.2.05.08 Not used per Amendment No. 112 273 2.2.05.09a Not used per Amendment No. 112 274 2.2.05.09b Not used per Amendment No. 112 877 2.2.05.09c 9.c) The MCR Load Shed Panels Testing will be performed on the The MCR Load Shed Panels identified in Table 2.2.5-1 perform their MCR Load Shed Panels listed in identified in Table 2.2.5-1 active safety function after receiving a Table 2.2.5-1 using real or perform their active safety signal from the PMS. simulated signals into the PMS. function identified in the table after receiving a signal from the PMS.

C-178 Amendment No. 112

Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 275 2.2.05.10 Not used per Amendment No. 112 276 2.2.05.11 Not used per Amendment No. 112 277 2.2.05.12 Not used per Amendment No. 112 Table 2.2.5-6 Component Name Tag Number Component Location Emergency Air Storage Tank 01 VES-MT-01 Auxiliary Building Emergency Air Storage Tank 02 VES-MT-02 Auxiliary Building Emergency Air Storage Tank 03 VES-MT-03 Auxiliary Building Emergency Air Storage Tank 04 VES-MT-04 Auxiliary Building Emergency Air Storage Tank 05 VES-MT-05 Auxiliary Building Emergency Air Storage Tank 06 VES-MT-06 Auxiliary Building Emergency Air Storage Tank 07 VES-MT-07 Auxiliary Building Emergency Air Storage Tank 08 VES-MT-08 Auxiliary Building Emergency Air Storage Tank 09 VES-MT-09 Auxiliary Building Emergency Air Storage Tank 10 VES-MT-10 Auxiliary Building Emergency Air Storage Tank 11 VES-MT-11 Auxiliary Building Emergency Air Storage Tank 12 VES-MT-12 Auxiliary Building Emergency Air Storage Tank 13 VES-MT-13 Auxiliary Building Emergency Air Storage Tank 14 VES-MT-14 Auxiliary Building Emergency Air Storage Tank 15 VES-MT-15 Auxiliary Building Emergency Air Storage Tank 16 VES-MT-16 Auxiliary Building C-179 Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built CCS conforms CCS is as described in the Design will be performed. with the functional Description of this Section 2.3.1. arrangement described in the Design Description of this Section 2.3.1.

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. 112

Table 2.3.1-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 281 2.3.01.03.ii 3. The CCS provides the nonsafety- ii) Testing will be performed to ii) Each pump of the CCS can related functions of transferring heat confirm that the CCS can provide at least 2685 gpm of from the RNS during shutdown and the provide cooling water to the cooling water to one RNS HX spent fuel pool cooling system during RNS HXs while providing and at least 1200 gpm of all modes of operation to the SWS. cooling water to the SFS HXs. cooling water to one SFS HX while providing at least 4415 gpm to other users of cooling water.

4. Controls exist in the MCR to cause Testing will be performed to Controls in the MCR operate the pumps identified in Table 2.3.1-1 to actuate the pumps identified in to cause pumps listed in Table perform the listed functions. Table 2.3.1-1 using controls in 2.3.1-1 to perform the listed the MCR. functions.
5. Displays of the parameters identified Inspection will be performed for Displays identified in Table in Table 2.3.1-1 can be retrieved in the retrievability of the parameters 2.3.1-1 can be retrieved in the MCR. in the MCR. MCR.

C-183a Amendment No. 112

Table 2.3.1-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 282 2.3.01.04 Not used per Amendment No. 112 283 2.3.01.05 Not used per Amendment No. 112 Table 2.3.1-3 Component Name Tag No. Component Location CCS Pump A CCS-MP-01A Turbine Building CCS Pump B CCS-MP-01B Turbine Building CCS Heat Exchanger A CCS-ME-01A Turbine Building CCS Heat Exchanger B CCS-ME-01B Turbine Building C-184 Amendment No. 112

Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 296 2.3.02.06b 6.b) The Class 1E components Testing will be performed on the A simulated test signal exists identified in Table 2.3.2-1 are powered CVS by providing a simulated at the Class 1E equipment from their respective Class 1E division. test signal in each Class 1E identified in Table 2.3.2-1 division. when the assigned Class 1E division is provided the test signal.

297 2.3.02.06c Not used per Amendment No. 84 298 2.3.02.07a Not used per Amendment No. 84 299 2.3.02.07b Not used per Amendment No. 84 300 2.3.02.07c Not used per Amendment No. 84 301 2.3.02.08a.i 8.a) The CVS provides makeup water i) Testing will be performed by i) Each CVS makeup pump to the RCS. aligning a flow path from each provides a flow rate of greater CVS makeup pump, actuating than or equal to 100 gpm.

makeup flow to the RCS at pressure greater than or equal to 2000 psia, and measuring the flow rate in the makeup pump discharge line with each pump suction aligned to the boric acid storage tank.

8.b) The CVS provides the pressurizer Testing will be performed by Each CVS makeup pump auxiliary spray. aligning a flow path from each provides spray flow to the CVS makeup pump to the pressurizer.

pressurizer auxiliary spray and measuring the flow rate in the makeup pump discharge line with each pump suction aligned to the boric acid storage tank and with RCS pressure greater than or equal to 2000 psia.

9. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.3.2-1 can be retrieved in the retrievability of the safety- identified in Table 2.3.2-1 can MCR. related displays in the MCR. be retrieved in the MCR.

10.a) Controls exist in the MCR to Stroke testing will be performed Controls in the MCR operate cause the remotely operated valves on the remotely operated valves to cause the remotely operated identified in Table 2.3.2-1 to perform identified in Table 2.3.2-1 using valves identified in Table active functions. the controls in the MCR. 2.3.2-1 to perform active functions.

10.b) The valves identified in Table i) Testing will be performed i) The valves identified in 2.3.2-1 as having PMS control perform using real or simulated signals Table 2.3.2-1 as having PMS an active safety function after receiving into the PMS. control perform the active a signal from the PMS. function identified in the table after receiving a signal from the PMS.

C-195 Amendment No. 112

Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria ii) Testing will be performed to ii) These valves close within demonstrate that the remotely the following times after operated CVS isolation valves receipt of an actuation signal:

CVS-V090, V091, V136A/B V090, V091 < 30 sec close within the required V136A/B < 20 sec response time.

11.a) The motor-operated and check iii) Tests of the motor-operated iii) Each motor-operated valve valves identified in Table 2.3.2-1 valves will be performed under changes position as indicated perform an active safety-related pre-operational flow, differential in Table 2.3.2-1 under pre-function to change position as indicated pressure, and temperature operational test conditions.

in the table. conditions.

iv) Exercise testing of the check iv) Each check valve changes valves with active safety position as indicated in Table functions identified in Table 2.3.2-1.

2.3.2-1 will be performed under pre-operational test pressure, temperature and fluid flow conditions.

11.b) After loss of motive power, the Testing of the remotely operated Upon loss of motive power, remotely operated valves identified in valves will be performed under each remotely operated valve Table 2.3.2-1 assume the indicated loss the conditions of loss of motive identified in Table 2.3.2-1 of motive power position. power. assumes the indicated loss of motive power position.

12.a) Controls exist in the MCR to Testing will be performed to Controls in the MCR cause cause the pumps identified in Table actuate the pumps identified in pumps identified in Table 2.3.2-3 to perform the listed function. Table 2.3.2-3 using controls in 2.3.2-3 to perform the listed the MCR. function.

12.b) The pumps identified in Table Testing will be performed to The pumps identified in Table 2.3.2-3 start after receiving a signal confirm starting of the pumps 2.3.2-3 start after a signal is from the PLS. identified in Table 2.3.2-3. generated by the PLS.

13. Displays of the parameters Inspection will be performed for Displays identified in Table identified in Table 2.3.2-3 can be retrievability of the displays 2.3.2-3 can be retrieved in the retrieved in the MCR. identified in Table 2.3.2-3 in the MCR.

MCR.

302 2.3.02.08a.ii 8.a) The CVS provides makeup water ii) Inspection of the boric acid ii) The volume in the boric to the RCS. storage tank volume will be acid storage tank is at least performed. 70,000 gallons between the tank suction point and the tank overflow.

303 2.3.02.08a.iii 8.a) The CVS provides makeup water iii) Testing will be performed to iii) The total CVS makeup to the RCS. measure the delivery rate from flow to the RCS is less than or the DWS to the RCS. Both CVS equal to 175 gpm.

makeup pumps will be operating and the RCS pressure will be below 6 psig.

C-195a Amendment No. 112

Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 304 2.3.02.08b Not used per Amendment No. 112 305 2.3.02.09 Not used per Amendment No. 112 306 2.3.02.10a Not used per Amendment No. 112 307 2.3.02.10b.i Not used per Amendment No. 112 308 2.3.02.10b.ii Not used per Amendment No. 112 309 2.3.02.11a.i 11.a) The motor-operated and check i) Tests or type tests of i) A test report exists and valves identified in Table 2.3.2-1 motor-operated valves will be concludes that each motor-perform an active safety-related performed that demonstrate the operated valve function to change position as indicated capability of the valve to operate changes position as indicated in the table. under its design conditions. in Table 2.3.2-1 under design conditions.

ii) Inspection will be performed ii) A report exists and for the existence of a report concludes that the as-built verifying that the as-built motor- motor-operated valves are operated valves are bounded by bounded by the tests or type the tested conditions. tests.

310 2.3.02.11a.ii Not used per Amendment No. 84 C-196 Amendment No. 112

Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 311 2.3.02.11a.iii Not used per Amendment No. 112 312 2.3.02.11a.iv Not used per Amendment No. 112 313 2.3.02.11b Not used per Amendment No. 112 314 2.3.02.12a Not used per Amendment No. 112 315 2.3.02.12b Not used per Amendment No. 112 316 2.3.02.13 Not used per Amendment No. 112 317 2.3.02.14 14. The nonsafety-related piping Inspection will be conducted of The CVS Seismic Analysis located inside containment and the as-built components as Reports exist for the non-designated as reactor coolant pressure documented in the CVS Seismic safety related piping located boundary, as identified in Table 2.3.2-2, Analysis Report. inside containment and has been designed to withstand a designated as reactor coolant seismic design basis event and maintain pressure boundary as structural integrity. identified in Table 2.3.2-2.

C-197 Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built DOS conforms DOS is as described in the Design will be performed. with the functional Description of this Section 2.3.3. arrangement described in the Design Description of this Section 2.3.3.

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 hours0.167 days <br />0.0238 weeks <br />0.00548 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. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built FPS conforms FPS is as described in the Design will be performed. with the functional Description of this Section 2.3.4. arrangement described in the Design Description of this Section 2.3.4.

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. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built MHS conforms MHS is as described in the Design will be performed. with the functional Description of this Section 2.3.5. arrangement as described in the Design Description of this Section 2.3.5.

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. 112

Table 2.3.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 346 2.3.05.03b.i 3.b) The cask handling crane is single i) Validation of double design i) A report exists and failure proof. factors is provided for hooks concludes that the cask where used as load bearing handling crane is single failure components. Validation of proof. A certificate of redundant factors is provided for conformance from the vendor load bearing components such exists and concludes that the as: cask handling crane is single

  • Hoisting ropes failure proof.
  • Sheaves
  • Equalizer assembly
  • Holding brakes 347 2.3.05.03b.ii Not used per Amendment No. 112 348 2.3.05.03b.iii 3.b) The cask handling crane is single ii) Testing of the cask handling ii) The cask handling crane failure proof. crane is performed. shall be static load tested to 125% of the rated load.

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

4. The cask handling crane cannot Testing of the cask handling The cask handling crane does move over the spent fuel pool. crane is performed. not move over the spent fuel pool.

349 2.3.05.03c.i 3.c) The equipment hatch hoist is i) Validation of double design i) A report exists and single failure proof. factors is provided for hooks concludes that the equipment where used as load bearing hatch hoist is single failure components. Validation of proof. A certificate of redundant factors is provided for conformance from the vendor load bearing components such exists and concludes that the as: equipment hatch hoist is

  • Hoisting ropes single failure proof.
  • Sheaves
  • Equalizer assembly
  • Holding brakes 350 2.3.05.03c.ii 3.c) The equipment hatch hoist is ii) Testing of the equipment ii) The equipment hatch hoist single failure proof. hatch hoist is performed. holding mechanism shall stop and hold the hatch.

C-212 Amendment No. 112

Table 2.3.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 351 2.3.05.03d.i 3.d) The maintenance hatch hoist is i) Validation of double design i) A report exists and single failure proof. factors is provided for hooks concludes that the where used as load bearing maintenance hatch hoist is components. Validation of single failure proof. A redundant factors is provided for certificate of conformance load bearing components such from the vendor exists and as: concludes that the

  • Hoisting ropes maintenance hatch hoist is
  • Sheaves single failure proof.
  • Equalizer assembly
  • Holding brakes C-212a Amendment No. 112

Table 2.3.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 352 2.3.05.03d.ii 3.d) The maintenance hatch hoist is ii) Testing of the maintenance ii) The maintenance hatch single failure proof. hatch hoist is performed. hoist holding mechanism shall stop and hold the hatch.

353 2.3.05.04 Not used per Amendment No. 112 Table 2.3.5-3 Component Name Tag No. Component Location Containment Polar Crane MHS-MH-01 Containment Cask Handling Crane MHS-MH-02 Auxiliary Building Equipment Hatch Hoist MHS-MH-05 Containment Maintenance Hatch Hoist MHS-MH-06 Containment 2.3.6 Normal Residual Heat Removal System Design Description The normal residual heat removal system (RNS) removes heat from the core and reactor coolant system (RCS) and provides RCS low temperature over-pressure (LTOP) protection at reduced RCS pressure and temperature conditions after shutdown. The RNS also provides a means for cooling the in-containment refueling water storage tank (IRWST) during normal plant operation.

The RNS is as shown in Figure 2.3.6-1 and the RNS component locations are as shown in Table 2.3.6-5.

1. The functional arrangement of the RNS is as described in the Design Description of this Section 2.3.6.
2. a) The components identified in Table 2.3.6-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

b) The piping identified in Table 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 components identified in Table 2.3.6-1 as ASME Code Section III meet ASME Code Section III requirements.

b) Pressure boundary welds in piping identified in Table 2.3.6-2 as ASME Code Section III meet ASME Code Section III requirements.

C-213 Amendment No. 112

Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 375 2.3.06.09b.ii 9.b) The RNS provides heat removal ii) Testing will be performed to ii) Each RNS pump provides from the reactor coolant during confirm that the RNS can at least 1400 gpm net flow to shutdown operations. provide flow through the RNS the RCS when the hot leg heat exchangers when the pump water level is at an elevation suction is aligned to the RCS hot 15.5 inches +/- 2 inches above leg and the discharge is aligned the bottom of the hot leg.

to both PXS DVI lines with the RCS at atmospheric pressure.

iii) Inspection will be performed iii) The RCS cold legs piping of the reactor coolant loop centerline is 17.5 inches +/- 2 piping. inches above the hot legs piping centerline.

iv) Inspection will be performed iv) The RNS pump suction of the RNS pump suction piping. piping from the hot leg to the pump suction piping low point does not form a local high point (defined as an upward slope with a vertical rise greater than 3 inches).

v) Inspection will be performed v) The RNS suction line of the RNS pump suction nozzle connection to the RCS is connection to the RCS hot leg. constructed from 20-inch Schedule 140 pipe.

9.c) The RNS provides low pressure Testing will be performed to Each RNS pump provides at makeup flow from the cask loading pit confirm that the RNS can least 1100 gpm net flow to the to the RCS for scenarios following provide low pressure makeup RCS when the water level actuation of the ADS. flow from the cask loading pit to above the bottom of the cask the RCS when the pump suction loading pit is 1 foot +/- 6 is aligned to the cask loading pit inches.

and the discharge is aligned to both PXS DVI lines with RCS at atmospheric pressure.

9.d) The RNS provides heat removal Testing will be performed to Two operating RNS pumps from the in-containment refueling water confirm that the RNS can provide at least 2000 gpm to storage tank (IRWST). provide flow through the RNS the IRWST.

heat exchangers when the pump suction is aligned to the IRWST and the discharge is aligned to the IRWST.

12.a) The motor-operated and check iii) Tests of the motor-operated iii) Each motor-operated valves identified in Table 2.3.6-1 valves will be performed under valve changes position as perform an active safety-related preoperational flow, differential indicated in Table 2.3.6-1 function to change position as indicated pressure and temperature under preoperational test in the table. conditions. conditions.

C-226 Amendment No. 112

Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria iv) Exercise testing of the check iv) Each check valve changes valves active safety functions position as indicated in Table identified in Table 2.3.6-1 will 2.3.6-1.

be performed under preoperational test pressure, temperature and fluid flow conditions.

376 2.3.06.09b.iii Not used per Amendment No. 112 377 2.3.06.09b.iv Not used per Amendment No. 112 378 2.3.06.09b.v Not used per Amendment No. 112 379 2.3.06.09c Not used per Amendment No. 112 380 2.3.06.09d Not used per Amendment No. 112 381 2.3.06.10 Not used per Amendment No. 112 C-226a Amendment No. 112

Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 382 2.3.06.11a 10. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.3.6-1 can be retrieved in the retrievability of the safety- identified in Table 2.3.6-1 can MCR. related displays in the MCR. be retrieved in the MCR.

11.a) Controls exist in the MCR to Stroke testing will be performed Controls in the MCR operate cause those remotely operated valves on the remotely operated valves to cause those remotely identified in Table 2.3.6-1 to perform identified in Table 2.3.6-1 using operated valves identified in active functions. the controls in the MCR. Table 2.3.6-1 to perform active functions.

11.b) The valves identified in Table Testing will be performed using The valves identified in Table 2.3.6-1 as having PMS control perform real or simulated signals into the 2.3.6-1 as having PMS control active safety functions after receiving a PMS. perform the active function signal from the PMS. identified in the table after receiving a signal from the PMS.

12.b) After loss of motive power, the Testing of the remotely operated Upon loss of motive power, remotely operated valves identified in valves will be performed under each remotely operated valve Table 2.3.6-1 assume the indicated loss the conditions of loss of motive identified in Table 2.3.6-1 of motive power position. power. assumes the indicated loss of motive power position.

13. Controls exist in the MCR to cause Testing will be performed to Controls in the MCR cause the pumps identified in Table 2.3.6-3 to actuate the pumps identified in pumps identified in Table perform the listed function. Table 2.3.6-3 using controls in 2.3.6-3 to perform the listed the MCR. action.
14. Displays of the RNS parameters Inspection will be performed for Displays of the RNS identified in Table 2.3.6-3 can be retrievability in the MCR of the parameters identified in Table retrieved in the MCR. displays identified in Table 2.3.6-3 are retrieved in the 2.3.6-3. MCR.

383 2.3.06.11b Not used per Amendment No. 112 384 2.3.06.12a.i 12.a) The motor-operated and check i) Tests or type tests of i) A test report exists and valves identified in Table 2.3.6-1 motor-operated valves will be concludes that each motor-perform an active safety-related performed that demonstrate the operated valve changes function to change position as indicated capability of the valve to operate position as indicated in in the table. under its design conditions. Table 2.3.6-1 under design conditions.

ii) Inspection will be performed ii) A report exists and for the existence of a report concludes that the as-built verifying that the as-built motor- motor-operated valves are operated valves are bounded by bounded by the tested the tested conditions. conditions.

385 2.3.06.12a.ii Not used per Amendment No. 84 C-227 Amendment No. 112

Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 386 2.3.06.12a.iii Not used per Amendment No. 112 387 2.3.06.12a.iv Not used per Amendment No. 112 388 2.3.06.12b Not used per Amendment No. 112 389 2.3.06.13 Not used per Amendment No. 112 390 2.3.06.14 Not used per Amendment No. 112 C-228 Amendment No. 112

Table 2.3.7-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 406 2.3.07.07b.v Not used per Amendment No. 84 407 2.3.07.07b.vi Not used per Amendment No. 84 408 2.3.07.07c 7c) The SFS provides check valves in Exercise testing of the check Each check valve changes the drain line from the refueling cavity valves with active safety- position as indicated on to prevent flooding of the refueling functions identified in Table Table 2.3.7-1.

cavity during containment flooding. 2.3.7-1 will be performed under pre-operational test pressure, temperature and flow conditions.

8. The SFS provides the nonsafety- ii) Testing will be performed to ii) Each SFS pump produces related function of removing spent fuel confirm that each SFS pump at least 900 gpm through its decay heat using pumped flow through provides flow through its heat heat exchanger.

a heat exchanger. exchanger when taking suction from the SFP and returning flow to the SFP.

9. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.3.7-1 can be retrieved in the retrievability of the safety- identified in Table 2.3.7-1 can MCR. related displays in the MCR. be retrieved in the MCR.
10. Controls exist in the MCR to cause Testing will be performed to Controls in the MCR cause the pumps identified in Table 2.3.7-3 to actuate the pumps identified in pumps identified in Table perform their listed functions. Table 2.3.7-3 using controls in 2.3.7-3 to perform the listed the MCR. functions.
11. Displays of the SFS parameters Inspection will be performed for Displays of the SFS identified in Table 2.3.7-3 can be retrievability in the MCR of the parameters identified in Table retrieved in the MCR. displays identified in Table 2.3.7-3 are retrieved in the 2.3.7-3. MCR.

409 2.3.07.08.i 8. The SFS provides the nonsafety- i) Inspection will be performed i) A report exists and related function of removing spent fuel for the existence of a report that concludes that the heat decay heat using pumped flow through determines the heat removal transfer characteristic, UA, of a heat exchanger. capability of the SFS heat each SFS heat exchanger is exchangers. greater than or equal to 2.2 million Btu/hr-°F.

410 2.3.07.08.ii Not used per Amendment No. 112 411 2.3.07.09 Not used per Amendment No. 112 412 2.3.07.10 Not used per Amendment No. 112 413 2.3.07.11 Not used per Amendment No. 112 C-238 Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built SWS conforms SWS is as described in the Design will be performed. with the functional Description of this Section 2.3.8. arrangement as described in the Design Description of this Section 2.3.8.

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. 112

Table 2.3.8-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 418 2.3.08.03 Not used per Amendment No. 112 419 2.3.08.04 Not used per Amendment No. 112 Table 2.3.8-3 Component Name Tag No. Component Location Service Water Pump A SWS-MP-01A Turbine Building or yard Service Water Pump B SWS-MP-01B Turbine Building or yard Service Water Cooling Tower SWS-ME-01 Yard C-243 Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built VLS conforms VLS is as described in the Design will be performed. with the functional Description of this Section 2.3.9. arrangement as described in the Design Description of this Section 2.3.9.

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. 112

Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 424 2.3.09.03.ii 3. The VLS provides the nonsafety- i) Inspection for the number of i) At least 66 hydrogen related function to control the igniters will be performed. igniters are provided inside containment hydrogen concentration for containment at the locations beyond design basis accidents. specified in Table 2.3.9-2.

ii) Operability testing will be ii) The surface temperature of performed on the igniters. the igniter meets or exceeds 1700°F.

4.a) Controls exist in the MCR to cause Testing will be performed on the Controls in the MCR operate the components identified in Table igniters using the controls in the to energize the igniters 2.3.9-2 to perform the listed function. MCR.

5. Displays of the parameters identified Inspection will be performed for Displays identified in Table in Table 2.3.9-1 can be retrieved in the retrievability of the displays 2.3.9-1 can be retrieved in the MCR. identified in Table 2.3.9-1 in the MCR.

MCR.

425 2.3.09.03.iii 3. The VLS provides the nonsafety- iii) An inspection of the as-built iii) The equipment access related function to control the containment internal structures opening and CMT-A opening containment hydrogen concentration for will be performed. constitute at least 98% of the beyond design basis accidents. vent path area from Room 11206 to Room 11300. The minimum distance between the equipment access opening and the containment shell is at least 24.3 feet. The minimum distance between the CMT-A opening and the containment shell is at least 9.4 feet. The CMT-B opening constitutes at least 98% of the vent path area from Room 11207 to Room 11300 and is a minimum distance of 24.6 feet away from the containment shell.

Other openings through the ceilings of these rooms must be at least 3 feet from the containment shell.

426 2.3.09.03.iv 3. The VLS provides the nonsafety- iv) An inspection will be iv) The discharge from each related function to control the performed of the as-built IRWST of these IRWST vents is containment hydrogen concentration for vents that are located in the roof oriented generally away from beyond design basis accidents. of the IRWST along the side of the containment shell.

the IRWST next to the containment shell.

C-249 Amendment No. 112

Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 427 2.3.09.04a Not used per Amendment No. 112 428 2.3.09.04b 4.b) The components identified in Testing will be performed on the The igniters energize after Table 2.3.9-2 perform the listed igniters using the DAS controls. receiving a signal from DAS.

function after receiving manual a signal from DAS.

429 2.3.09.05 Not used per Amendment No. 112 2.3.10 Liquid Radwaste System Design Description The liquid radwaste system (WLS) receives, stores, processes, samples and monitors the discharge of radioactive wastewater.

C-249a Amendment No. 112

Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 440 2.3.10.05b Not used per Amendment No. 85 441 2.3.10.06a Not used per Amendment No. 85 442 2.3.10.06b Not used per Amendment No. 85 443 2.3.10.07a.i Not used per Amendment No. 112 444 2.3.10.07a.ii 7.a) The WLS provides the nonsafety- i) Inspection will be performed i) Nonsafety-related displays related function of detecting leaks for retrievability of the displays of WLS containment sump within containment to the containment of containment sump level level channels WLS-034, sump. channels WLS-034, WLS-035, WLS-035, and WLS-036 can and WLS-036 in the MCR. be retrieved in the MCR.

ii) Testing will be performed by ii) A report exists and adding water to the sump and concludes that sump level observing display of sump level. channels WLS-034, WLS-035, and WLS-036 can detect a change of 1.75 +/- 0.1 inches.

7.b) The WLS provides the nonsafety- Tests will be performed to A simulated high radiation related function of controlling releases confirm that a simulated high signal causes the discharge of radioactive materials in liquid radiation signal from the control isolation valve effluents. discharge radiation monitor, WLS-PL-V223 to close.

WLS-RE-229, causes the discharge isolation valve WLS-PL-V223 to close.

8. Controls exist in the MCR to cause Stroke testing will be performed Controls in the MCR operate the remotely operated valve identified on the remotely operated valve to cause the remotely operated in Table 2.3.10-3 to perform its active listed in Table 2.3.10-3 using valve to perform its active function. controls in the MCR. function.
9. The check valves identified in Table Exercise testing of the check Each check valve changes 2.3.10-1 perform an active safety- valves with active safety position as indicated on Table related function to change position as functions identified in Table 2.3.10-1.

indicated in the table. 2.3.10-1 will be performed under pre-operational test pressure, temperature and flow conditions.

10. Displays of the parameters Inspection will be performed for Displays identified in Table identified in Table 2.3.10-3 can be retrievability of the displays 2.3.10-3 can be retrieved in retrieved in the MCR. identified in Table 2.3.10-3 in the MCR.

the MCR.

445 2.3.10.07b Not used per Amendment No. 112 446 2.3.10.08 Not used per Amendment No. 112 447 2.3.10.09 Not used per Amendment No. 112 C-255 Amendment No. 112

Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 448 2.3.10.10 Not used per Amendment No. 112 878 2.3.10.11a 11. a) The Class 1E components Testing will be performed on the A simulated test signal exists identified in Table 2.3.10-1 are powered WLS by providing a simulated at the Class 1E components from their respective Class 1E division. test signal in each Class 1E identified in Table 2.3.10-1 division. when the assigned Class 1E division is provided the test signal.

879 2.3.10.12 12. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.3.10-1 can be retrieved in the retrievability of the safety- identified in Table 2.3.10-1 main control room (MCR). related displays in the MCR. can be retrieved in the MCR.

Table 2.3.10-5 Component Name Tag No. Component Location WLS Reactor Coolant Drain Tank WLS-MT-01 Containment WLS Containment Sump WLS-MT-02 Containment WLS Degasifier Column WLS-MV-01 Auxiliary Building WLS Effluent Holdup Tanks WLS-MT-05A Auxiliary Building WLS-MT-05B WLS Waste Holdup Tanks WLS-MT-06A Auxiliary Building WLS-MT-06B WLS Waste Pre-Filter WLS-MV-06 Auxiliary Building WLS Ion Exchangers WLS-MV-03 Auxiliary Building WLS-MV-04A WLS-MV-04B WLS-MV-04C WLS Waste After-Filter WLS-MV-07 Auxiliary Building WLS Monitor Tanks WLS-MT-07A Auxiliary Building WLS-MT-07B WLS-MT-07C WLS-MT-07D Radwaste Building WLS-MT-07E WLS-MT-07F C-256 Amendment No. 112

Table 2.3.13-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 470 2.3.13.08 8. The PSS provides the nonsafety- Testing will be performed to A sample is drawn from the related function of providing the obtain samples of the reactor reactor coolant and the capability of obtaining reactor coolant coolant and containment containment atmosphere.

and containment atmosphere samples. atmosphere.

9. Safety-related displays identified in Inspection will be performed for The safety-related displays Table 2.3.13-1 can be retrieved in the retrievability of the safety- identified in Table 2.3.13-1 MCR. related displays in the MCR. can be retrieved in the MCR.

10.a) Controls exist in the MCR to Stroke testing will be performed Controls in the MCR operate cause those remotely operated valves on the remotely operated valves to cause those remotely identified in Table 2.3.13-1 to perform identified in Table 2.3.13-1 operated valves identified in active functions. using the controls in the MCR. Table 2.3.13-1 to perform active functions.

10.b) The valves identified in Table Testing will be performed on The remotely operated valves 2.3.13-1 as having PMS control remotely operated valves listed identified in Table 2.3.13-1 as perform an active function after in Table 2.3.13-1 using real or having PMS control perform receiving a signal from the PMS. simulated signals into the PMS. the active function identified in the table after receiving a signal from the PMS.

11.b) After loss of motive power, the Testing of the remotely operated After loss of motive power, remotely operated valves identified in valves will be performed under each remotely operated valve Table 2.3.13-1 assume the indicated the conditions of loss of motive identified in Table 2.3.13-1 loss of motive power position. power. assumes the indicated loss of motive power position.

12. Controls exist in the MCR to cause Testing will be performed on the Controls in the MCR cause the valves identified in Table 2.3.13-2 components in Table 2.3.13-2 valves identified in Table to perform the listed function. using controls in the MCR. 2.3.13-2 to perform the listed functions.

471 2.3.13.09 Not used per Amendment No. 112 472 2.3.13.10a Not used per Amendment No. 112 473 2.3.13.10b Not used per Amendment No. 112 474 2.3.13.11a 11.a) Deleted.

475 2.3.13.11b Not used per Amendment No. 112 476 2.3.13.12 Not used per Amendment No. 112 C-267 Amendment No. 112

Table 2.3.19-1 Telephone/Page System Equipment Location Fuel Handling Area 12562 Division A, B, C, D dc Equipment Rooms 12201/12203/12205/12207 Division A, B, C, D I&C Rooms 12301/12302/12304/12305 Maintenance Floor Staging Area 12351 Containment Maintenance Floor 11300 Containment Operating Deck 11500 Table 2.3.19-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 484 2.3.19.01a Not used per Amendment No. 112 485 2.3.19.01b Not used per Amendment No. 112 486 2.3.19.02a 1.a) The EFS has handsets, amplifiers, Inspection of the as-built system The as-built EFS has handsets, loudspeakers, and siren tone generators will be performed. amplifiers, loudspeakers, and connected as a telephone/page system. siren tone generators connected as a telephone/page system.

1.b) The EFS has sound-powered Inspection of the as-built system The as-built EFS has sound-equipment connected as a system. will be performed. powered equipment connected as a system.

2.a) The EFS telephone/page system An inspection and test will be Telephone/page equipment is provides intraplant, station-to-station performed on the telephone/page installed and voice communications and area broadcasting communication equipment. transmission and reception between the MCR and the locations from the MCR are listed in Table 2.3.19-1. accomplished.

2.b) EFS provides sound-powered An inspection and test will be Sound-powered equipment is communications between the MCR, the performed of the sound-powered installed and voice RSW, the Division A, B, C, D communication equipment. transmission and reception are dc equipment rooms (Rooms accomplished.

12201/12203/12205/ 12207), the Division A, B, C, D I&C rooms (Rooms 12301/12302/ 12304/12305), and the diesel generator building (Rooms 60310/60320) without external power.

487 2.3.19.02b Not used per Amendment No. 112 C-273 Amendment No. 112

2.3.20 Turbine Building Closed Cooling Water System No entry for this system.

2.3.21 Secondary Sampling System No entry for this system.

2.3.22 Containment Leak Rate Test System No entry. Covered in Section 2.2.1, Containment System.

2.3.23 This section intentionally blank 2.3.24 Demineralized Water Treatment System No entry for this system.

2.3.25 Gravity and Roof Drain Collection System No entry for this system.

2.3.26 This section intentionally blank 2.3.27 Sanitary Drainage System No entry for this system.

2.3.28 Turbine Island Vents, Drains, and Relief System No entry for this system.

2.3.29 Radioactive Waste Drain System Design Description The radioactive waste drain system (WRS) collects radioactive and potentially radioactive liquid wastes from equipment and floor drains during normal operation, startup, shutdown, and refueling. The liquid wastes are then transferred to appropriate processing and disposal systems.

Nonradioactive wastes are collected by the waste water system (WWS). The WRS is as shown in Figure 2.3.29-1.

1. The functional arrangement of the WRS is as described in the Design Description of this Section 2.3.29.
2. The WRS collects liquid wastes from the equipment and floor drainage of the radioactive portions of the auxiliary building, annex building, and radwaste building and directs these wastes to a WRS sump or WLS waste holdup tanks located in the auxiliary building.
3. The WRS collects chemical wastes from the auxiliary building chemical laboratory drains and the decontamination solution drains in the annex building and directs these wastes to the chemical waste tank of the liquid radwaste system.
4. The WWS stops the discharge from the turbine building sumps upon detection of high radiation in the discharge stream to the oil separator.

C-274 Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built WRS conforms WRS is as described in the Design will be performed. with the functional Description of this Section 2.3.29. arrangement as described in the Design Description of this Section 2.3.29.

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. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built startup feedwater startup feedwater system is as described will be performed. system conforms with the in the Design Description of this functional arrangement as Section 2.4.1. described in the Design Description of this Section 2.4.1.

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. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built MTS conforms MTS is as described in the Design will be performed. with the functional Description of this Section 2.4.2. arrangement as described in the Design Description of this Section 2.4.2.

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. 112

Table 2.4.2-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 498 2.4.02.02b 2.b) The main turbine-generator trips Testing will be performed using The main turbine-generator after receiving a signal from the PMS. real or simulated signals into the trips after receiving a signal PMS. from the PMS.

499 2.4.02.02c Not used per Amendment No. 112 500 2.4.02.03.i 3) The trip signals from the two turbine i) The system design will be i) The system design review electrical overspeed protection trip reviewed. shows that the trip signals of systems are isolated from, and the two electrical overspeed independent of, each other. protection trip systems are isolated from, and independent of, each other.

C-280a Amendment No. 112

Table 2.4.2-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 501 2.4.02.03.ii Not used per Amendment No. 112 502 2.4.02.03.iii 3) The trip signals from the two turbine iii) Inspection will be performed iii) A report exists and electrical overspeed protection trip for the existence of a report concludes that the two systems are isolated from, and verifying that the two turbine electrical overspeed protection independent of, each other. electrical overspeed protection systems have diverse systems have diverse hardware hardware and and software/firmware. software/firmware.

Table 2.4.2-2 Component Name Tag No. Component Location HP Turbine MTS-MG-01 Turbine Building LP Turbine A MTS-MG-02A Turbine Building LP Turbine B MTS-MG-02B Turbine Building LP Turbine C MTS-MG-02C Turbine Building Gland Steam Condenser GSS-ME-01 Turbine Building Gland Condenser Vapor Exhauster 1A GSS-MA-01A Turbine Building Gland Condenser Vapor Exhauster 1B GSS-MA-01B Turbine Building Electrical Overspeed Trip Device -- Turbine Building Emergency Electrical Overspeed -- Turbine Building Trip Device 2.4.3 Main Steam System No entry. Covered in Section 2.2.4, Steam Generator System.

C-281 Amendment No. 112

Table 2.5.1-3 DAS Sensors and Displays Equipment Name Tag Number Containment Temperature VCS-053A Containment Temperature VCS-053B Core Exit Temperature IIS-009 Core Exit Temperature IIS-013 Core Exit Temperature IIS-030 Core Exit Temperature IIS-034 Rod Control Motor Generator Voltage PLS-001 Rod Control Motor Generator Voltage PLS-002 Table 2.5.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 505 2.5.01.01 Not used per Amendment No. 85 506 2.5.01.02a 2.a) The DAS provides an automatic Electrical power to the PMS The generator field control reactor trip on low wide-range steam equipment will be disconnected relays (contained in the generator water level, or on low and an operational test of the as- control cabinets for the rod pressurizer water level, or on high hot built DAS will be performed drive motor-generator sets) leg temperature, separate from the using real or simulated test open after the test signal PMS. signals. reaches the specified limit.

2.b) The DAS provides automatic Electrical power to the PMS Appropriate DAS output actuation of selected functions, as equipment will be disconnected signals are generated after the identified in Table 2.5.1-1, separate and an operational test of the test signal reaches the from the PMS. as-built DAS will be performed specified limit.

using real or simulated test signals.

2.c) The DAS provides manual Electrical power to the control i) The generator field control initiation of reactor trip, and selected room multiplexers, if any, and relays (contained in the functions, as identified in Table 2.5.1-2, PMS equipment will be control cabinets for the rod separate from the PMS. These manual disconnected and the outputs drive motor-generator sets) initiation functions are implemented in from the DAS signal processing open after reactor and turbine a manner that bypasses the control equipment will be disabled. trip manual initiation controls room multiplexers, if any; the PMS While in this configuration, an are actuated.

cabinets; and the signal processing operational test of the as-built equipment of the DAS. system will be performed using the DAS manual actuation controls.

C-287 Amendment No. 112

Table 2.5.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria Electrical power to the control ii) DAS output signals are room multiplexers, if any, and generated for the selected PMS equipment will be functions, as identified in disconnected and the outputs Table 2.5.1-2, after manual from the DAS signal processing initiation controls are equipment will be disabled. actuated.

While in this configuration, an operational test of the as-built system will be performed using the DAS manual actuation controls.

2.d) The DAS provides MCR displays Electrical power to the PMS The selected plant parameters of selected plant parameters, as equipment will be disconnected can be retrieved in the MCR.

identified in Table 2.5.1-3, separate and inspection will be performed from the PMS. for retrievability of the selected plant parameters in the MCR.

3.f) The DAS is powered by non-Class Electrical power to the PMS A simulated test signal exists 1E uninterruptible power supplies that equipment will be disconnected. at the DAS equipment when are independent and separate from the While in this configuration, a the assigned non-Class 1E power supplies which power the PMS. test will be performed by uninterruptible power supply providing simulated test signals is provided the test signal.

in the non-Class 1E uninterruptible power supplies.

3.g) The DAS signal processing Channel tests will be performed The capability exists for cabinets are provided with the on the as built system. testing individual DAS capability for channel testing without channels without propagating actuating the controlled components. an actuation signal to a DAS controlled component.

507 2.5.01.02b Not used per Amendment No. 112 508 2.5.01.02c.i Not used per Amendment No. 112 C-287a Amendment No. 112

Table 2.5.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 509 2.5.01.02c.ii Not used per Amendment No. 112 510 2.5.01.02d Not used per Amendment No. 112 511 2.5.01.03a 3.a) The signal processing hardware of Inspection of the as-built DAS The DAS signal processing the DAS uses input modules, output and PMS signal processing equipment uses input modules, and microprocessor or special hardware will be performed. modules, output modules, and purpose logic processor boards that are micro-processor or special different than those used in the PMS. purpose logic processor boards that are different than those used in the PMS. The difference may be a different design, use of different component types, or different manufacturers.

512 2.5.01.03b 3.b) The display hardware of the DAS Inspection of the as-built DAS The DAS display hardware is uses a different display device than that and PMS display hardware will different than the display used in the PMS. be performed. hardware used in the PMS.

The difference may be a different design, use of different component types, or different manufacturers.

513 2.5.01.03c 3.c) Software diversity between the Inspection of the DAS and PMS Any DAS algorithms, logic, DAS and PMS will be achieved through design documentation will be program architecture, the use of different algorithms, logic, performed. executable operating systems, program architecture, executable and executable software/logic operating system, and executable are different than those used software/logic. in the PMS.

514 2.5.01.03d 3.d) The DAS has electrical surge Type tests, analyses, or a A report exists and concludes withstand capability (SWC), and can combination of type tests and that the DAS equipment can withstand the electromagnetic analyses will be performed on withstand the SWC, EMI, RFI interference (EMI), radio frequency the equipment. and ESD conditions that exist (RFI), and electrostatic discharge (ESD) where the DAS equipment is conditions that exist where the DAS located in the plant.

equipment is located in the plant.

C-288 Amendment No. 112

Table 2.5.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 515 2.5.01.03e 3.e) The sensors identified on Table Inspection of the as-built system The sensors identified on 2.5.1-3 are used for DAS input and are will be performed. Table 2.5.1-3 are used by separate from those being used by the DAS and are separate from PMS and plant control system. those being used by the PMS and plant control system.

516 2.5.01.03f Not used per Amendment No. 112 517 2.5.01.03g Not used per Amendment No. 112 518 2.5.01.03h 3.h) The DAS equipment can withstand Type tests, analyses, or a A report exists and concludes the room ambient temperature and combination of type tests and that the DAS equipment can humidity conditions that will exist at analyses will be performed on withstand the room ambient the plant locations in which the DAS the equipment. temperature and humidity equipment is installed at the times for conditions that will exist at the which the DAS is designed to be plant locations in which the operational. DAS equipment is installed at the times for which the DAS is designed to be operational.

519 2.5.01.04 4. The DAS hardware and any software Inspection will be performed of A report exists and concludes are developed using a planned design the process used to design the that the process defines the process which provides for specific hardware and any software. organizational responsibilities, design documentation and reviews activities, and configuration during the following life cycle stages: management controls for the a) Development phase for hardware and following:

any software a) Documentation and review b) System test phase of hardware and any software.

c) Installation phase b) Performance of tests and the documentation of test The planned design process also results during the system test provides for the use of commercial off-phase.

the-shelf hardware and software.

c) Performance of tests and inspections during the installation phase.

The process also defines requirements for the use of commercial off-the-shelf hardware and software.

C-289 Amendment No. 112

Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 527 2.5.02.05a 5.a) The Class 1E equipment, identified Tests will be performed by A simulated test signal exists in Table 2.5.2-1, is powered from its providing a simulated test signal at the Class 1E equipment respective Class 1E division. in each Class 1E division. identified in Table 2.5.2-1 when the assigned Class 1E division is provided the test signal.

528 2.5.02.05b Not used per Amendment No. 84 529 2.5.02.06a.i 6.a) The PMS initiates an automatic An operational test of the as- i) The reactor trip switchgear reactor trip, as identified in built PMS will be performed opens after the test signal Table 2.5.2-2, when plant process using real or simulated test reaches the specified limit.

signals reach specified limits. signals. This only needs to be verified for one automatic reactor trip function.

530 2.5.02.06a.ii 6.a) The PMS initiates an automatic An operational test of the as- ii) PMS output signals to the reactor trip, as identified in built PMS will be performed reactor trip switchgear are Table 2.5.2-2, when plant process using real or simulated test generated after the test signal signals reach specified limits. signals. reaches the specified limit.

This needs to be verified for each automatic reactor trip function.

6.b) The PMS initiates automatic An operational test of the Appropriate PMS output actuation of engineered safety features, as-built PMS will be performed signals are generated after the as identified in Table 2.5.2-3, when using real or simulated test test signal reaches the plant process signals reach specified signals. specified limit. These output limits. signals remain following removal of the test signal.

Tests from the actuation signal to the actuated device(s) are performed as part of the system-related inspection, test, analysis, and acceptance criteria.

6.c) The PMS provides manual An operational test of the ii) PMS output signals are initiation of reactor trip and selected as-built PMS will be performed generated for reactor trip and engineered safety features as identified using the PMS manual actuation selected engineered safety in Table 2.5.2-4. controls. features as identified in Table 2.5.2-4 after the manual initiation controls are actuated.

C-299 Amendment No. 112

Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 8.a) The PMS provides for the i) An inspection will be i) The plant parameters listed minimum inventory of displays, visual performed for retrievability of in Table 2.5.2-5 with a "Yes" alerts, and fixed position controls, as plant parameters in the MCR. in the "Display" column, can identified in Table 2.5.2-5. The plant be retrieved in the MCR.

parameters listed with a "Yes" in the "Display" column and visual alerts listed with a "Yes" in the "Alert" column can be retrieved in the MCR.

The fixed position controls listed with a "Yes" in the "Control" column are provided in the MCR.

iii) An operational test of the as- iii) For each test of an as-built built system will be performed fixed position control listed in using each MCR fixed position Table 2.5.2-5 with a "Yes" in control. the "Control" column, an actuation signal is generated.

Tests from the actuation signal to the actuated device(s) are performed as part of the system-related inspection, test, analysis and acceptance criteria.

8.c) Displays of the open/closed status Inspection will be performed for Displays of the open/closed of the reactor trip breakers can be retrievability of displays of the status of the reactor trip retrieved in the MCR. open/closed status of the reactor breakers can be retrieved in trip breakers in the MCR. the MCR.

9.a) The PMS automatically removes An operational test of the The PMS blocks are blocks of reactor trip and engineered as-built PMS will be performed automatically removed when safety features actuation when the plant using real or simulated test the test signal reaches the approaches conditions for which the signals. specified limit.

associated function is designed to provide protection. These blocks are identified in Table 2.5.2-6.

9.b) The PMS two-out-of-four An operational test of the The PMS two-out-of-four initiation logic reverts to a two-out-of- as-built PMS will be performed. initiation logic reverts to a three coincidence logic if one of the two-out-of-three coincidence four channels is bypassed. All bypassed logic if one of the four channels are alarmed in the MCR. channels is bypassed. All bypassed channels are alarmed in the MCR.

9.c) The PMS does not allow An operational test of the The redundant channel cannot simultaneous bypass of two redundant as-built PMS will be performed. be placed in bypass.

channels. With one channel in bypass, an attempt will be made to place a redundant channel in bypass.

C-299a Amendment No. 112

Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 531 2.5.02.06b Not used per Amendment No. 112 532 2.5.02.06c.i 6.c) The PMS provides manual An operational test of the as- i) The reactor trip switchgear initiation of reactor trip and selected built PMS will be performed opens after manual reactor trip engineered safety features as identified using the PMS manual actuation controls are actuated.

in Table 2.5.2-4. controls.

533 2.5.02.06c.ii Not used per Amendment No. 112 534 2.5.02.07a 7.a) The PMS provides process signals Type tests, analyses, or a A report exists and concludes to the PLS through isolation devices. combination of type tests and that the isolation devices analyses of the isolation devices prevent credible faults from will be performed. propagating into the PMS.

535 2.5.02.07b 7.b) The PMS provides process signals Type tests, analyses, or a A report exists and concludes to the DDS through isolation devices. combination of type tests and that the isolation devices analyses of the isolation devices prevent credible faults from will be performed. propagating into the PMS.

536 2.5.02.07c 7.c) Data communication between Type tests, analyses, or a A report exists and concludes safety and nonsafety systems does not combination of type tests and that data communication inhibit the performance of the safety analyses of the PMS gateways between safety and nonsafety function. will be performed. systems does not inhibit the performance of the safety function.

537 2.5.02.07d 7.d) The PMS ensures that the Type tests, analyses, or a A report exists and concludes automatic safety function and the combination of type tests and that the automatic safety Class 1E manual controls both have analyses of the PMS manual function and the Class 1E priority over the non-Class 1E soft control circuits and algorithms manual controls both have controls. will be performed. priority over the non-Class 1E soft controls.

538 2.5.02.07e 7.e) The PMS receives signals from Type tests, analyses, or a A report exists and concludes non-safety equipment that provides combination of type tests and that the isolation devices interlocks for PMS test functions analyses of the isolation devices prevent credible faults from through isolation devices. will be performed. propagating into the PMS.

539 2.5.02.08a.i Not used per Amendment No. 112 C-300 Amendment No. 112

Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 540 2.5.02.08a.ii 8.a) The PMS provides for the ii) An inspection and test will be ii) The plant parameters listed minimum inventory of displays, visual performed to verify that the plant in Table 2.5.2-5 with a "Yes" alerts, and fixed position controls, as parameters are used to generate in the "Alert" column are used identified in Table 2.5.2-5. The plant visual alerts that identify to generate visual alerts that parameters listed with a "Yes" in the challenges to critical safety identify challenges to critical "Display" column and visual alerts functions. safety functions. The visual listed with a "Yes" in the "Alert" alerts actuate in accordance column can be retrieved in the MCR. with their correct logic and The fixed position controls listed with a values.

"Yes" in the "Control" column are provided in the MCR.

541 2.5.02.08a.iii Not used per Amendment No. 112 542 2.5.02.08b.i 8.b) The PMS provides for the transfer i) An inspection will be i) A transfer switch exists for of control capability from the MCR to performed to verify that a each safety-related division the RSW using multiple transfer transfer switch exists for each and the nonsafety-related switches. Each individual transfer safety-related division and the control capability.

switch is associated with only a single nonsafety-related control safety-related group or with nonsafety- capability.

related control capability.

543 2.5.02.08b.ii 8.b) The PMS provides for the transfer ii) An operational test of the as- ii) Actuation of each transfer of control capability from the MCR to built system will be performed to switch results in an alarm in the RSW using multiple transfer demonstrate the transfer of the MCR and RSW, the switches. Each individual transfer control capability from the MCR activation of operator control switch is associated with only a single to the RSW. capability from the RSW, and safety-related group or with nonsafety- the deactivation of operator related control capability. control capability from the MCR for the associated safety-related division and nonsafety-related control capability.

544 2.5.02.08c Not used per Amendment No. 112 C-301 Amendment No. 112

Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 545 2.5.02.09a Not used per Amendment No. 112 546 2.5.02.09b Not used per Amendment No. 112 547 2.5.02.09c Not used per Amendment No. 112 548 2.5.02.09d 9.d) The PMS provides the interlock An operational test of the as- Appropriate PMS output functions identified in Table 2.5.2-7. built PMS will be performed signals are generated as the using real or simulated test interlock conditions are signals. changed.

549 2.5.02.10 10. Setpoints are determined using a Inspection will be performed for A report exists and concludes methodology which accounts for loop a document that describes the that the PMS setpoints are inaccuracies, response testing, and methodology and input determined using a maintenance or replacement of parameters used to determine the methodology which accounts instrumentation. PMS setpoints. for loop inaccuracies, response testing, and maintenance or replacement of instrumentation.

C-302 Amendment No. 112

Table 2.5.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 556 2.5.04.01 1. The functional arrangement of Inspection of the as-built system The as-built DDS conforms with the DDS is as described in the will be performed. the functional arrangement as Design Description of this described in the Design Section 2.5.4. Description of this Section 2.5.4.

557 2.5.04.02.i 2. The DDS provides for the i) An inspection will be performed i) The plant parameters listed in minimum inventory of displays, for retrievability of plant Table 2.5.4-1 with a "Yes" in the visual alerts, and fixed position parameters at the RSW. "Display" column can be retrieved controls, as identified in Table at the RSW.

2.5.4-1. The plant parameters listed with a "Yes" in the "Display" column and visual alerts listed with a "Yes" in the "Alert" column can be retrieved at the RSW. The controls listed with a "Yes" in the "Control" column are provided at the RSW.

ii) An inspection and test will be ii) The plant parameters listed in performed to verify that the plant Table 2.5.4-1 with a "Yes" in the parameters are used to generate "Alert" column are used to visual alerts that identify generate visual alerts that identify challenges to critical safety challenges to critical safety functions. functions. The visual alerts actuate in accordance with their logic and values.

iii) An operational test of the iii) For each test of a control listed as-built system will be performed in Table 2.5.4-1 with a "Yes" in using each RSW control. the "Control" column, an actuation signal is generated. Tests from the actuation signal to the actuated device(s) are performed as part of the system-related inspection, test, analysis and acceptance criteria.

558 2.5.04.02.ii Not used per Amendment No. 112 559 2.5.04.02.iii Not used per Amendment No. 112 560 2.5.04.03 3. The DDS provides Tests of the as-built system will be The as-built system provides information pertinent to the performed. displays of the bypassed and status of the protection and operable status of the protection safety monitoring system. and safety monitoring system.

C-312 Amendment No. 112

Table 2.5.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 561 C.2.5.04.04a 4. The plant calorimetric Inspection will be performed of a) The as-built system takes input uncertainty and plant the plant operating instrumentation for feedwater flow measurement instrumentation performance is installed for feedwater flow from a Caldon [Cameron] LEFM bounded by the 1% calorimetric measurement, its associated power CheckPlus' System; uncertainty value assumed for calorimetric uncertainty the initial reactor power in the calculation, and the calculated safety analysis. calorimetric values.

Inspection will be performed of b) the power calorimetric the plant operating instrumentation uncertainty calculation installed for feedwater flow documented for that measurement, its associated power instrumentation is based on an calorimetric uncertainty accepted Westinghouse calculation, and the calculated methodology and the uncertainty calorimetric values. values for that instrumentation are not lower than those for the actual installed instrumentation; and Inspection will be performed of c) the calculated calorimetric the plant operating instrumentation power uncertainty measurement installed for feedwater flow values are bounded by the 1%

measurement, its associated power uncertainty value assumed for the calorimetric uncertainty initial reactor power in the safety calculation, and the calculated analysis.

calorimetric values.

562 C.2.5.04.04b Not used per Amendment No. 112 563 C.2.5.04.04c Not used per Amendment No. 112 2.5.5 In-Core Instrumentation System Design Description The in-core instrumentation system (IIS) provides safety-related core exit thermocouple signals to the protection and safety monitoring system (PMS). The IIS also provides nonsafety-related core exit thermocouple signals to the diverse actuation system (DAS). The core exit thermocouples are housed in the core instrument assemblies. Multiple core instrument assemblies are used to provide radial coverage of the core. At least three core instrument assemblies are provided in each core quadrant.

1. The functional arrangement of the IIS is as described in the Design Description of this Section 2.5.5.
2. The seismic Category I equipment identified in Table 2.5.5-1 can withstand seismic design basis loads without loss of safety function.
3. a) The Class 1E equipment identified in Table 2.5.5-1 as being qualified for a harsh environment can withstand environmental conditions that would exist before, during, and following a design basis accident without loss of safety function, for the time required to perform the safety function.

C-313 Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built ECS conforms ECS is as described in the Design will be performed. with the functional Description of this Section 2.6.1. arrangement as described in the Design Description of this Section 2.6.1.

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. 112

Table 2.6.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 586 2.6.01.04c 4.c) Each standby diesel generator Testing will be performed using Each standby diesel generator 6900 Vac circuit breaker closes after real or simulated signals from 6900 Vac circuit breaker receiving a signal from the onsite the standby diesel load system. closes after receiving a signal standby power system. from the standby diesel system.

587 2.6.01.04d 4.d) Each ancillary diesel generator Each ancillary diesel generator Each diesel generator provides unit is sized to supply power to long- will be operated with fuel power to the load with a term safety-related post-accident supplied from the ancillary generator terminal voltage of monitoring loads and control room diesel generator fuel tank and 480 +/- 10% volts and a lighting and ventilation through a with a load of 35 kW or greater frequency of 60 +/- 5% Hz.

regulating transformer; and for one PCS and a power factor between recirculation pump. 0.9 and 1.0 for a time period required to reach engine temperature equilibrium plus 2.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br />.

588 2.6.01.04e 4.a) The ECS provides the capability Tests will be performed using a A test signal exists at the for distributing non-Class 1E ac power test signal to confirm that an terminals of each selected from onsite sources (ZOS) to nonsafety- electrical path exists for each load.

related loads listed in Table 2.6.1-2. selected load listed in Table 2.6.1-2 from an ECS-ES-1 or ECS-ES-2 bus. Each test may be a single test or a series of over-lapping tests.

4.e) The ECS provides two loss-of- Tests on the as-built ECS system A loss-of-voltage signal is voltage signals to the onsite standby will be conducted by simulating generated when the loss-of-power system (ZOS), one for each a loss-of-voltage condition on voltage condition is simulated.

diesel-backed 6900 Vac switchgear bus. each diesel-backed 6900 Vac switchgear bus.

4.f) The ECS provides a reverse-power Tests on the as-built ECS system The generator circuit breaker trip of the generator circuit breaker will be conducted by simulating trip signal does not occur until which is blocked for at least 15 seconds a turbine trip signal followed by at least 15 seconds after the following a turbine trip. a simulated reverse-power simulated turbine trip.

condition. The generator circuit breaker trip signal will be monitored.

5. Controls exist in the MCR to cause Tests will be performed to verify Controls in the MCR cause the circuit breakers identified in Table that controls in the MCR can the circuit breakers identified 2.6.1-3 to perform the listed functions. operate the circuit breakers in Table 2.6.1-3 to operate.

identified in Table 2.6.1-3.

6. Displays of the parameters identified Inspection will be performed for Displays identified in Table in Table 2.6.1-3 can be retrieved in the retrievability of the displays 2.6.1-3 can be retrieved in the MCR. identified in Table 2.6.1-3 in the MCR.

MCR.

C-324 Amendment No. 112

Table 2.6.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 589 2.6.01.04f Not used per Amendment No. 112 590 2.6.01.05 Not used per Amendment No. 112 591 2.6.01.06 Not used per Amendment No. 112 C-324a Amendment No. 112

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 599 2.6.03.02.iii Not used per Amendment No. 84 600 2.6.03.03 Not used per Amendment No. 84 601 2.6.03.04a 4.a) The IDS provides electrical Testing will be performed on the A simulated test signal exists independence between the Class 1E IDS by providing a simulated at the Class 1E equipment divisions. test signal in each Class 1E identified in Table 2.6.3-1 division. when the assigned Class 1E division is provided the test signal.

602 2.6.03.04b 4.b) The IDS provides electrical Type tests, analyses, or a A report exists and concludes isolation between the non-Class 1E ac combination of type tests and that the battery chargers, power system and the non-Class 1E analyses of the isolation devices regulating transformers, and lighting in the MCR. will be performed. isolation fuses prevent credible faults from propagating into the IDS.

603 2.6.03.04c 4.c) Each IDS 24-hour battery bank Testing of each 24-hour as-built The battery terminal voltage is supplies a dc switchboard bus load for a battery bank will be performed greater than or equal to 210 V period of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> without recharging. by applying a simulated or real after a period of no less than load, or a combination of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> with an equivalent simulated or real loads which load that equals or exceeds the envelope the battery bank design battery bank design duty cycle duty cycle. The test will be capacity.

conducted on a battery bank that has been fully charged and has been connected to a battery charger maintained at 270+/-2 V for a period of no less than 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> prior to the test.

4.d) Each IDS 72-hour battery bank Testing of each 72-hour as-built The battery terminal voltage is supplies a dc switchboard bus load for a battery bank will be performed greater than or equal to 210 V period of 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> without recharging. by applying a simulated or real after a period of no less than load, or a combination of 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> with an equivalent simulated or real loads which load that equals or exceeds the envelope the battery bank design battery bank design duty cycle duty cycle. The test will be capacity.

conducted on a battery bank that has been fully charged and has been connected to a battery charger maintained at 270+/-2 V for a period of no less than 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> prior to the test.

C-340 Amendment No. 112

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 4.e) The IDS spare battery bank Testing of the as-built spare The battery terminal voltage is supplies a dc load equal to or greater battery bank will be performed greater than or equal to 210 V than the most severe switchboard bus by applying a simulated or real after a period with a load and load for the required period without load, or a combination of duration that equals or recharging. simulated or real loads which exceeds the most severe envelope the most severe of the battery bank design duty cycle division batteries design duty capacity.

cycle. The test will be conducted on a battery bank that has been fully charged and has been connected to a battery charger maintained at 270+/-2 V for a period of no less than 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> prior to the test.

4.f) Each IDS 24-hour inverter supplies Testing of each 24-hour as-built Each 24-hour inverter supplies its ac load. inverter will be performed by a line-to-line output voltage of applying a simulated or real 208 +/- 2% V at a frequency of load, or a combination of 60 +/- 0.5% Hz.

simulated or real loads, equivalent to a resistive load greater than 12 kW. The inverter input voltage will be no more than 210 Vdc during the test.

4.g) Each IDS 72-hour inverter Testing of each 72-hour as-built Each 72-hour inverter supplies supplies its ac load. inverter will be performed by a line-to-line output voltage of applying a simulated or real 208 +/- 2% V at a frequency of load, or a combination of 60 +/- 0.5% Hz.

simulated or real loads, equivalent to a resistive load greater than 7 kW. The inverter input voltage will be no more than 210 Vdc during the test.

4.h) Each IDS 24-hour battery charger Testing will be performed by Two PMS input signals exist provides the PMS with two loss-of-ac simulating a loss of input voltage from each 24-hour battery input voltage signals. to each 24-hour battery charger. charger indicating loss of ac input voltage when the loss-of-input voltage condition is simulated.

C-340a Amendment No. 112

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 5.a) Each IDS 24-hour battery charger Testing of each as-built 24-hour Each 24-hour battery charger supplies a dc switchboard bus load battery charger will be provides an output current of while maintaining the corresponding performed by applying a at least 150 A with an output battery charged. simulated or real load, or a voltage in the range 210 to combination of simulated or real 280 V.

loads.

5.b) Each IDS 72-hour battery charger Testing of each 72-hour as-built Each 72-hour battery charger supplies a dc switchboard bus load battery charger will be provides an output current of while maintaining the corresponding performed by applying a at least 125 A with an output battery charged. simulated or real load, or a voltage in the range 210 to combination of simulated or real 280 V.

loads.

5.c) Each IDS regulating transformer Testing of each as-built Each regulating transformer supplies an ac load when powered from regulating transformer will be supplies a line-to-line output the 480 V MCC. performed by applying a voltage of 208 +/- 2% V.

simulated or real load, or a combination of simulated or real loads, equivalent to a resistive load greater than 30 kW when powered from the 480 V MCC.

6. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.6.3-1 can be retrieved in the retrievability of the safety- identified in Table 2.6.3-1 can MCR. related displays in the MCR. be retrieved in the MCR.
11. Displays of the parameters Inspection will be performed for Displays identified in Table identified in Table 2.6.3-2 can be retrievability of the displays 2.6.3-2 can be retrieved in the retrieved in the MCR. identified in Table 2.6.3-2 in the MCR.

MCR.

C-340b Amendment No. 112

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 604 2.6.03.04d Not used per Amendment No. 112 605 2.6.03.04e Not used per Amendment No. 112 606 2.6.03.04f Not used per Amendment No. 112 607 2.6.03.04g Not used per Amendment No. 112 C-341 Amendment No. 112

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 608 2.6.03.04h Not used per Amendment No. 112 609 2.6.03.04i 4.i) The IDS supplies an operating Testing will be performed by The motor starter input voltage at the terminals of the Class 1E stroking each specified motor- terminal voltage is greater motor operated valves identified in operated valve and measuring than or equal 200 Vdc with subsections 2.1.2, 2.2.1, 2.2.2, 2.2.3, the terminal voltage at the motor the motor operating.

2.2.4, 2.3.2, 2.3.6, and 2.7.1 that is starter input terminals with the greater than or equal to the minimum motor operating. The battery specified voltage. terminal voltage will be no more than 210 Vdc during the test.

876 2.6.03.04j 4.j) The IDS provides electrical Type tests, analyses, or a A report exists and concludes isolation between the non- Class 1E combination of type tests and that the battery monitor fuse battery monitors and the Class 1E analyses of the isolation devices isolation panels prevent battery banks. will be performed. credible faults from propagating into the Class 1E portions of the IDS.

610 2.6.03.05a Not used per Amendment No. 112 611 2.6.03.05b Not used per Amendment No. 112 612 2.6.03.05c Not used per Amendment No. 112 613 2.6.03.05d.i 5.d) The IDS Divisions B and C Inspection of the as-built system i) Ancillary diesel generator 1 regulating transformers supply their will be performed. is electrically connected to post-72-hour ac loads when powered regulating transformer from an ancillary diesel generator. IDSC-DT-1 Inspection of the as-built system ii) Ancillary diesel generator 2 will be performed. is electrically connected to regulating transformer IDSB-DT-1.

C-342 Amendment No. 112

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 614 2.6.03.05d.ii Not used per Amendment No. 112 615 2.6.03.06 Not used per Amendment No. 112 616 2.6.03.07 7. The IDS dc battery fuses and battery Analyses for the as-built IDS dc Analyses for the as-built IDS charger circuit breakers, and dc electrical distribution system to dc electrical distribution distribution panels, MCCs, and their determine the capacities of the system exist and conclude that circuit breakers and fuses, are sized to battery fuses and battery charger the capacities of as-built IDS supply their load requirements. circuit breakers, and dc battery fuses and battery distribution panels, MCCs, and charger circuit breakers, and their circuit breakers and fuses, dc distribution panels, MCCs, will be performed. and their circuit breakers and fuses, as determined by their nameplate ratings, exceed their analyzed load requirements.

8. Circuit breakers and fuses in IDS Analyses for the as-built IDS dc Analyses for the as-built IDS battery, battery charger, dc distribution electrical distribution system to dc electrical distribution panel, and MCC circuits are rated to determine fault currents will be system exist and conclude that interrupt fault currents. performed. the analyzed fault currents do not exceed the interrupt capacity of circuit breakers and fuses in the battery, battery charger, dc distribution panel, and MCC circuits, as determined by their nameplate ratings.
9. The IDS batteries, battery chargers, Analyses for the as-built IDS dc Analyses for the as-built IDS dc distribution panels, and MCCs are electrical distribution system to dc electrical distribution rated to withstand fault currents for the determine fault currents will be system exist and conclude that time required to clear the fault from its performed. the fault current capacities of power source. as-built IDS batteries, battery chargers, dc distribution panels, and MCCs, as determined by manufacturers ratings, exceed their analyzed fault currents for the time required to clear the fault from its power source as determined by the circuit interrupting device coordination analyses.

C-343 Amendment No. 112

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria

10. The IDS electrical distribution Analyses for the as-built IDS dc Analyses for the as-built IDS system cables are rated to withstand electrical distribution system to dc electrical distribution fault currents for the time required to determine fault currents will be system exist and conclude that clear the fault from its power source. performed. the IDS dc electrical distribution system cables will withstand the analyzed fault currents, as determined by manufacturers ratings, for the time required to clear the fault from its power source as determined by the circuit interrupting device coordination analyses.

617 2.6.03.08 Not used per Amendment No. 112 618 2.6.03.09 Not used per Amendment No. 112 C-343a Amendment No. 112

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 619 2.6.03.10 Not used per Amendment No. 112 620 2.6.03.11 Not used per Amendment No. 112 Table 2.6.3-4 Component Name Tag No. Component Location Division A 250 Vdc 24-Hour Battery Bank IDSA-DB-1 Auxiliary Building Division B 250 Vdc 24-Hour Battery Bank 1 IDSB-DB-1 Auxiliary Building Division B 250 Vdc 72-Hour Battery Bank 2 IDSB-DB-2 Auxiliary Building Division C 250 Vdc 24-Hour Battery Bank 1 IDSC-DB-1 Auxiliary Building Division C 250 Vdc 72-Hour Battery Bank 2 IDSC-DB-2 Auxiliary Building Division D 250 Vdc 24-Hour Battery Bank IDSD-DB-1 Auxiliary Building Spare 250 Vdc Battery Bank IDSS-DB-1 Auxiliary Building Division A 24-Hour Battery Charger 1 IDSA-DC-1 Auxiliary Building Division B 24-Hour Battery Charger 1 IDSB-DC-1 Auxiliary Building Division B 72-Hour Battery Charger 2 IDSB-DC-2 Auxiliary Building Division C 24-Hour Battery Charger 1 IDSC-DC-1 Auxiliary Building Division C 72-Hour Battery Charger 2 IDSC-DC-2 Auxiliary Building Division D 24-Hour Battery Charger 1 IDSD-DC-1 Auxiliary Building Spare Battery Charger 1 IDSS-DC-1 Auxiliary Building Division A 250 Vdc Distribution Panel IDSA-DD-1 Auxiliary Building C-344 Amendment No. 112

Table 2.6.4-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 622 2.6.04.02a 2.a) On loss of power to a 6900 volt Tests on the as-built ZOS system Each as-built diesel generator diesel-backed bus, the associated diesel will be conducted by providing a automatically starts on generator automatically starts and simulated loss-of-voltage signal. receiving a simulated loss-of-produces ac power at rated voltage and The starting air supply receiver voltage signal and attains a frequency. The source circuit breakers will not be replenished during voltage of 6900 + 10% V and and bus load circuit breakers are the test. frequency 60 + 5% Hz after opened, and the generator is connected the start signal is initiated and to the bus. opens ac power system breakers on the associated 6900 V bus.

2.b) Each diesel generator unit is sized Each diesel generator will be Each diesel generator provides to supply power to the selected operated with a load of 4000 kW power to the load with a nonsafety-related electrical or greater and a power factor generator terminal voltage of components. between 0.9 and 1.0 for a time 6900 +/- 10% V and a period required to reach engine frequency of 60 + 5% Hz.

temperature equilibrium plus 2.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br />.

3. Displays of diesel generator status Inspection will be performed for Displays of diesel generator (running/not running) and electrical retrievability of the displays in status and electrical output output power (watts) can be retrieved in the MCR. power can be retrieved in the the MCR. MCR.
4. Controls exist in the MCR to start A test will be performed to Controls in the MCR operate and stop each diesel generator. verify that controls in the MCR to start and stop each diesel can start and stop each diesel generator.

generator.

623 2.6.04.02b Not used per Amendment No. 112 624 2.6.04.02c 2.c) Automatic-sequence loads are An actual or simulated signal is The load sequencer initiates a sequentially loaded on the associated initiated to start the load closure signal within buses. sequencer operation. Output +/-5 seconds of the set intervals signals will be monitored to to connect the loads.

determine the operability of the load sequencer. Time measurements are taken to determine the load stepping intervals.

625 2.6.04.03 Not used per Amendment No. 112 626 2.6.04.04 Not used per Amendment No. 112 C-352 Amendment No. 112

Table 2.6.4-2 Component Name Tag No. Component Location Onsite Diesel Generator A Package ZOS-MS-05A Diesel Generator Building Onsite Diesel Generator B Package ZOS-MS-05B Diesel Generator Building C-352a Amendment No. 112

2.6.5 Lighting System Design Description The lighting system (ELS) provides the normal and emergency lighting in the main control room (MCR) and at the remote shutdown workstation (RSW).

1. The functional arrangement of the ELS is as described in the Design Description of this Section 2.6.5.
2. The ELS has six groups of emergency lighting fixtures located in the MCR and at the RSW.

Each group is powered by one of the Class 1E inverters. The ELS has four groups of panel lighting fixtures located on or near safety panels in the MCR. Each group is powered by one of the Class 1E inverters in Divisions B and C (one 24-hour and one 72-hour inverter in each Division).

3. The lighting fixtures located in the MCR utilize seismic supports.
4. The panel lighting circuits are classified as associated and treated as Class 1E. These lighting circuits are routed with the Divisions B and C Class 1E circuits. Separation is provided between ELS associated divisions and between associated divisions and non-Class 1E cable.
5. The normal lighting can provide 50 foot candles at the safety panel and at the workstations in the MCR and at the RSW.
6. The emergency lighting can provide 10 foot candles at the safety panel and at the workstations in the MCR and at the RSW.

Table 2.6.5-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 627 2.6.05.01 Not used per Amendment No. 84 628 2.6.05.02.i Not used per Amendment No. 112 C-353 Amendment No. 112

Table 2.6.5-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 629 2.6.05.02.ii 2. The ELS has six groups of i) Inspection of the as-built i) The as-built ELS has six emergency lighting fixtures located in system will be performed. groups of emergency lighting the MCR and at the RSW. Each group fixtures located in the MCR is powered by one of the Class 1E and at the RSW. The ELS has inverters. The ELS has four groups of four groups of panel lighting panel lighting fixtures located on or fixtures located on or near near safety panels in the MCR. Each safety panels in the MCR.

group is powered by one of the Class 1E inverters in Divisions B and C (one 24-hour and one 72-hour inverter in each Division).

ii) Testing of the as-built system ii) Each of the six as-built will be performed using one emergency lighting groups is Class 1E inverter at a time. supplied power from its respective Class 1E inverter and each of the four as-built panel lighting groups is supplied power from its respective Class 1E inverter.

5. The normal lighting can provide 50 i) Testing of the as-built normal i) When adjusted for foot candles at the safety panel and at lighting in the MCR will be maximum illumination and the workstations in the MCR and at the performed. powered by the main ac power RSW. system, the normal lighting in the MCR provides at least 50 foot candles at the safety panel and at the workstations.

ii) Testing of the as-built normal ii) When adjusted for lighting at the RSW will be maximum illumination and performed. powered by the main ac power system, the normal lighting in the RSW provides at least 50 foot candles at the safety panel and at the workstations.

6. The emergency lighting can provide i) Testing of the as-built i) When adjusted for 10 foot candles at the safety panel and emergency lighting in the MCR maximum illumination and at the workstations in the MCR and at will be performed. powered by the six Class 1E the RSW. inverters, the emergency lighting in the MCR provides at least 10 foot candles at the safety panel and at the workstations.

C-354 Amendment No. 112

Table 2.6.5-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria ii) Testing of the as-built ii) When adjusted for emergency lighting at the RSW maximum illumination and will be performed. powered by the six Class 1E inverters, the emergency lighting provides at least 10 foot candles at the RSW.

630 2.6.05.03.i 3. The lighting fixtures located in the i) Inspection will be performed i) The lighting fixtures MCR utilize seismic supports. to verify that the lighting fixtures located in the MCR are located in the MCR are located located on the Nuclear Island.

on the Nuclear Island.

ii) Analysis of seismic supports ii) A report exists and will be performed. concludes that the seismic supports can withstand seismic design basis loads.

631 2.6.05.03.ii Not used per Amendment No. 85 632 2.6.05.04 Not used per Amendment No. 85 633 2.6.05.05.i Not used per Amendment No. 112 634 2.6.05.05.ii Not used per Amendment No. 112 635 2.6.05.06.i Not used per Amendment No. 112 636 2.6.05.06.ii Not used per Amendment No. 112 2.6.6 Grounding and Lightning Protection System Design Description The grounding and lightning protection system (EGS) provides electrical grounding for instrumentation grounding, equipment grounding, and lightning protection during normal and off-normal conditions.

1. The EGS provides an electrical grounding system for: (1) instrument/computer grounding; (2) electrical system grounding of the neutral points of the main generator, main step-up transformers, auxiliary transformers, load center transformers, and onsite standby diesel generators; and (3) equipment grounding of equipment enclosures, metal structures, metallic tanks, ground bus of switchgear assemblies, load centers, motor control centers, and control cabinets. Lightning protection is provided for exposed structures and buildings housing safety-related and fire protection equipment. Each grounding system and lightning protection system is grounded to the station grounding grid.

C-355 Amendment No. 112

Table 2.6.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 637 2.6.06.01.i 1. The EGS provides an electrical i) An inspection for the i) A connection exists grounding system for: instrument/computer grounding between the (1) instrument/computer grounding; system connection to the station instrument/computer (2) electrical system grounding of the grounding grid will be grounding system and the neutral points of the main generator, performed. station grounding grid.

main step-up transformers, auxiliary transformers, load center transformers, auxiliary and onsite standby diesel generators; and (3) equipment grounding of equipment enclosures, metal structures, metallic tanks, ground bus of switchgear assemblies, load centers, motor control centers, and control cabinets. Lightning protection is provided for exposed structures and buildings housing safety-related and fire protection equipment. Each grounding system and lightning protection system is grounded to the station grounding grid.

ii) An inspection for the ii) A connection exists electrical system grounding between the electrical system connection to the station grounding and the station grounding grid will be grounding grid.

performed.

iii) An inspection for the iii) A connection exists equipment grounding system between the equipment connection to the station grounding system and the grounding grid will be station grounding grid.

performed.

iv) An inspection for the iv) A connection exists lightning protection system between the lightning connection to the station protection system and the grounding grid will be station grounding grid.

performed.

638 2.6.06.01.ii Not used per Amendment No. 112 C-356 Amendment No. 112

Table 2.6.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 639 2.6.06.01.iii Not used per Amendment No. 112 640 2.6.06.01.iv Not used per Amendment No. 112 2.6.7 Special Process Heat Tracing System No entry for this system.

C-357 Amendment No. 112

Table 2.6.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 643 2.6.09.04 Not used per Amendment No. 84 644 2.6.09.05a 5.a) Security alarm annunciation Test, inspection, or a combination Security alarm annunciation and and video assessment of test and inspections of the video assessment information is information is displayed installed systems will be displayed concurrently in the concurrently in the central alarm performed. central alarm station and the station and the secondary alarm secondary alarm station, and the station, and the video image video image recording with real recording with real time time playback capability provides playback capability can provide assessment of activities before and assessment of activities before after alarm annunciation within the and after each alarm perimeter barrier.

annunciation within the perimeter area barrier.

15.b) Intrusion detection and Tests will be performed on The intrusion detection system assessment systems concurrently intrusion detection and assessment concurrently provides visual provide visual displays and equipment. displays and audible annunciations audible annunciation of alarms of alarms in both the central and in the central and secondary secondary alarm stations.

alarm stations.

645 2.6.09.05b 5.b) The central and secondary Inspections of the central and The central and secondary alarm alarm stations are located inside secondary alarm stations will be stations are located inside the the protected area and the performed. protected area and the interior of interior of each alarm station is each alarm station is not visible not visible from the perimeter of from the perimeter of the protected the protected area. area.

646 2.6.09.05c 5.c) The central and secondary Inspections and/or analysis of the The central and secondary alarm alarm stations are designed and central and secondary alarm stations are designed and equipped equipped such that, in the event station will be performed. such that, in the event of a single of a single act, in accordance act, in accordance with the design with the design basis threat of basis threat of radiological radiological sabotage, the design sabotage, equipment needed to enables the survivability of maintain the functional capability equipment needed to maintain of either alarm station to detect the functional capability of and assess alarms and either alarm station to detect and communicate with onsite and assess alarms and communicate offsite response personnel exists.

with onsite and offsite response personnel.

647 2.6.09.06 6. The vehicle barrier system is Inspections and analysis will be The vehicle barrier system will installed and located at the performed for the vehicle barrier protect against the DBT vehicle necessary stand-off distance to system. bombs based upon the stand-off protect against the DBT vehicle distance of the system.

bombs.

648 2.6.09.07a Not used per Amendment No. 112 C-360 Amendment No. 112

Table 2.6.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 649 2.6.09.07b Not used per Amendment No. 112 650 2.6.09.08 8. Isolation zones and exterior Inspection of the illumination in The illumination in isolation zones areas within the protected area the isolation zones and external and exterior areas within the are provided with illumination to areas of the protected area will be protected area is 0.2 foot candles permit observation of abnormal performed. measured horizontally at ground presence or activity of persons or level or, alternatively, sufficient to vehicles. permit observation.

651 2.6.09.09 Not used per Amendment No. 112

10. Not used
11. Not used
12. Not used 652 2.6.09.13a 13.a) The central and secondary Tests, inspections, or a The central and secondary alarm alarm stations have conventional combination of tests and stations are equipped with (landline) telephone service with inspections of the central and conventional (landline) telephone the main control room and local secondary alarm stations service with the main control room law enforcement authorities. conventional telephone services and local law enforcement will be performed. authorities.

13.b) The central and secondary Tests, inspections, or a The central and secondary alarm alarm stations are capable of combination of tests and stations are equipped with the continuous communication with inspections of the central and capability to continuously security personnel. secondary alarm stations communicate with security continuous communication officers, watchmen, armed capabilities will be performed. response individuals, or any security personnel that have responsibilities during a contingency event.

653 2.6.09.13b Not used per Amendment No. 112 654 2.6.09.13c 13.c) Non-portable Tests, inspections, or a Non-portable communication communication equipment in the combination of tests and devices (including conventional central and secondary alarm inspections of the non-portable telephone systems) in the central stations remains operable from communications equipment will and secondary alarm stations are an independent power source in be performed. wired to an independent power the event of loss of normal supply that enables the system to power. remain operable in the event of loss of normal power.

14. Not used.

C-361 Amendment No. 112

Table 2.6.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 655 2.6.09.15a 15.a) Security alarm devices, A test will be performed to verify A report exists and concludes that including transmission lines to that security alarms, including security alarm devices, including annunciators, are tamper transmission lines to annunciators, transmission lines to annunciators, indicating and self-checking are tamper indicating and are tamper indicating and (e.g., an automatic indication is self-checking (e.g., an automatic self-checking (e.g., an automatic provided when failure of the indication is provided when failure indication is provided when failure alarm system or a component of the alarm system or a of the alarm system or a occurs, or when on standby component occurs, or when on component occurs, or when the power). Alarm annunciation standby power) and that alarm system is on standby power) and shall indicate the type of alarm annunciation indicates the type of that alarm annunciation indicates (e.g., intrusion alarms and alarm (e.g., intrusion alarms and the type of alarm (e.g., intrusion emergency exit alarm) and emergency exit alarms) and alarms and emergency exit alarms) location. location. and location.

16. Equipment exists to record Test, analysis, or a combination of A report exists and concludes that onsite security alarm test and analysis will be performed equipment is capable of recording annunciation, including the to ensure that equipment is each onsite security alarm location of the alarm, false capable of recording each onsite annunciation, including the alarm, alarm check, and tamper security alarm annunciation, location of the alarm, false alarm, indication; and the type of alarm, including the location of the alarm, alarm check, and tamper location, alarm circuit, date, and false alarm, alarm check, and indication; and the type of alarm, time. tamper indication; and the type of location, alarm circuit, date, and alarm, location, alarm circuit, date, time.

and time.

656 2.6.09.15b Not used per Amendment No. 112 657 2.6.09.16 Not used per Amendment No. 112 C.2.6.9 Physical Security Table C.2.6.9-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 658 C.2.6.09.01 1. The external walls, doors, ceiling, Type test, analysis, or a The external walls, doors, and floors in the location within which combination of type test and ceilings, and floors in the the last access control function for analysis will be performed for location within which the last access to the protected area is the external walls, doors, access control function for performed are bullet-resistant to at least ceilings, and floors in the access to the protected area is Underwriters Laboratory Ballistic location within which the last performed are bullet-resistant Standard 752, level 4. access control function for to at least Underwriters access to the protected area is Laboratory Ballistic performed. Standard 752, level 4.

C-362 Amendment No. 112

Table C.2.6.9-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 659 C.2.6.09.02 2. Physical barriers for the protected An inspection of the protected Physical barriers at the area perimeter are not part of vital area area perimeter barrier will be perimeter of the protected area barriers. performed. are separated from any other barrier designated as a vital area barrier.

660 C.2.6.09.03a 3.a) Isolation zones exist in outdoor Inspections will be performed of Isolation zones exist in areas adjacent to the physical barrier at the isolation zones in outdoor outdoor areas adjacent to the the perimeter of the protected area that areas adjacent to the physical physical barrier at the allows 20 feet of observation on either barrier at the perimeter of the perimeter of the protected area side of the barrier. Where permanent protected area. and allow 20 feet of buildings do not allow a 20-foot observation and assessment of observation distance on the inside of the the activities of people on protected area, the building walls are either side of the barrier.

immediately adjacent to, or an integral Where permanent buildings part of, the protected area barrier. do not allow a 20-foot observation and assessment distance on the inside of the protected area, the building walls are immediately adjacent to, or an integral part of, the protected area barrier and the 20-foot observation and assessment distance does not apply.

661 C.2.6.09.03b 3.b) The isolation zones are monitored Inspections will be performed of The isolation zones are with intrusion detection equipment that the intrusion detection equipped with intrusion provides the capability to detect and equipment within the isolation detection equipment that assess unauthorized persons. zones. provides the capability to detect and assess unauthorized persons.

4. The intrusion detection and Tests, inspections or a The intrusion detection and assessment equipment at the protected combination of tests and assessment equipment at the area perimeter: inspections of the intrusion protected area perimeter:

a) detects penetration or attempted detection and assessment a) detects penetration or penetration of the protected area equipment at the protected area attempted penetration of barrier and concurrently alarms in perimeter and its uninterruptible the protected area barrier both the Central Alarm Station and power supply will be performed. and concurrently alarms in Secondary Alarm Station; the Central Alarm Station and Secondary Alarm Station; b) remains operable from an Tests, inspections or a b) remains operable from an uninterruptible power supply in the combination of tests and uninterruptible power event of the loss of normal power. inspections of the intrusion supply in the event of the detection and assessment loss of normal power.

equipment at the protected area perimeter and its uninterruptible power supply will be performed.

662 C.2.6.09.04a Not used per Amendment No. 112 C-363 Amendment No. 112

Table C.2.6.9-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 663 C.2.6.09.04b Not used per Amendment No. 112 664 C.2.6.09.05a 5. Access control points are established Tests, inspections, or The access control points for to: combination of tests and the protected area:

a) control personnel and vehicle inspections of installed systems a) are configured to control access into the protected area. and equipment at the access personnel and vehicle control points to the protected access.

area will be performed.

b) detect firearms, explosives, and Tests, inspections, or b) include detection incendiary devices at the protected combination of tests and equipment that is capable area personnel access points. inspections of installed systems of detecting firearms, and equipment at the access incendiary devices, and control points to the protected explosives at the area will be performed. protected area personnel access points.

665 C.2.6.09.05b Not used per Amendment No. 112 666 C.2.6.09.06 6. An access control system with A test of the access control The access authorization numbered picture badges is installed for system with numbered picture system with numbered picture use by individuals who are authorized badges will be performed. badges can identify and access to protected areas and vital areas authorize protected area and without escort. vital area access only to those personnel with unescorted access authorization.

667 C.2.6.09.07 7. Access to vital equipment physical Inspection will be performed to Vital equipment is located barriers requires passage through the confirm that access to vital within a protected area such protected area perimeter barrier. equipment physical barriers that access to vital equipment requires passage through the physical barriers requires protected area perimeter barrier. passage through the protected area perimeter barrier.

7.a) Vital equipment is located only Inspection will be performed to All vital equipment is located within a vital area. confirm that vital equipment is only within a vital area.

located within a vital area 7.b) Access to vital equipment requires Inspection will be performed to Vital equipment is located passage through the vital area barrier. confirm that access to vital within a protected area such equipment requires passage that access to vital equipment through the vital area barrier. requires passage through the vital area barrier.

C-364 Amendment No. 112

Table C.2.6.9-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 668 C.2.6.09.08a 8.a) Penetrations through the protected Inspections will be performed of Penetrations and openings area barrier are secured and monitored. penetrations through the through the protected area protected area barrier. barrier are secured and monitored.

8.b) Unattended openings (such as Inspections will be performed of Unattended openings (such as underground pathways) that intersect unattended openings that underground pathways) that the protected area boundary or vital area intersect the protected area intersect the protected area boundary will be protected by a boundary or vital area boundary. boundary or vital area physical barrier and monitored by boundary are protected by a intrusion detection equipment or physical barrier and monitored provided surveillance at a frequency by intrusion detection sufficient to detect exploitation. equipment or provided surveillance at a frequency sufficient to detect exploitation.

C-364a Amendment No. 112

Table C.2.6.9-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 669 C.2.6.09.08b Not used per Amendment No. 112 670 C.2.6.09.09 9. Emergency exits through the Tests, inspections, or a Emergency exits through the protected area perimeter are alarmed combination of tests and protected area perimeter are and secured with locking devices to inspections of emergency exits alarmed and secured by allow for emergency egress. through the protected area locking devices that allow perimeter will be performed. prompt egress during an emergency.

9. Emergency exits through the vital Test, inspection, or a The emergency exits through area boundaries are locked, alarmed, combination of tests and the vital area boundaries are and equipped with a crash bar to allow inspections of the emergency locked, alarmed, and equipped for emergency egress. exits through the vital area with a crash bar to allow for boundaries will be performed. emergency egress.

2.6.10 Main Generation System No entry. Covered in Section 2.6.1, Main ac Power System.

2.6.11 Excitation and Voltage Regulation System No entry for this system.

C.2.6.12 Transmission Switchyard and Offsite Power System Table C.2.6.12-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 671 C.2.6.12.01 1. A minimum of one offsite circuit Inspections of the as-built offsite At least one offsite circuit is supplies electric power from the circuit will be performed. provided from the transmission network to the transmission switchyard interface with the onsite alternating interface to the interface with current (ac) power system. the onsite ac power system.

672 C.2.6.12.02 2. Each offsite power circuit Analyses of the offsite power A report exists and concludes interfacing with the onsite ac power system will be performed to that each as-built offsite system is adequately rated to evaluate the as-built ratings of circuit is rated to supply the supply assumed loads during each offsite circuit interfacing load assumptions during normal, abnormal and accident with the onsite ac power system normal, abnormal and conditions. against the load assumptions. accident conditions.

C-365 Amendment No. 112

Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 688 2.7.01.06b Not used per Amendment No. 84 689 2.7.01.07 Not used per Amendment No. 84 690 2.7.01.08a Not used per Amendment No. 84 691 2.7.01.08b Not used per Amendment No. 84 692 2.7.01.08c Not used per Amendment No. 84 693 2.7.01.08d Not used per Amendment No. 112 694 2.7.01.09 Not used per Amendment No. 112 695 2.7.01.10a Not used per Amendment No. 112 696 2.7.01.10b Not used per Amendment No. 112 697 2.7.01.11 Not used per Amendment No. 112 C-373 Amendment No. 112

Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 698 2.7.01.12 Not used per Amendment No. 112 699 2.7.01.13 Not used per Amendment No. 112 700 2.7.01.14 8.d) The VBS provides ventilation Testing will be performed on the The fans start and run.

cooling via the ancillary equipment in components in Table 2.7.1-3.

Table 2.7.1-3 to the MCR and the division B&C Class 1E I&C rooms.

9. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 2.7.1-1 can be retrieved in the retrievability of the safety- identified in Table 2.7.1-1 can MCR. related displays in the MCR. be retrieved in the MCR.

10.a) Controls exist in the MCR to Stroke testing will be performed Controls in the MCR operate cause the remotely operated valves on the remotely operated valves to cause the remotely operated identified in Table 2.7.1-1 to perform identified in Table 2.7.1-1 using valves identified in Table their active functions. the controls in the MCR. 2.7.1-1 to perform their active functions.

10.b) The valves identified in Table Testing will be performed using The valves identified in Table 2.7.1-1 as having PMS control perform real or simulated signals into the 2.7.1-1 as having PMS control their active safety function after PMS. perform their active safety receiving a signal from the PMS. function after receiving a signal from PMS.

11. After loss of motive power, the Testing of the remotely operated Upon loss of motive power, remotely operated valves identified in valves will be performed under each remotely operated valves Table 2.7.1-1 assume the indicated loss the conditions of loss of motive identified in Table 2.7.1-1 of motive power position. power. assumes the indicated loss of motive power position.
12. 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 2.7.1-3 to cause the components listed 2.7.1-3 to perform the listed function. using controls in the MCR. in Table 2.7.1-3 to perform the listed functions.
13. Displays of the parameters Inspection will be performed for The displays identified in identified in Table 2.7.1-3 can be retrievability of the parameters Table 2.7.1-3 can be retrieved retrieved in the MCR. in the MCR. in the MCR.
14. The background noise level in the The as-built VBS will be The background noise level in MCR and RSR does not exceed operated, and background noise the MCR and RSR does not 65 dB(A) when the VBS is operating. levels in the MCR and RSR will exceed 65 dB(A) when the be measured. VBS is operating.

C-374 Amendment No. 112

Table 2.7.1-5 Component Name Tag No. Component Location Supplemental Air Filtration Unit A VBS-MS-01A Auxiliary Building Supplemental Air Filtration Unit B VBS-MS-01B Auxiliary Building MCR/CSA Supply Air Handling Unit A VBS-MS-02A Auxiliary Building MCR/CSA Supply Air Handling Unit B VBS-MS-02B Annex Building Division "A" and "C" Class 1E Electrical Room VBS-MS-03A Auxiliary Building AHU A Division "A" and "C" Class 1E Electrical Room VBS-MS-03C Auxiliary Building AHU C Division "B" and "D" Class 1E Electrical Room VBS-MS-03B Auxiliary Building AHU B Division "B" and "D" Class 1E Electrical Room VBS-MS-03D Auxiliary Building AHU D MCR Toilet Exhaust Fan VBS-MA-04 Auxiliary Building Division "A&C" Class 1E Battery Room Exhaust VBS-MA-07A Auxiliary Building Fan Division "A&C" Class 1E Battery Room Exhaust VBS-MA-07C Auxiliary Building Fan Division "B&D" Class 1E Battery Room Exhaust VBS-MA-07B Auxiliary Building Fan C-374a Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built VWS conforms VWS is as described in the Design will be performed. with the functional Description of this Section 2.7.2. arrangement as described in the Design Description of this Section 2.7.2.

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. 112

Table 2.7.2-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 704 2.7.02.03b 3.b) The VWS air-cooled chillers Inspection will be performed for A report exists and concludes transfer heat from the VWS to the the existence of a report that that the heat transfer rate of surrounding atmosphere. determines the heat transfer each air-cooled chiller is capability of each air-cooled greater than or equal to chiller. 230 tons.

705 2.7.02.04 Not used per Amendment No. 112 706 2.7.02.05 Not used per Amendment No. 112 Table 2.7.2-3 Component Name Tag No. Component Location Water Chiller Pump A VWS-MP-01A Turbine Building Water Chiller Pump B VWS-MP-01B Turbine Building Air Cooled Chiller Pump 2 VWS-MP-02 Auxiliary Building Air Cooled Chiller Pump 3 VWS-MP-03 Annex Building Water Chiller A VWS-MS-01A Turbine Building Water Chiller B VWS-MS-01B Turbine Building Air Cooled Chiller 2 VWS-MS-02 Auxiliary Building Air Cooled Chiller 3 VWS-MS-03 Auxiliary Building C-380 Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built VXS conforms VXS is as described in the Design will be performed. with the functional Description of this Section 2.7.3. arrangement described in the Design Description of this Section 2.7.3.

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. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built VZS conforms VZS is as described in the Design will be performed. with the functional Description of this Section 2.7.4. arrangement described in the Design Description of this Section 2.7.4.

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. 112

Table 2.7.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 719 2.7.05.02.i 2. The VAS maintains each building i) Testing will be performed to i) The time average pressure area at a slightly negative pressure confirm that the VAS maintains differential in the served areas relative to the atmosphere or adjacent each building at a slightly of the annex, fuel handling clean plant areas. negative pressure when and radiologically controlled operating all VAS supply AHUs auxiliary buildings as and all VAS exhaust fans. measured by each of the instruments identified in Table 2.7.5-1 is negative.

ii) Testing will be performed to ii) A report exists and confirm the ventilation flow rate concludes that the calculated through the auxiliary building exhaust flow rate based on the fuel handling area when measured flow rates is greater operating all VAS supply AHUs than or equal to 15,300 cfm.

and all VAS exhaust fans.

iii) Testing will be performed to iii) A report exists and confirm the auxiliary building concludes that the calculated radiologically controlled area exhaust flow rate based on the ventilation flow rate when measured flow rates is greater operating all VAS supply AHUs than or equal to 22,500 cfm.

and all VAS exhaust fans.

3. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.7.5-1 can be retrieved in the retrievability of the parameters Table 2.7.5-1 can be retrieved MCR. in the MCR. in the MCR.

720 2.7.05.02.ii Not used per Amendment No. 112 721 2.7.05.02.iii Not used per Amendment No. 112 722 2.7.05.03 Not used per Amendment No. 112 C-394 Amendment No. 112

Table 2.7.5-3 Component Name Tag No. Component Location Auxiliary/Annex Building Supply AHU A VAS-MS-01A Annex Building Auxiliary/Annex Building Supply AHU B VAS-MS-01B Annex Building Fuel Handling Area Supply AHU A VAS-MS-02A Annex Building Fuel Handling Area Supply AHU B VAS-MS-02B Annex Building CVS Pump Room Unit Cooler A VAS-MS-05A Auxiliary Building CVS Pump Room Unit Cooler B VAS-MS-05B Auxiliary Building RNS Pump Room Unit Cooler A VAS-MS-06A Auxiliary Building RNS Pump Room Unit Cooler B VAS-MS-06B Auxiliary Building Auxiliary/Annex Building Exhaust Fan A VAS-MA-02A Auxiliary Building Auxiliary/Annex Building Exhaust Fan B VAS-MA-02B Auxiliary Building C-394a Amendment No. 112

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 1. The functional arrangement of the Inspection of the as-built system The as-built VFS conforms VFS is as described in the Design will be performed. with the functional Description of this Section 2.7.6. arrangement described in the Design Description of this Section 2.7.6.

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. 112

Table 2.7.6-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 726 2.7.06.03.i 3. The VFS provides the intermittent i) Testing will be performed to i) The flow rate measured at flow of outdoor air to purge the confirm that containment supply each fan is greater than or containment atmosphere during normal AHU fan A when operated with equal to 3,600 scfm.

plant operation, and continuous flow containment exhaust fan A during hot or cold plant shutdown provides a flow of outdoor air.

conditions.

ii) Testing will be performed to ii) The flow rate measured at confirm that containment supply each fan is greater than or AHU fan B when operated with equal to 3,600 scfm.

containment exhaust fan B provides a flow of outdoor air.

iii) Inspection will be conducted iii) The nominal line size of the containment purge is 36 in.

discharge line (VFS-L204) penetrating the containment.

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 2.7.6-1 to cause the components listed 2.7.6-1 to perform the listed function. using controls in the MCR. in Table 2.7.6-1 to perform the listed functions.
5. Displays of the parameters identified Inspection will be performed for The displays identified in in Table 2.7.6-1 can be retrieved in the retrievability of the parameters Table 2.7.6-1 can be retrieved MCR. in the MCR. in the MCR.

727 2.7.06.03.ii Not used per Amendment No. 112 C-396a Amendment No. 112

Table 2.7.6-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 728 2.7.06.03.iii Not used per Amendment No. 112 729 2.7.06.04 Not used per Amendment No. 112 730 2.7.06.05 Not used per Amendment No. 112 Table 2.7.6-3 Component Name Tag No. Component Location Containment Air Filtration Supply AHU A VFS-MS-01A Annex Building Containment Air Filtration Supply AHU B VFS-MS-01B Annex Building Containment Air Filtration Exhaust Unit A VFS-MS-02A Annex Building Containment Air Filtration Exhaust Unit B VFS-MS-02B Annex Building C-397 Amendment No. 112

Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 813 3.3.00.08 8. Systems, structures, and Following as-built An as-built Pipe Rupture components identified as essential reconciliation, an inspection will Hazard Analysis Report exists targets are protected from the dynamic be performed of the as-built high and concludes that systems, and environmental effects of and moderate energy pipe structures, and components postulated pipe ruptures. rupture mitigation features for identified as essential targets systems, structures, and can withstand the effects of components identified as postulated pipe rupture essential targets. without loss of required safety function.

814 3.3.00.09 9. The reactor cavity sump has a An inspection of the as-built A report exists and concludes minimum concrete thickness as shown containment building internal that the reactor cavity sump in Table 3.3-5 between the bottom of structures will be performed. has a minimum concrete the sump and the steel containment. thickness as shown on Table 3.3-5 between the bottom of the sump and the steel containment.

815 3.3.00.10.i 10. The shield building roof and PCS i) A test will be performed to i) A report exists and storage tank support and retain the measure the leakage from the concludes that total water flow PCS water sources. The PCS storage PCS storage tank based on from the leak chase collection tank has a stainless steel liner which measuring the water flow out of system does not exceed provides a barrier on the inside the leak chase collection system. 10 gal/hr.

surfaces of the tank. Leak chase channels are provided on the tank boundary liner welds.

C-439 Amendment No. 112

Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 816 3.3.00.10.ii 10. The shield building roof and PCS ii) An inspection of the PCS ii) A report exists and storage tank support and retain the storage tank exterior tank concludes that inspection and PCS water sources. The PCS storage boundary and shield building measurement of the PCS tank has a stainless steel liner which tension ring will be performed storage tank and the tension provides a barrier on the inside before and after filling of the ring structure, before and after surfaces of the tank. Leak chase PCS storage tank to the overflow filling of the tank, shows channels are provided on the tank level. The vertical elevation of structural behavior under boundary liner welds. the shield building roof will be normal loads to be acceptable.

measured at a location at the outer radius of the roof (tension ring) and at a location on the same azimuth at the outer radius of the PCS storage tank before and after filling the PCS storage tank.

iii) An inspection of the PCS iii) A report exists and storage tank exterior tank concludes that there is no boundary and shield building visible water leakage from the tension ring will be performed PCS storage tank through the before and after filling of the concrete and that there is no PCS storage tank to the overflow visible excessive cracking in level. The boundaries of the PCS the boundaries of the PCS storage tank and the shield storage tank and the shield building roof above the tension building roof above the ring will be inspected visually tension ring.

for excessive concrete cracking.

C-439a Amendment No. 112

Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 817 3.3.00.10.iii Not used per Amendment No. 112

11. Deleted 818 3.3.00.12 12. The extended turbine generator An inspection of the as-built The extended axis of the axis intersects the shield building. turbine generator will be turbine generator intersects performed. the shield building.

819 3.3.00.13 13. Separation is provided between An inspection of the separation The minimum horizontal the structural elements of the turbine, of the nuclear island from the clearance above floor annex and radwaste buildings and the annex, radwaste and turbine elevation 100-0 between the nuclear island structure. This building structures will be structural elements of the separation permits horizontal motion performed. The inspection will annex and radwaste buildings of the buildings in the safe shutdown verify the specified horizontal and the nuclear island is earthquake without impact between clearance between structural 4 inches. The minimum structural elements of the buildings. elements of the adjacent horizontal clearance above buildings, consisting of the floor elevation 100-0 reinforced concrete walls and between the structural slabs, structural steel columns elements of the turbine and floor beams. building and the nuclear island is 4 inches.

820 3.3.00.14 14. The external walls, doors, ceiling, Type test, analysis, or a A report exists and concludes and floors in the main control room, combination of type test and that the external walls, doors, the central alarm station, and the analysis will be performed for ceilings, and floors in the secondary alarm station are the external walls, doors, main control room, the central bullet-resistant to at least Underwriters ceilings, and floors in the main alarm station, and the Laboratory Ballistic Standard 752, control room, the central alarm secondary alarm station are level 4. station, and the secondary alarm bullet-resistant to at least station. Underwriters Laboratory Ballistic Standard 752, level 4.

15. Deleted C-440 Amendment No. 112

Table 3.5-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 829 3.5.00.04 Not used per Amendment No. 112 830 3.5.00.05 Not used per Amendment No. 112 831 3.5.00.06 4. Safety-related displays identified in Inspection will be performed for Safety-related displays Table 3.5-1 can be retrieved in the retrievability of the displays in identified in Table 3.5-1 can MCR. the MCR. be retrieved in the MCR.

5. The process radiation monitors listed Inspection for the existence of Each of the monitors listed in in Table 3.5-2 are provided. the monitors will be performed. Table 3.5-2 exists.
6. The effluent radiation monitors listed Inspection for the existence of Each of the monitors listed in in Table 3.5-3 are provided. the monitors will be performed. Table 3.5-3 exists.
7. The airborne radiation monitors listed Inspection for the existence of Each of the monitors listed in in Table 3.5-4 are provided. the monitors will be performed. Table 3.5-4 exists.
8. The area radiation monitors listed in Inspection for the existence of Each of the monitors listed in Table 3.5-5 are provided. the monitors will be performed. Table 3.5-5 exists.

832 3.5.00.07 Not used per Amendment No. 112 833 3.5.00.08 Not used per Amendment No. 112 C-447 Amendment No. 112

Table 3.5-7 Component Component Name Tag No. Location Containment High Range Radiation Monitor PXS-RE160 Containment Containment High Range Radiation Monitor PXS-RE161 Containment Containment High Range Radiation Monitor PXS-RE162 Containment Containment High Range Radiation Monitor PXS-RE163 Containment MCR Radiation Monitoring Package A VBS-RY01A Auxiliary Building MCR Radiation Monitoring Package B VBS-RY01B Auxiliary Building Containment Atmosphere Radiation Monitor (Gaseous) PSS-RE026 Auxiliary Building Containment Atmosphere Radiation Monitor PSS-RE027 Auxiliary Building (particulate, for RCS pressure boundary leakage detection)

Steam Generator Blowdown Radiation Monitor BDS-RE010 Turbine Building Steam Generator Blowdown Radiation Monitor BDS-RE011 Turbine Building Component Cooling Water Radiation Monitor CCS-RE001 Turbine Building Main Steam Line Radiation Monitor SGS-RY026 Auxiliary Building Main Steam Line Radiation Monitor SGS-RY027 Auxiliary Building Service Water Blowdown Radiation Monitor SWS-RE008 Turbine Building C-447a Amendment No. 112

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