ML17320A648

Revised Draft - Combined License for Turkey Point Unit 7

ML17320A648
Person / Time
Site:	Turkey Point
Issue date:	12/05/2017
From:	Office of New Reactors
To:
References
Download: ML17320A648 (47)

Text

12/05/2017 Revised Draft 1

COMBINED LICENSE TURKEY POINT UNIT 7 FLORIDA POWER & LIGHT COMPANY Docket No.52-041 License No. NPF-XXX

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for a combined license (COL) for Turkey Point Unit 7 filed by Florida Power & Light Company (FPL), which incorporates by reference Appendix D to Title 10 of the Code of Federal Regulations (10 CFR) Part 52, complies with the applicable standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.

There is reasonable assurance that the facility will be constructed and will operate in conformity with the license, the provisions of the Act, and the Commission regulations set forth in 10 CFR Chapter I, except as exempted from compliance in Section 2.F below; C.

There is reasonable assurance (i) that the activities authorized by this COL can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the Commission regulations set forth in 10 CFR Chapter I, except as exempted from compliance in Section 2.F below; D.

FPL is technically qualified to engage in the activities authorized by this license in accordance with the Commission regulations set forth in 10 CFR Chapter I. FPL is financially qualified to engage in the activities authorized by this COL in accordance with the Commission regulations set forth in 10 CFR Chapter I; E.

FPL has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements;"

F.

The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; G.

After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering reasonable available alternatives, the issuance of this license subject to the conditions for protection of the environment set forth herein is in accordance with Subpart A of 10 CFR Part 51 and all applicable requirements have been satisfied; and H.

The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this license will be in accordance with the applicable regulations in 10 CFR Parts 30, 40, and 70.

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2.

On the basis of the foregoing findings regarding this facility, COL No. NPF-XXX is hereby issued to FPL (the licensee), to read as follows:

A.

This license applies to Turkey Point Unit 7, a light-water nuclear reactor and associated equipment (the facility), owned by FPL. The facility would be located in unincorporated southeast Miami-Dade County, Florida (FL), approximately 25 miles south of Miami, FL, on an approximately 218-acre area south of the existing Turkey Point Units 3 and 4, and is described in FPL's final safety analysis report (FSAR), as supplemented and amended.

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1)

FPL, pursuant to Sections 103 and 185b. of the Act and 10 CFR Part 52, to construct, possess, use, and operate the facility at the designated location in accordance with the procedures and limitations set forth in this license; (2)

(a) FPL, pursuant to the Act and 10 CFR Part 70, to receive and possess at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and in amounts necessary for reactor operation, described in the FSAR, as supplemented and amended; (b) FPL, pursuant to the Act and 10 CFR Part 70, to use special nuclear material as reactor fuel, after a Commission finding under 10 CFR 52.103(g) has been made, in accordance with the limitations for storage and in amounts necessary for reactor operation, described in the FSAR, as supplemented and amended; (3)

(a) FPL, pursuant to the Act and 10 CFR Parts 30 and 70, to receive, possess, and use, at any time before a Commission finding under 10 CFR 52.103(g), such byproduct and special nuclear material (but not uranium hexafluoride) as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts not exceeding those specified in 10 CFR 30.35(d) and 10 CFR 70.25(d) for establishing decommissioning financial assurance, and not exceeding those specified in 10 CFR 30.72 and 10 CFR 70.22(i)(1);

(b) FPL, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, after a Commission finding under 10 CFR 52.103(g),

any byproduct, source, and special nuclear material (but not uranium hexafluoride) as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts, as necessary; (4)

(a) FPL, pursuant to the Act and 10 CFR Parts 30 and 70, to receive, possess, and use, before a Commission finding under 10 CFR 52.103(g),

in amounts not exceeding those specified in 10 CFR 30.72, any byproduct or special nuclear material (but not uranium hexafluoride) that

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is (1) in unsealed form; (2) on foils or plated surfaces, or (3) sealed in glass, for sample analysis or instrument calibration or other activity associated with radioactive apparatus or components, in amounts not exceeding those specified in 10 CFR 30.35(d) and 10 CFR 70.25(d) for establishing decommissioning financial assurance, and not exceeding those specified in 10 CFR 30.72 and 10 CFR 70.22(i)(1);

(b) FPL, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, after a Commission finding under 10 CFR 52.103(g), in amounts as necessary, any byproduct, source, or special nuclear material (but not uranium hexafluoride) without restriction as to chemical or physical form, for sample analysis or instrument calibration or other activity associated with radioactive apparatus or components; and (5)

FPL, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

The license is subject to, and FPL shall comply with, all applicable provisions of the Act and the rules, regulations, and orders of the Commission, including the conditions set forth in 10 CFR Chapter I, now or hereafter in effect.

D.

The license is subject to, and FPL shall comply with, the conditions specified and incorporated below:

(1)

Changes during Construction (a)

FPL may request use of a preliminary amendment request (PAR) process, for license amendments, at any time before a Commission finding under 10 CFR 52.103(g). To use the PAR process, FPL shall submit a written request to the Office of New Reactors (NRO) in accordance with COL-ISG-025, Changes during Construction under Part 52.

(b)

Before NROs issuance of a written PAR notification, FPL shall submit the license amendment request (LAR). Thereafter, NRO will issue a written PAR notification, setting forth whether FPL may proceed in accordance with the PAR, LAR, and COL-ISG-025. If FPL elects to proceed and the LAR is subsequently denied, FPL shall return the facility to its current licensing basis.

(2)

Pre-operational Testing (a)

FPL shall perform the design-specific pre-operational tests identified below:

1.

In-Containment Refueling Water Storage Tank (IRWST)

Heatup Test (first plant test as identified in AP1000 Design Control Document (DCD), Rev. 19, Section 14.2.9.1.3 Item (h));

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2.

Pressurizer Surge Line Stratification Evaluation (first plant test as identified in AP1000 DCD, Rev. 19, Section 14.2.9.1.7 Item (d));

3.

Reactor Vessel Internals Vibration Testing (first plant test as identified in AP1000 DCD, Rev. 19, Section 14.2.9.1.9);

4.

Core Makeup Tank Heated Recirculation Tests (first three plants test as identified in AP1000 DCD, Rev. 19, Section 14.2.9.1.3 Items (k) and (w)); and

5.

Automatic Depressurization System Blowdown Test (first three plants test as identified in AP1000 DCD, Rev. 19, Section 14.2.9.1.3 Item (s)).

(b)

FPL shall review and evaluate the results of the tests identified in Section 2.D.(2)(a) of this license and confirm that these test results are within the range of acceptable values predicted or otherwise confirm that the tested systems perform their specified functions in accordance with AP1000 DCD Rev. 19, Section 14.2.9.

(c)

FPL shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of the design-specific pre-operational tests identified in Section 2.D.(2)(a) of this license; and (d)

FPL shall notify the Director of NRO, or the Directors designee, in writing, upon the successful completion of all the ITAAC included in Appendix C to this license.

(3)

Nuclear Fuel Loading and Pre-critical Testing (a)

Until the submission of the notification required by Section 2.D.(2)(c) of this license, FPL shall not load fuel into the reactor vessel; (b)

Upon submission of the notification required by Section 2.D.(2)(c) of this license and upon a Commission finding in accordance with 10 CFR 52.103(g) that all the acceptance criteria in the ITAAC in Appendix C to this license are met, FPL is authorized to perform pre-critical tests in accordance with the conditions specified herein; (c)

FPL shall perform the pre-critical tests identified in AP1000 DCD Rev. 19, Section 14.2.10.1; (d)

FPL shall review and evaluate the results of the tests identified in Section 2.D.(3)(c) of this license and confirm that these test results are within the range of acceptable values predicted or otherwise confirm that the tested systems perform their specified

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functions in accordance with AP1000 DCD Rev. 19, Section 14.2.10; and (e)

FPL shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of the pre-critical tests identified in Section 2.D.(3)(c) of this license.

(4)

Initial Criticality and Low-Power Testing (a)

Upon submission of the notification required by Section 2.D.(3)(e) of this license, FPL is authorized to operate the facility at reactor steady-state core power levels not to exceed 5-percent thermal power in accordance with the conditions specified herein; (b)

FPL shall perform the initial criticality and low-power tests identified in AP1000 DCD Rev. 19, Sections 14.2.10.2 and 14.2.10.3, respectively, the Natural Circulation (first plant test) identified in AP1000 DCD Rev. 19, Section 14.2.10.3.6, and the Passive Residual Heat Removal Heat Exchanger (first plant test) identified in AP1000 DCD Rev. 19, Section 14.2.10.3.7; (c)

FPL shall review and evaluate the results of the tests identified in Section 2.D.(4)(b) of this license and confirm that these test results are within the range of acceptable values predicted or otherwise confirm that the tested systems perform their specified functions in accordance with AP1000 DCD Rev. 19, Section 14.2.10.2 and 14.2.10.3; and (d)

FPL shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of initial criticality and low-power tests identified in Section 2.D.(4)(b) of this license, including the design-specific tests identified therein.

(5)

Power Ascension Testing (a)

Upon submission of the notification required by Section 2.D.(4)(d) of this license, FPL is authorized to operate the facility at reactor steady-state core power levels not to exceed 100-percent thermal power in accordance with the conditions specified herein, but only for the purpose of performing power ascension testing; (b)

FPL shall perform the power ascension tests identified in the AP1000 DCD Rev. 19, Section 14.2.10.4, the Rod Cluster Control Assembly Out of Bank Measurements (first plant test) identified in AP1000 DCD, Rev. 19, Section 14.2.10.4.6, and the Load Follow Demonstration (first plant test) identified in AP1000 DCD, Rev. 19, Section 14.2.10.4.22; (c)

FPL shall review and evaluate the results of the tests identified in Section 2.D.(5)(b) of this license and confirm that these test results are within the range of acceptable values predicted or

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otherwise confirm that the tested systems perform their specified functions in accordance with AP1000 DCD Rev.19, Section 14.2.10.4; and (d)

FPL shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of power ascension tests identified in Section 2.D.(5)(b) of this license, including the design-specific tests identified therein.

(6)

Maximum Power Level Upon submission of the notification required by Section 2.D.(5)(d) of this license, FPL is authorized to operate the facility at steady state reactor core power levels not to exceed 3400 MW thermal (100-percent thermal power), as described in the FSAR, in accordance with the conditions specified herein.

(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, FPL shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(b)

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

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

(8)

Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively, of this license 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 FPL shall implement the programs or portions of programs identified below, on or before the date FPL achieves the following milestones.

(a)

Environmental Qualification Program implemented before initial fuel load;

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(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 of byproduct or special nuclear materials that are not fuel (excluding exempt quantities as described in 10 CFR 30.18);

2.

The fire protection measures in accordance with RG 1.189 for areas containing new fuel (including adjacent areas where a fire could affect the new fuel) implemented before receipt of fuel onsite;

3.

All fire protection program features implemented before initial fuel load; (f)

Standard Radiological Effluent Controls implemented before initial fuel load; (g)

Offsite Dose Calculation Manual implemented before initial fuel load; (h)

Radiological Environmental Monitoring Program implemented before initial fuel load; (i)

Process Control Program implemented before initial fuel load; (j)

Radiation Protection Program (RPP) (including the ALARA principle) or applicable portions as identified in FSAR Section 12.5 thereof:

1.

RPP features (including the ALARA principle) applicable to receipt of by-product, source, or special nuclear materials (excluding exempt quantities as described in 10 CFR 30.18) implemented before initial receipt of such materials;

2.

RPP features (including the ALARA principle) applicable to new fuel implemented before receipt of initial fuel on site;

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3.

All other RPP features (including the ALARA principle) except for those applicable to control radioactive waste shipment implemented before initial fuel load;

4.

RPP features (including the ALARA principle) applicable to radioactive waste shipment implemented before first shipment of radioactive waste; (k)

Reactor Operator Training Program implemented 18 months before the scheduled date of initial fuel load; (l)

Motor-Operated Valve Testing Program implemented before initial fuel load; (m)

Initial Test Program

1.

Construction Test Program implemented before the first construction test;

2.

Preoperational Test Program implemented before the first preoperational test; and

3.

Startup Test Program implemented before initial fuel load; (n)

Special Nuclear Material Control and Accounting Program implemented before initial receipt of special nuclear material; and (o)

Special Nuclear Material Physical Protection Program implemented before initial receipt of special nuclear material on site.

(11)

Operational Program Implementation Schedule No later than 12 months after issuance of the COL, FPL shall submit to the Director of NRO, or the Directors designee, a schedule for implementation of the operational programs listed in FSAR Table 13.4-201, including the associated estimated date for initial loading of fuel. The schedule shall be updated every 6 months until 12 months before scheduled fuel loading, and every month thereafter until all the operational programs listed in FSAR Table 13.4-201 have been fully implemented. The schedule shall identify the completion of or implementation of the following:

(a)

The construction and inspection procedures for steel concrete composite (SC) construction activities for seismic Category I nuclear island modules (including shield building SC modules) described in AP1000 DCD Rev. 19, Section 3.8.4.8; (b)

The spent fuel rack Metamic Coupon monitoring program (before initial fuel load);

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(c)

Implementation of the flow accelerated corrosion (FAC) program including construction phase activities (before initial fuel load);

(d)

A turbine maintenance and inspection program, which must be consistent with the maintenance and inspection program plan activities and inspection intervals identified in FSAR Section 10.2.3.6 (before initial fuel load);

(e)

The availability of documented instrumentation uncertainties to calculate a power calorimetric uncertainty (before initial fuel load);

(f)

The availability of administrative controls to implement maintenance and contingency activities related to the power calorimetric uncertainty instrumentation (before initial fuel load);

(g)

The site-specific severe accident management guidelines (before startup testing);

(h)

The operational and programmatic elements of the mitigative strategies for responding to circumstances associated with loss of large areas of the plant due to explosions or fire developed in accordance with 10 CFR 50.54(hh)(2) (before initial fuel load); and (i)

The pre-operational and startup procedures (including the site-specific startup administration manual) identified in FSAR Section 14.2.3 (before initiating the initial test program).

(12)

Site-and Unit-specific Conditions (a)

Before commencing installation of individual piping segments and connected components in their final locations, FPL shall complete the as-designed pipe rupture hazards analysis for compartments (rooms) containing those segments in accordance with the criteria outlined in the AP1000 DCD, Rev. 19, Sections 3.6.1.3.2 and 3.6.2.5, and shall inform the Director of NRO, or the Directors designee, in writing, upon the completion of this analysis and the availability of the as-designed pipe rupture hazards analysis reports.

(b)

Before commencing installation of individual piping segments identified in AP1000 DCD, Rev. 19, Section 3.9.8.7, and connected components in their final locations in the facility, FPL shall complete the analysis of the as-designed individual piping segments and shall inform the Director of NRO, or the Directors designee, in writing, upon the completion of these analyses and the availability of the design reports for the selected piping packages.

(c)

No later than one hundred eighty (180) days before the date scheduled for initial fuel load set forth in the notification submitted in accordance with 10 CFR 52.103(a), FPL shall submit to the

12/05/2017 Revised Draft 10 Director of NRO, or the Directors designee, in writing, a fully developed set of plant-specific emergency action levels (EALs) in accordance with Nuclear Energy Institute (NEI) 07-01, Methodology for Development of Emergency Action Levels -

Advanced Passive Light Water Reactors, Revision 0, with no deviations. The EALs shall have been discussed and agreed upon with State and local officials.

(d)

No later than eighteen (18) months before the latest date set forth in the schedule submitted in accordance with 10 CFR 52.99(a) for completing the inspections, tests, and analysis in the ITAAC, FPL shall have performed a detailed staffing analysis, in accordance with NEI 10-05, Assessment of On-Shift Emergency Response Organization Staffing and Capabilities, Revision 0.

No later than one hundred eighty (180) days before the date scheduled for initial fuel load set forth in the notification submitted in accordance with 10 CFR 52.103(a), FPL shall have revised the Emergency Plan to incorporate any changes identified in the staffing analysis that are needed to bring staffing to the required levels.

(e)

Before initial fuel load, FPL shall:

1.

Update the seismic interaction analysis in AP1000 DCD, Rev. 19, Section 3.7.5.3 to reflect as-built information, which must be based on as-procured data, as well as the as-constructed condition;

2.

Reconcile the seismic analyses described in Section 3.7.2 of the AP1000 DCD, Rev. 19, to account for detailed design changes, including, but not limited to, those due to as-procured or as-built changes in component mass, center of gravity, and support configuration based on as-procured equipment information;

3.

Calculate the instrumentation uncertainties of the actual plant operating instrumentation to confirm that either the design limit departure from nucleate boiling ratio (DNBR) values remain valid or that the safety analysis minimum DNBR bounds the new design limit DNBR values plus DNBR penalties;

4.

Update the pressure-temperature (P-T) limits using the pressure temperature limits report (PTLR) methodologies approved in AP1000 DCD, Rev. 19, using the plant-specific material properties or confirm that the reactor vessel material properties meet the specifications of and use the Westinghouse generic PTLR curves;

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5.

Verify that plant-specific belt line material properties are consistent with the properties given in AP1000 DCD Rev. 19, Section 5.3.3.1 and Tables 5.3-1 and 5.3-3. The verification must include a pressurized thermal shock (PTS) evaluation based on as-procured reactor vessel material data and the projected neutron fluence for the plant design objective. Submit this PTS evaluation report to the Director of NRO, or the Directors designee, in writing, at least 18 months before initial fuel load;

6.

Review differences between the as-built plant and the design used as the basis for the AP1000 seismic margin analysis. FPL shall perform a verification walkdown to identify differences between the as-built plant and the design. FPL shall evaluate any differences and must modify the seismic margin analysis as necessary to account for the plant-specific design and any design changes or departures from the certified design. FPL shall compare the as-built structures, systems, and components (SSCs) high confidence, low probability of failures (HCLPFs) with those assumed in the AP1000 seismic margin evaluation, before initial fuel load. FPL shall evaluate deviations from the HCLPF values or assumptions in the seismic margin evaluation due to the as-built configuration and final analysis to determine if vulnerabilities have been introduced;

7.

Review differences between the as-built plant and the design used as the basis for the AP1000 probabilistic risk assessment (PRA) and the AP1000 DCD, Rev. 19, Table 19.59-18. FPL shall evaluate the plant-specific PRA-based insight differences and shall modify the plant-specific PRA model as necessary to account for the plant-specific design and any design changes or departures from the design certified in Rev. 19 of the AP1000 DCD;

8.

Review differences between the as-built plant and the design used as the basis for the AP1000 internal fire and internal flood analysis. FPL shall evaluate the plant-specific internal fire and internal flood analyses and shall modify the analyses as necessary to account for the plant-specific design and any design changes or departures from the design certified in Rev. 19 of the AP1000 DCD; and

9.

Perform a thermal lag assessment of the as-built equipment listed in Tables 6b and 6c in Attachment A of APP-GW-GLR-069, Equipment Survivability Assessment, to provide additional assurance that this equipment can perform its severe accident functions during environmental

12/05/2017 Revised Draft 12 conditions resulting from hydrogen burns associated with severe accidents. FPL shall perform this assessment for equipment used for severe accident mitigation that has not been tested at severe accident conditions. FPL shall assess the ability of the as-built equipment to perform during accident hydrogen burns using the environment enveloping method or the test based thermal analysis method described in Electric Power Research Institute (EPRI) NP-4354, Large Scale Hydrogen Burn Equipment Experiments.

10.

Implement a surveillance program for explosively actuated valves (squib valves) that includes the following provisions in addition to the requirements specified in the edition of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) as incorporated by reference in 10 CFR 50.55a.

a.

Preservice Testing All explosively actuated valves shall be preservice tested by verifying the operational readiness of the actuation logic and associated electrical circuits for each explosively actuated valve with its pyrotechnic charge removed from the valve. This must include confirmation that sufficient electrical parameters (voltage, current, resistance) are available at the explosively actuated valve from each circuit that is relied upon to actuate the valve. In addition, a sample of at least 20% of the pyrotechnic charges in all explosively actuated valves shall be tested in the valve or a qualified test fixture to confirm the capability of each sampled pyrotechnic charge to provide the necessary motive force to operate the valve to perform its intended function without damage to the valve body or connected piping.

The sampling must select at least one explosively actuated valve from each redundant safety train.

Corrective action shall be taken to resolve any deficiencies identified in the operational readiness of the actuation logic or associated electrical circuits, or the capability of a pyrotechnic charge.

If a charge fails to fire or its capability is not confirmed, all charges with the same batch number shall be removed, discarded, and replaced with charges from a different batch number that has demonstrated successful 20% sampling of the charges.

b.

Operational Surveillance

12/05/2017 Revised Draft 13 Explosively actuated valves shall be subject to the following surveillance activities after commencing plant operation:

i.

At least once every 2 years, each explosively actuated valve shall undergo visual external examination and remote internal examination (including evaluation and removal of fluids or contaminants that may interfere with operation of the valve) to verify the operational readiness of the valve and its actuator. This examination shall also verify the appropriate position of the internal actuating mechanism and proper operation of remote position indicators.

Corrective action shall be taken to resolve any deficiencies identified during the examination with post-maintenance testing conducted that satisfies the preservice testing requirements.

ii.

At least once every 10 years, each explosively actuated valve shall be disassembled for internal examination of the valve and actuator to verify the operational readiness of the valve assembly and the integrity of individual components and to remove any foreign material, fluid, or corrosion. The examination schedule shall provide for both of the two valve designs used for explosively actuated valves at the facility to be included among the explosively actuated valves to be disassembled and examined every 2 years. Corrective action shall be taken to resolve any deficiencies identified during the examination with post-maintenance testing conducted that satisfies the preservice testing requirements.

iii.

For explosively actuated valves selected for test sampling every 2 years in accordance with the ASME OM Code, the operational readiness of the actuation logic and associated electrical circuits shall be verified for each sampled explosively actuated valve following removal of its charge. This must include confirmation that sufficient electrical parameters (voltage, current, resistance) are available for each valve actuation circuit. Corrective action shall be taken to

12/05/2017 Revised Draft 14 resolve any deficiencies identified in the actuation logic or associated electrical circuits.

iv.

For explosively actuated valves selected for test sampling every 2 years in accordance with the ASME OM Code, the sampling must select at least one explosively actuated valve from each redundant safety train. Each sampled pyrotechnic charge shall be tested in the valve or a qualified test fixture to confirm the capability of the charge to provide the necessary motive force to operate the valve to perform its intended function without damage to the valve body or connected piping. Corrective action shall be taken to resolve any deficiencies identified in the capability of a pyrotechnic charge in accordance with the preservice testing requirements.

This license condition shall expire upon (1) incorporation of the above surveillance provisions for explosively actuated valves into the facilitys inservice testing program, or (2) incorporation of inservice testing requirements for explosively actuated valves in new reactors (i.e., plants receiving a construction permit, or combined license for construction and operation, after January 1, 2000) to be specified in a future edition of the ASME OM Code as incorporated by reference in 10 CFR 50.55a, including any conditions imposed by the NRC, into the facilitys inservice testing program.

11.

Address the following requirements using the guidance contained in JLD ISG-2012-03, Compliance with Order EA-12-051, Reliable Spent Fuel Pool Instrumentation, Revision 0:

The spent fuel pool instrumentation shall be maintained available and reliable through the development and implementation of a training program. The training program shall include provisions to ensure trained personnel can route the temporary power lines from the alternate power source to the appropriate connection points, and connect the alternate power source to the safety-related level instrument channels.

12.

Develop, implement, and maintain procedural controls limiting radionuclide inventory in each of the Radwaste Building Monitor Tanks, and separately in each of up to three (3) Radwaste Building mobile radwaste processing

12/05/2017 Revised Draft 15 systems to below A2 quantities for radionuclides specified in Appendix A to 10 CFR Part 71 (Tables A-1 and A-3), as described in FSAR Subsection 13.5.2.2.5. The procedures shall also ensure that any additional equipment located in the Radwaste Building is limited to below A2 quantities and that the total cumulative radioactive inventory contained in unpackaged wastes (including liquid waste, wet waste, solid waste, gaseous waste, activated or contaminated metals and components, and contaminated waste present at any time in the Radwaste Building) is limited so that an unmitigated release, occurring over a two hour time period, would not result in a dose of greater than 500 millirem at the protected area boundary or an unmitigated exposure, occurring over a two hour time period, would not result in a dose of greater than 5 rem to site personnel located 10 feet from the total cumulative radioactive inventory.

(f)

FPL shall perform geologic mapping of excavations for safety related structures; examine and evaluate geologic features discovered in these excavations; and shall inform the Director of NRO, or the Directors designee, in writing, once excavations for these safety related structures are open for examination.

(g)

Emergency Planning Actions

1.

Communications:

a.

No later than eighteen (18) months before the latest date set forth in the schedule submitted in accordance with 10 CFR 52.99(a) for completing the inspections, tests, and analyses in the ITAAC, the licensee shall have performed an assessment of on-site and off-site communications systems and equipment relied upon during an emergency event to ensure communications capabilities can be maintained during an extended loss of alternating current power. The communications capability assessment shall be performed in accordance with NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities, Revision 0.

b.

No later than one hundred eighty (180) days before the date scheduled for initial fuel load set forth in the notification submitted in accordance with 10 CFR 52.103(a), the licensee shall have completed implementation of corrective actions identified in the communications capability assessment, including revisions to the Emergency Plan.

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2.

Staffing:

a.

No later than eighteen (18) months before the latest date set forth in the schedule submitted in accordance with 10 CFR 52.99(a) for completing the inspections, tests, and analyses in the ITAAC, the licensee shall have performed an assessment of the on-site and augmented staffing capability for response to a multi-unit event. The staffing assessment shall be performed in accordance with NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities, Revision 0.

b.

No later than one hundred eighty (180) days before the date scheduled for initial fuel load, as set forth in the notification submitted in accordance with 10 CFR 52.103(a), the licensee shall revise the Emergency Plan to include the following:

i.

Incorporation of corrective actions identified in the staffing assessments described by this license condition.

ii.

Identification of how the augmented staff will be notified, given degraded communications capabilities.

(h)

Mitigation Strategies for Beyond-Design-Basis External Events

1.

FPL shall complete development of an overall integrated plan of strategies to mitigate a beyond-design-basis external event at least 1 year before the completion of the last ITAAC on the schedule required by 10 CFR 52.99(a).

2.

The overall integrated plan required by this condition must include guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities. The overall integrated plan must include provisions to address all accident mitigation procedures and guidelines (including the guidance and strategies required by this section, emergency operating procedures, abnormal operating procedures, and extensive damage management guidelines).

3.

The guidance and strategies required by this condition must be capable of (i) mitigating a simultaneous loss of all alternating current (ac) power and loss of normal access to the normal heat sink and (ii) providing for adequate capacity to perform the functions upon which the guidance

12/05/2017 Revised Draft 17 and strategies rely for all units on the Turkey Point site and in all modes at each unit on the site.

4.

Before initial fuel load, the licensee shall fully implement the guidance and strategies required by this condition, including:

a.

Procedures;

b.

Training

c.

Acquisition, staging or installation of equipment and consumables relied upon in the strategies; and

d.

Configuration controls and provisions for maintenance and testing (including testing procedures and frequencies for preventative maintenance) of the equipment upon which the strategies and guidance required by this condition rely

5.

The training required by this condition must use a Systematic Approach to Training (SAT) to evaluate training for station personnel, and must be based upon plant equipment and procedures upon which the guidance and strategies required by this Condition rely.

6.

The licensee shall maintain the guidance and strategies described in the application upon issuance of the license, and the integrated plan of strategies upon its completion as required by this condition. The licensee may change the strategies and guidelines required by this condition provided that the licensee evaluates each such change to ensure that the provisions of 2.D.(12)(h)2 and 2.D.(12)(h)3 in this condition continue to be satisfied and the licensee documents the evaluation in an auditable form.

(i)

Insurance and Indemnity

1.

Before the scheduled date for initial fuel load, and within ninety (90) days after the NRC publishes the notice of intended operation in the Federal Register, FPL shall provide satisfactory documentary evidence to the Director of the Office of Nuclear Reactor Regulation or the Directors designee that it has obtained the appropriate amount of primary and secondary financial protection required of licensees pursuant to 10 CFR 140.11(a)(4) and the appropriate amount of financial protection required by 10 CFR 50.54(w).

12/05/2017 Revised Draft 18

2.

Before the scheduled date of initial fuel load, and within ninety (90) days after the NRC publishes the notice of intended operation in the Federal Register, FPL shall provide evidence to the NRC that it would have the ability to pay into the nuclear industry retrospective rating plan in the event of a nuclear incident and in the amount specified in 10 CFR 140.11(a)(4) for one calendar year using one of the following methods:

a.

Surety bond,

b.

Letter of credit,

c.

Revolving credit/term loan arrangement,

d.

Maintenance of escrow deposits of government securities, or

e.

Annual certified financial statement showing either that a cash flow (i.e., cash available to a company after all operating expenses, taxes, interest charges, and dividends have been paid) can be generated and would be available for payment of retrospective premiums within three (3) months after submission of the statement, or a cash reserve or a combination of cash flow and cash reserve.

Thereafter, FPL shall provide evidence of the guarantees of payment of deferred premiums in accordance with the provisions specified in 10 CFR 140.21.

(j)

At the first annual update of the Turkey Point Units 6 and 7 FSAR required by 10 CFR 50.71(e), FPL shall include the following changes based on inspection findings from NRC Inspection Report No. 99900404/2015-203:

1.

Revise Appendix 19F.4.1, Malevolent Aircraft, to include the Auxiliary Building as a key design feature that also protects from physical damage the core cooling credited to meet 10 CFR 50.150(b)(2).

2.

Revise DCD drawings to show the 5 psid and 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated doors that have been added to the inner portion (annulus side) of the shield building in accordance with final markups used to satisfy NRC Inspection Report No. 99900404/2015-203 and 10 CFR 50.150(a)(1). The DCD figures listed below are to be revised:

a.

Figure 1.2-7 Nuclear Island General Arrangement Plan at Elevation 107'-2" & 111'-0"

12/05/2017 Revised Draft 19

b.

Figure 1.2-10 Nuclear Island General Arrangement Plan at El. 135'-3"

c.

Figure 9A-1 (Sheet 5 of 16) Nuclear Island Fire Areas Plan at Elevation 100'-0" & 107'-2"

d.

Figure 9A-1 (Sheet 7 of 16) Nuclear Island Fire Area Plan at Elevation 135'-3"

e.

Figure 12.3-1 (Sheet 6 of 16) Radiation Zones, Normal Operations/Shutdown Nuclear Island, Elevation 100'-0" & 107'-2"

f.

Figure 12.3-1 (Sheet 8 of 16) Radiation Zones, Normal Operations/Shutdown Nuclear Island, Elevation 135'-3"

g.

Figure 12.3-2 (Sheet 6 of 15) Radiation Zones, Post-Accident Nuclear Island, Elevation 100'-0" &

107'-2"

h.

Figure 12.3-2 (Sheet 8 of 15) Radiation Zones, Post-Accident Nuclear Island, Elevation 135'-3"

i.

Figure 12.3-3 (Sheet 6 of 16) Radiological Access Controls, Normal Operations/Shutdown Nuclear Island, Elevation 100'-0" & 107'-2"

j.

Figure 12.3-3 (Sheet 8 of 16) Radiological Access Controls, Normal Operations/Shutdown Nuclear Island, Elevation 135'-3" E.

FPL shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Act, to cover public liability claims.

F.

Exemptions (1)

The following exemptions from the regulations were granted in the rulemaking for the design certification rule that is referenced in the application. In accordance with 10 CFR Part 52, Appendix A, Section V, Applicable Regulations, Subsection B, and pursuant to 10 CFR 52.63(a)(5), FPL is exempt from the following portions of the regulations:

(a)

Paragraph (f)(2)(iv) of 10 CFR 50.34Plant Safety Parameter Display Console (b)

Paragraph (c)(1) of 10 CFR 50.62Auxiliary (or emergency) feedwater system; and

12/05/2017 Revised Draft 20 (c)

Appendix A to 10 CFR Part 50, GDC 17Second offsite power supply circuit.

(2)

The following exemption from part of the referenced design certification rule meets the requirements of 10 CFR 52.7 and Section VIII.A.4, VIII.B.4, or VIII.C.4 of Appendix D to 10 CFR Part 52, is authorized by law, will not present an undue risk to the public health or safety, and is consistent with the common defense and security. Special circumstances are present in that the application of the regulation in this particular circumstance is not necessary to achieve the underlying purpose of the rule (10 CFR 50.12(a)(2)(ii)) as described in the application and the FSER associated with this license.

(a)

FPL is exempt from the requirement of 10 CFR Part 52, Appendix D, Section IV.A.2.a to include a plant-specific DCD containing the same type of information and using the same organization and numbering as the generic DCD for the AP1000 certified design. This exemption is specific to the organization and numbering scheme in the FSAR and is related to departure number STD DEP 1.1-1.

(3)

For the reasons set forth below, the following specific exemptions which are outside the scope of the design certification rule referenced in the application are granted:

(a)

FPL is exempt from the requirements of 10 CFR 70.22(b),

10 CFR 70.32(c), 10 CFR 74.31, 10 CFR 74.41, and 10 CFR 74.51 because FPL meets the requirements of 10 CFR 70.17 and 74.7 as discussed in Section 1.5.4 of the final safety evaluation report (FSER) associated with this license. The exemption meets the requirements of 10 CFR 52.7 because it is authorized by law, will not present an undue risk to public health and safety, and is consistent with the common defense and security. Additionally, special circumstances are present in that the application of the regulations in this particular circumstance is not necessary to achieve the underlying purpose of the rule (10 CFR 50.12(a)(ii)) as described in the FSER associated with this license.

(b)

FPL is exempt from the requirements of 10 CFR 52.93(a)(1) as it relates to the exemption granted in Section 2.F.(2)(a) of this license because the exemption meets the requirements of 10 CFR 52.7 and because the exemption is authorized by law, will not present an undue risk to the public health or safety, and is consistent with the common defense and security. Additionally, special circumstances are present in that the application of the regulation in this particular circumstance is not necessary to achieve the underlying purpose of the rule (10 CFR 50.12(a)(2)(ii))

as described in the FSER associated with this license.

12/05/2017 Revised Draft 21 (4)

For the reasons set forth below, the following exemptions associated with departures from Tier 1 and generic technical specifications of the AP1000 design certification are granted:

The Tier 1 and generic technical specifications departures listed below meet the requirements of 10 CFR Part 52, Appendix A, Section VIII.A.4 or VIII.C.4 and the regulations referenced therein because as discussed in Chapter 21 of the FSER associated with this license:

The Tier 1 departures will not significantly decrease the level of safety otherwise provided by the design; The Tier 1 and generic technical specifications departures are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security; Special circumstances are present as required by 10 CFR 50.12(a)(2); specifically, as discussed in Chapter 21 of the final safety evaluation report for this license, the staff finds that there are special circumstances under 10 CFR 50.12(a)(2)(ii) for the following Tier 1 and generic technical specifications exemptions because application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule; For Tier 1 departures identified in 2.F.(4)(a), 2.F.(4)(b), 2.F.(4)(c),

and 2.F.(4)(d), special circumstances do not outweigh any potential decrease in safety due to reduced standardization.

a.

PTN DEP 3.2-1 (exemption from Tier 1 and generic technical specifications)

b.

PTN DEP 6.4-1 (exemption from Tier 1 and generic technical specifications)

c.

PTN DEP 6.4-2 (exemption from Tier 1 and generic technical specifications)

d.

PTN DEP 6.2-1 (exemption from Tier 1)

e.

PTN DEP 7.3-1 (exemption from generic technical specifications)

G.

FPL shall maintain the guidance and strategies developed in accordance with 10 CFR 50.54(hh)(2).

H.

This license is effective as of [insert actual date of license issuance] and shall expire at midnight on the date 40 years from the date that the Commission finds

12/05/2017 Revised Draft 22 that the acceptance criteria in the combined license are met in accordance with 10 CFR 52.103(g).

FOR THE NUCLEAR REGULATORY COMMISSION Frederick D. Brown, Acting Director Office of New Reactors Appendices:

Appendix A - Technical Specifications Appendix B - Environmental Protection Plan Appendix C - Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC)

12/05/2017 Revised Draft A-1 APPENDIX A TURKEY POINT UNIT 7 TECHNICAL SPECIFICATIONS The unit-specific technical specifications from the Turkey Point Unit 7 combined license application, Part 4, Section B, will be included in Appendix A of the Turkey Point Unit 7 combined license. The applicant has committed to providing the NRC with unit-specific versions of the Unit 6/Unit 7 technical specifications that were submitted in the combined license application in a suitable timeframe to support issuance of each individual units combined license. These unit-specific technical specifications will exceed 250 pages. Therefore, for ease of handling, the technical specifications are not included in this draft combined license, but can be viewed in the Agencywide Documents Access and Management System (ADAMS) at the Accession Number given below:

ML16250A350 - FPL - Turkey Point Units 6 & 7 COLA Rev. 8 (Technical Specifications) - Part 4 Technical Specifications

12/05/2017 Revised Draft B-1 APPENDIX B TURKEY POINT UNIT 7 ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL) 1.0 Objectives of the Environmental Protection Plan The Environmental Protection Plan (EPP) objectives are to ensure compliance with Biological Opinions issued pursuant to the Endangered Species Act of 1973, as amended (ESA), and to ensure that the U.S. Nuclear Regulatory Commission (NRC) is kept informed of other environmental matters. The EPP is intended to be consistent with Federal, State, and local requirements for environmental protection.

2.0 Environmental Protection Issues In the Final Environmental Impact Statement (FEIS) dated October 2016 the staff considered the environmental impacts associated with the construction and operation of Turkey Point Units 6 and 7. This EPP applies to Florida Power & Lights (FPL, the licensee) actions affecting the environmental resources evaluated in the FEIS and FPLs actions that may affect any newly discovered environmental resources.

2.1 Aquatic Resources Issues Federal agencies other than the NRC, such as the U.S. Environmental Protection Agency and the U.S. Army Corps of Engineers, have jurisdiction to regulate aquatic resources under the Federal Water Pollution Control Act (Clean Water Act or CWA) and the Rivers and Harbors Appropriation Act of 1899 (RHA). Certain water quality environmental considerations identified in the FEIS, including effluent limitations, monitoring requirements, and wetland and aquatic resource mitigation measures, are regulated under FPLs CWA permits, such as National Pollutant Discharge Elimination System and Section 404 permits, and RHA Section 10 permit.

Nothing within this EPP shall be construed to place additional requirements on the regulation of aquatic resources except the imposition of the requirements in a Biological Opinion under the ESA (see Section 2.3). FPL is required to inform the NRC of events or situations concerning aquatic resources consistent with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.72(b)(2)(xi), and this EPP does not expand any reporting requirement required by that regulation.

2.2 Terrestrial Resources Issues Several statutes govern the regulation of terrestrial resources. For example, the U.S. Fish and Wildlife Service (FWS) regulates matters involving migratory birds and their nests in accordance with the Migratory Bird Treaty Act (MBTA). Activities affecting migratory birds or their nests may require permits under the MBTA. The FWS also regulates matters involving the protection and taking of bald and golden eagles in accordance with the Bald and Golden Eagle Protection Act.

FPL shall inform NRC of any events or situations concerning terrestrial resources consistent with the provisions of 10 CFR 50.72(b)(2)(xi), and this EPP does not expand any reporting requirement required by that regulation.

12/05/2017 Revised Draft B-2 2.3 Endangered Species Act of 1973 The NRC may be required to protect some aquatic resources and terrestrial resources in accordance with the ESA. In accordance with ESA Section 7, FPL shall comply with the following conditions to implement the terms and conditions set forth in the Incidental Take Statement of the Biological Opinion issued by the FWS on June 23, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17177A673):

1. No earlier than one year (two years for the Miami tiger beetle) before commencing land clearing and construction activities for the plant and associated facilities in areas potentially containing one or more of the following species, FPL shall conduct surveys to determine whether the following species are present:

Florida bonneted bat Piping plover Bartrams scrub-hairstreak butterfly Florida leafwing butterfly Miami tiger beetle (a minimum of two years of survey data for appropriate habitat is required)

FPL shall provide the survey results in a report to the FWS Vero Beach Field Office and the NRC. If any individuals are found by these surveys, the licensee shall coordinate with the FWS to avoid or minimize any take of these species.

2. No earlier than one year before commencing land clearing and construction activities for the plant and associated facilities in areas potentially containing one or more of the following species, FPL shall conduct surveys to determine whether the following species are present:

Beach jaquemontia Carters small-flowered flax Crenulate lead plant Deltoid spurge Florida Brickell-bush Garbers spurge Smalls milkpea Tiny polygala FPL shall provide the survey results in a report to the FWS Vero Beach Field Office and NRC. If any occurrences of these species are found by these surveys, the licensee shall coordinate with the FWS to avoid or minimize any take of these species.

3. Before and for each day throughout the period of active land clearing, site preparation, and muck placement work, the licensee shall conduct pedestrian surveys for the American crocodile and eastern indigo snake in potentially suitable habitats undergoing disturbance. If any crocodiles are found, the licensee shall cease work in the affected area until the individuals have left or been relocated. If any eastern indigo snakes are found, the licensee shall cease work until the individuals have left areas where they might be killed or injured by project work.

12/05/2017 Revised Draft B-3

4. Prior to land-clearing to build the west transmission lines, the licensee shall conduct an aerial survey for the wood stork during the nesting season to determine if active wood stork nesting colonies occur within 0.5 mi (0.8 km) of the west transmission line route.

5. After land-clearing but prior to commencing construction on the west transmission lines, the licensee shall conduct flight surveys for the wood stork during the nesting season.

6. During the first nesting season following completion of construction of the west transmission lines, the licensee shall monitor for injured or dead wood storks along the section of the west transmission line that occurs near the known wood stork nesting colonies. Monitoring methods shall be developed in conjunction with the FWS, Florida Fish and Wildlife Conservation Commission, and South Florida Water Management District.

7. Following commencement of construction and throughout the period of construction, the licensee shall submit to the FWS Vero Beach Field Office an annual report describing:

1) Any observations within the project area of injured or dead individuals of the following species: American crocodile, eastern indigo snake, Everglade snail kite, Florida panther, red knot, and wood stork.

2) The acreage of each habitat type cleared, using habitat names used in the FEIS.

8. Upon locating a dead, injured, or sick threatened or endangered species, the licensee shall immediately notify the FWS Law Enforcement Office at 20501 Independence Boulevard, Groveland, Florida 34736-8573; Phone 352-429-1064 and the Florida Fish and Wildlife Conservation Commission, South Region, 3900 Drane Field Road, Lakeland, Florida, 33811-1299; Phone 800-282-8002. The licensee shall follow the instruction of the FWS Law Enforcement Office regarding the care, disposition, and/or preservation of any such individuals.

If any Federally listed species or critical habitat occurs in an area affected by construction or operation of the plant that was not previously identified as occurring in such areas, including species and critical habitat that were not previously Federally listed, FPL shall inform the NRC within four hours of discovery. The time of discovery is identified as the specific time when a decision is made to notify another agency or to issue a press release. Similarly, FPL shall inform the NRC within four hours of discovery of any take, as defined in the ESA, of a Federally listed species or destruction or adverse modification of critical habitat. The four-hour discovery notification shall be made to the NRC Operations Center via the Emergency Notification System. FPL shall provide any necessary information to the NRC if the NRC initiates or reinitiates consultation under the ESA.

Unusual Event - FPL shall inform the NRC of any onsite mortality, injury, or unusual occurrence of any species protected by the ESA within four hours of discovery, followed by a written report in accordance with Section 4.1. The time of discovery is identified as the specific time when a decision is made to notify another agency or to issue a press release. Such incidents shall be reported regardless of FPLs assessment of causal relation to plant construction or operation.

12/05/2017 Revised Draft B-4 3.0 Consistency Requirements FPL shall notify the NRC of proposed changes to permits or certifications concerning aquatic or terrestrial resources by providing the NRC with a copy of the proposed change(s) at the same time it is submitted to the permitting agency.

FPL shall provide the NRC with a copy of the application for renewal of permits or certifications at the same time the application is submitted to the permitting agency.

Changes to or renewals of such permits or certifications shall be reported to the NRC within 30 days following the later of the date the change or renewal is approved or the date the change becomes effective. If a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.

4.0 Administrative Procedures 4.1 Plant Reporting Requirements: Non-routine Reports A written report shall be submitted to the NRC within 30 days of occurrence of any unusual event described in Section 2.3 of this EPP. The report shall:

(a) describe, analyze, and evaluate the event, including extent and magnitude of the impact and plant operating characteristics at the time of the event, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (e) indicate the agencies notified and their preliminary responses.

Events reportable under this subsection, which also require reports to other Federal, state, or local agencies, shall be reported in accordance with those reporting requirements in lieu of the requirements of this subsection. The NRC shall be provided a copy of such report at the same time it is submitted to the other agency.

4.2 Review and Audit FPL shall provide for review and audit of compliance with Section 2.3 of this EPP. The audits shall be conducted independently of the individual or groups responsible for performing the specific activity. A description of the organizational structure utilized to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.

4.3 Records Retention Records required by this EPP shall be made and retained in a manner convenient for review and inspection. These records shall be made available to the NRC on request. The records,

12/05/2017 Revised Draft B-5 data, and logs relating to this EPP shall be retained for five years or, where applicable, in accordance with the requirements of other agencies.

4.4 Changes in Environmental Protection Plan A request for a change in the EPP shall include an assessment of the environmental impact of the proposed change and a supporting justification. Implementation of such changes in the EPP shall not commence prior to NRC approval of the proposed changes in the form of a license amendment incorporating the appropriate revision to the EPP.

FPL shall request a license amendment to incorporate the requirements of any Terms and Conditions set forth in the Incidental Take Statement of applicable Biological Opinions issued subsequent to the effective date of this EPP.

12/05/2017 Revised Draft C-1 APPENDIX C TURKEY POINT UNIT 7 INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA (ITAAC)

The ITAAC Master List is a table of unit-specific ITAAC which are from the AP1000 DCD and the Turkey Point combined license application. The consolidated set of unit-specific ITAAC will be included in Appendix C of the Turkey Point Unit 7 combined license. These unit-specific ITAAC details will exceed 170 pages. Therefore, for ease of handling, the ITAAC details are not included in this draft combined license, but can be viewed in the Agencywide Documents Access and Management System (ADAMS) at the Accession Number given below:

COL Application Part 10, Rev. 8 (COL8) - ML16250A554 - FPL - Turkey Point Units 6

& 7 COLA Rev. 8 (ITAAC) - Part 10 License Conditions (Including ITAAC)

Westinghouse AP1000 DCD, Rev. 19, document files 5 through 21 (DCD19) -

http://pbadupws.nrc.gov/docs/ML1117/ML11171A500.html No.

ITAAC No.

Plant System ITAAC Source 1

2.1.01.01 Fuel Handling and Refueling System DCD19 2

2.1.01.02 DCD19 3

2.1.01.03 DCD19 4

2.1.01.04 DCD19 5

2.1.01.05 DCD19 6

2.1.01.06.i DCD19 7

2.1.01.06.ii DCD19 8

2.1.01.07.i DCD19 9

2.1.01.07.ii DCD19 10 2.1.01.07.iii DCD19 11 2.1.01.07.iv DCD19 12 2.1.02.01 Reactor Coolant System DCD19 13 2.1.02.02a DCD19 14 2.1.02.02b DCD19 15 2.1.02.03a DCD19 16 2.1.02.03b DCD19 17 2.1.02.04a DCD19 18 2.1.02.04b DCD19 19 2.1.02.05a.i DCD19 20 2.1.02.05a.ii DCD19 21 2.1.02.05a.iii DCD19 22 2.1.02.05b DCD19 23 2.1.02.06 DCD19 24 2.1.02.07a.i DCD19 25 2.1.02.07a.ii DCD19 26 2.1.02.07b DCD19

12/05/2017 Revised Draft C-2 No.

ITAAC No.

Plant System ITAAC Source 27 2.1.02.07c DCD19 28 2.1.02.08a.i DCD19 29 2.1.02.08a.ii Reactor Coolant System (contd)

DCD19 30 2.1.02.08b DCD19 31 2.1.02.08c DCD19 32 2.1.02.08d.i DCD19 33 2.1.02.08d.ii DCD19 34 2.1.02.08d.iii DCD19 35 2.1.02.08d.iv DCD19 36 2.1.02.08d.v DCD19 37 2.1.02.08d.vi DCD19 38 2.1.02.08d.vii DCD19 39 2.1.02.08d.viii DCD19 40 2.1.02.08e DCD19 41 2.1.02.09a DCD19 42 2.1.02.09b.i DCD19 43 2.1.02.09b.ii DCD19 44 2.1.02.09c DCD19 45 2.1.02.10 DCD19 46 2.1.02.11a.i DCD19 47 2.1.02.11a.ii DCD19 48 2.1.02.11b.i DCD19 49 2.1.02.11b.ii DCD19 50 2.1.02.11b.iii DCD19 51 2.1.02.11c.i DCD19 52 2.1.02.11c.ii DCD19 53 2.1.02.12a.i DCD19 54 2.1.02.12a.ii DCD19 55 2.1.02.12a.iii DCD19 56 2.1.02.12a.iv DCD19 57 2.1.02.12a.v DCD19 58 2.1.02.12a.vi DCD19 59 2.1.02.12a.vii DCD19 60 2.1.02.12a.viii DCD19 61 2.1.02.12a.ix DCD19 62 2.1.02.12b DCD19 63 2.1.02.13a DCD19 64 2.1.02.13b DCD19 65 2.1.02.13c DCD19 66 2.1.02.14 DCD19 67 2.1.02.15 DCD19 68 2.1.03.01 Reactor System DCD19 69 2.1.03.02a DCD19 70 2.1.03.02b DCD19 71 2.1.03.02c DCD19 72 2.1.03.03 DCD19 73 2.1.03.04 DCD19 74 2.1.03.05 DCD19 75 2.1.03.06.i DCD19

12/05/2017 Revised Draft C-3 No.

ITAAC No.

Plant System ITAAC Source 76 2.1.03.06.ii DCD19 77 2.1.03.06.iii DCD19 78 2.1.03.07.i Reactor System (contd)

DCD19 79 2.1.03.07.ii DCD19 80 2.1.03.08 DCD19 81 2.1.03.09a.i DCD19 82 2.1.03.09a.ii DCD19 83 2.1.03.09b DCD19 84 2.1.03.09c DCD19 85 2.1.03.10 DCD19 86 2.1.03.11 DCD19 87 2.1.03.12 DCD19 88 2.1.03.13 DCD19 89 2.1.03.14 DCD19 90 2.2.01.01 Containment System DCD19 91 2.2.01.02a DCD19 92 2.2.01.02b DCD19 93 2.2.01.03a DCD19 94 2.2.01.03b DCD19 95 2.2.01.04a.i DCD19 96 2.2.01.04a.ii DCD19 97 2.2.01.04b DCD19 98 2.2.01.05.i DCD19 99 2.2.01.05.ii DCD19 100 2.2.01.05.iii DCD19 101 2.2.01.06a.i DCD19 102 2.2.01.06a.ii DCD19 103 2.2.01.06b DCD19 104 2.2.01.06c DCD19 105 2.2.01.06d.i DCD19 106 2.2.01.06d.ii DCD19 107 2.2.01.07.i DCD19 108 2.2.01.07.ii DCD19 109 2.2.01.08 DCD19 110 2.2.01.09 DCD19 111 2.2.01.10a DCD19 112 2.2.01.10b DCD19 113 2.2.01.10c DCD19 114 2.2.01.11a.i DCD19 115 2.2.01.11a.ii DCD19 116 2.2.01.11a.iii DCD19 117 2.2.01.11a.iv DCD19 118 2.2.01.11b DCD19 119 2.2.02.01 Passive Containment Cooling System DCD19 120 2.2.02.02a DCD19 121 2.2.02.02b DCD19 122 2.2.02.03a DCD19 123 2.2.02.03b DCD19 124 2.2.02.04a DCD19

12/05/2017 Revised Draft C-4 No.

ITAAC No.

Plant System ITAAC Source 125 2.2.02.04b DCD19 126 2.2.02.05a.i DCD19 127 2.2.02.05a.ii Passive Containment Cooling System (contd)

DCD19 128 2.2.02.05a.iii DCD19 129 2.2.02.05b DCD19 130 2.2.02.05c DCD19 131 2.2.02.06a.i DCD19 132 2.2.02.06a.ii DCD19 133 2.2.02.06b DCD19 134 2.2.02.06c DCD19 135 2.2.02.07a.i DCD19 136 2.2.02.07a.ii DCD19 137 2.2.02.07a.iii DCD19 138 2.2.02.07b.i DCD19 139 2.2.02.07b.ii DCD19 140 2.2.02.07b.iii DCD19 141 2.2.02.07c DCD19 142 2.2.02.07d DCD19 143 2.2.02.07e.i DCD19 144 2.2.02.07e.ii DCD19 145 2.2.02.07f.i DCD19 146 2.2.02.07f.ii DCD19 147 2.2.02.08a DCD19 148 2.2.02.08b DCD19 149 2.2.02.08c DCD19 150 2.2.02.09 DCD19 151 2.2.02.10a DCD19 152 2.2.02.10b DCD19 153 2.2.02.10c DCD19 154 2.2.02.11a.i DCD19 155 2.2.02.11a.ii DCD19 156 2.2.02.11a.iii DCD19 157 2.2.02.11b DCD19 158 2.2.03.01 Passive Core Cooling System DCD19 159 2.2.03.02a DCD19 160 2.2.03.02b DCD19 161 2.2.03.03a DCD19 162 2.2.03.03b DCD19 163 2.2.03.04a DCD19 164 2.2.03.04b DCD19 165 2.2.03.05a.i DCD19 166 2.2.03.05a.ii DCD19 167 2.2.03.05a.iii DCD19 168 2.2.03.05b DCD19 169 2.2.03.06 DCD19 170 2.2.03.07a.i DCD19 171 2.2.03.07a.ii DCD19 172 2.2.03.07b DCD19 173 2.2.03.07c DCD19

12/05/2017 Revised Draft C-5 No.

ITAAC No.

Plant System ITAAC Source 174 2.2.03.08a DCD19 175 2.2.03.08b.01 DCD19 176 2.2.03.08b.02 Passive Core Cooling System (contd)

DCD19 177 2.2.03.08c.i.01 DCD19 178 2.2.03.08c.i.02 DCD19 179 2.2.03.08c.i.03 DCD19 180 2.2.03.08c.i.04 DCD19 181 2.2.03.08c.ii DCD19 182 2.2.03.08c.iii DCD19 183 2.2.03.08c.iv.01 DCD19 184 2.2.03.08c.iv.02 DCD19 185 2.2.03.08c.iv.03 DCD19 186 2.2.03.08c.iv.04 DCD19 187 2.2.03.08c.v.01 DCD19 188 2.2.03.08c.v.02 DCD19 189 2.2.03.08c.vi.01 DCD19 190 2.2.03.08c.vi.02 DCD19 191 2.2.03.08c.vi.03 DCD19 192 2.2.03.08c.vii DCD19 193 2.2.03.08c.viii DCD19 194 2.2.03.08c.ix DCD19 195 2.2.03.08c.x DCD19 196 2.2.03.08c.xi DCD19 197 2.2.03.08c.xii DCD19 198 2.2.03.08c.xiii DCD19 199 2.2.03.08c.xiv DCD19 200 2.2.03.08d DCD19 201 2.2.03.09a.i DCD19 202 2.2.03.09a.ii DCD19 203 2.2.03.09a.iii DCD19 204 2.2.03.09b DCD19 205 2.2.03.09c DCD19 206 2.2.03.10 DCD19 207 2.2.03.11a.i DCD19 208 2.2.03.11a.ii DCD19 209 2.2.03.11b.i DCD19 210 2.2.03.11b.ii DCD19 211 2.2.03.11b.iii DCD19 212 2.2.03.11c.i DCD19 213 2.2.03.11c.ii DCD19 214 2.2.03.12a.i DCD19 215 2.2.03.12a.ii DCD19 216 2.2.03.12a.iv DCD19 217 2.2.03.12b DCD19 218 2.2.03.13 DCD19 219 2.2.04.01 Steam Generator System DCD19 220 2.2.04.02a DCD19 221 2.2.04.02b DCD19 222 2.2.04.03a DCD19

12/05/2017 Revised Draft C-6 No.

ITAAC No.

Plant System ITAAC Source 223 2.2.04.03b DCD19 224 2.2.04.04a DCD19 225 2.2.04.04b Steam Generator System (contd)

DCD19 226 2.2.04.05a.i DCD19 227 2.2.04.05a.ii DCD19 228 2.2.04.05a.iii DCD19 229 2.2.04.05b DCD19 230 2.2.04.06 DCD19 231 2.2.04.07a.i DCD19 232 2.2.04.07a.ii DCD19 233 2.2.04.07b DCD19 234 2.2.04.07c DCD19 235 2.2.04.08a.i DCD19 236 2.2.04.08a.ii DCD19 237 2.2.04.08b.i DCD19 238 2.2.04.08b.ii DCD19 239 2.2.04.08c DCD19 240 2.2.04.09a.i DCD19 241 2.2.04.09a.ii DCD19 242 2.2.04.09b.i DCD19 243 2.2.04.09b.ii DCD19 244 2.2.04.10 DCD19 245 2.2.04.11a DCD19 246 2.2.04.11b.i DCD19 247 2.2.04.11b.ii DCD19 248 2.2.04.12a.i DCD19 249 2.2.04.12a.ii DCD19 250 2.2.04.12a.iii DCD19 251 2.2.04.12b DCD19 252 2.2.05.01 Main Control Room Emergency Habitability System DCD19 253 2.2.05.02a DCD19 254 2.2.05.02b DCD19 255 2.2.05.03a DCD19 256 2.2.05.03b DCD19 257 2.2.05.04a DCD19 258 2.2.05.04b DCD19 259 2.2.05.05a.i DCD19 260 2.2.05.05a.ii DCD19 261 2.2.05.05a.iii DCD19 262 2.2.05.05b DCD19 263 2.2.05.06a DCD19 264 2.2.05.06b DCD19 265 2.2.05.07a.i DCD19 266 2.2.05.07a.ii DCD19 267 2.2.05.07a.iii DCD19 268 2.2.05.07b.i DCD19 269 2.2.05.07b.ii DCD19 270 2.2.05.07c DCD19 271 2.2.05.07d DCD19

12/05/2017 Revised Draft C-7 No.

ITAAC No.

Plant System ITAAC Source 272 C.2.2.05.07e COL8 273 2.2.05.08 DCD19 274 2.2.05.09a Main Control Room Emergency Habitability System (contd)

DCD19 275 2.2.05.09b DCD19 276 2.2.05.10 DCD19 277 2.2.05.11 DCD19 278 2.2.05.12 DCD19 279 2.3.01.01 Component Cooling Water System DCD19 280 2.3.01.02 DCD19 281 2.3.01.03.i DCD19 282 2.3.01.03.ii DCD19 283 2.3.01.04 DCD19 284 2.3.01.05 DCD19 285 2.3.02.01 Chemical and Volume Control System DCD19 286 2.3.02.02a DCD19 287 2.3.02.02b DCD19 288 2.3.02.03a DCD19 289 2.3.02.03b DCD19 290 2.3.02.04a DCD19 291 2.3.02.04b DCD19 292 2.3.02.05.i DCD19 293 2.3.02.05.ii DCD19 294 2.3.02.05.iii DCD19 295 2.3.02.06a.i DCD19 296 2.3.02.06a.ii DCD19 297 2.3.02.06b DCD19 298 2.3.02.06c DCD19 299 2.3.02.07a DCD19 300 2.3.02.07b DCD19 301 2.3.02.07c DCD19 302 2.3.02.08a.i DCD19 303 2.3.02.08a.ii DCD19 304 2.3.02.08a.iii DCD19 305 2.3.02.08b DCD19 306 2.3.02.09 DCD19 307 2.3.02.10a DCD19 308 2.3.02.10b.i DCD19 309 2.3.02.10b.ii DCD19 310 2.3.02.11a.i DCD19 311 2.3.02.11a.ii DCD19 312 2.3.02.11a.iii DCD19 313 2.3.02.11a.iv DCD19 314 2.3.02.11b DCD19 315 2.3.02.12a DCD19 316 2.3.02.12b DCD19 317 2.3.02.13 DCD19 318 2.3.02.14 DCD19 319 2.3.03.01 Standby Diesel Fuel Oil System DCD19 320 2.3.03.02 DCD19

12/05/2017 Revised Draft C-8 No.

ITAAC No.

Plant System ITAAC Source 321 2.3.03.03a DCD19 322 2.3.03.03b DCD19 323 2.3.03.03c Standby Diesel Fuel Oil System (contd)

DCD19 324 2.3.03.03d DCD19 325 2.3.03.04 DCD19 326 2.3.03.05 DCD19 327 2.3.04.01 Fire Protection System DCD19 328 2.3.04.02.i DCD19 329 2.3.04.02.ii DCD19 330 2.3.04.03 DCD19 331 2.3.04.04.i DCD19 332 2.3.04.04.ii DCD19 333 2.3.04.05 DCD19 334 2.3.04.06 DCD19 335 2.3.04.07 DCD19 336 2.3.04.08 DCD19 337 2.3.04.09 DCD19 338 2.3.04.10 DCD19 339 2.3.04.11 DCD19 340 2.3.05.01 Mechanical Handling System DCD19 341 2.3.05.02.i DCD19 342 2.3.05.02.ii DCD19 343 2.3.05.02.iii DCD19 344 2.3.05.03a.i DCD19 345 2.3.05.03a.ii DCD19 346 2.3.05.03a.iii DCD19 347 2.3.05.03b.i DCD19 348 2.3.05.03b.ii DCD19 349 2.3.05.03b.iii DCD19 350 2.3.05.03c.i DCD19 351 2.3.05.03c.ii DCD19 352 2.3.05.03d.i DCD19 353 2.3.05.03d.ii DCD19 354 2.3.05.04 DCD19 355 2.3.06.01 Normal Residual Heat Removal System DCD19 356 2.3.06.02a DCD19 357 2.3.06.02b DCD19 358 2.3.06.03a DCD19 359 2.3.06.03b DCD19 360 2.3.06.04a DCD19 361 2.3.06.04b DCD19 362 2.3.06.05a.i DCD19 363 2.3.06.05a.ii DCD19 364 2.3.06.05a.iii DCD19 365 2.3.06.05b DCD19 366 2.3.06.06 DCD19 367 2.3.06.07a.i DCD19 368 2.3.06.07a.ii DCD19 369 2.3.06.07b DCD19

12/05/2017 Revised Draft C-9 No.

ITAAC No.

Plant System ITAAC Source 370 2.3.06.07c DCD19 371 2.3.06.08a DCD19 372 2.3.06.08b Normal Residual Heat Removal System (contd)

DCD19 373 2.3.06.09a.i DCD19 374 2.3.06.09a.ii DCD19 375 2.3.06.09b.i DCD19 376 2.3.06.09b.ii DCD19 377 2.3.06.09b.iii DCD19 378 2.3.06.09b.iv DCD19 379 2.3.06.09b.v DCD19 380 2.3.06.09c DCD19 381 2.3.06.09d DCD19 382 2.3.06.10 DCD19 383 2.3.06.11a DCD19 384 2.3.06.11b DCD19 385 2.3.06.12a.i DCD19 386 2.3.06.12a.ii DCD19 387 2.3.06.12a.iii DCD19 388 2.3.06.12a.iv DCD19 389 2.3.06.12b DCD19 390 2.3.06.13 DCD19 391 2.3.06.14 DCD19 392 2.3.07.01 Spent Fuel Pool Cooling System DCD19 393 2.3.07.02a DCD19 394 2.3.07.02b DCD19 395 2.3.07.03 DCD19 396 2.3.07.04 DCD19 397 2.3.07.05.i DCD19 398 2.3.07.05.ii DCD19 399 2.3.07.05.iii DCD19 400 2.3.07.06a DCD19 401 2.3.07.06b DCD19 402 2.3.07.07a DCD19 403 2.3.07.07b.i DCD19 404 2.3.07.07b.ii DCD19 405 2.3.07.07b.iii DCD19 406 2.3.07.07b.iv DCD19 407 2.3.07.07b.v DCD19 408 2.3.07.07b.vi DCD19 409 2.3.07.07c DCD19 410 2.3.07.08.i DCD19 411 2.3.07.08.ii DCD19 412 2.3.07.09 DCD19 413 2.3.07.10 DCD19 414 2.3.07.11 DCD19 415 2.3.08.01 Service Water System DCD19 416 2.3.08.02.i DCD19 417 2.3.08.02.ii DCD19 418 2.3.08.02.iii DCD19

12/05/2017 Revised Draft C-10 No.

ITAAC No.

Plant System ITAAC Source 419 2.3.08.03 DCD19 420 2.3.08.04 DCD19 421 2.3.09.01 Containment Hydrogen Control System DCD19 422 2.3.09.02a DCD19 423 2.3.09.02b DCD19 424 2.3.09.03.i DCD19 425 2.3.09.03.ii DCD19 426 C.2.3.09.03.iii COL8 427 2.3.09.03.iv DCD19 428 2.3.09.04a DCD19 429 2.3.09.04b DCD19 430 2.3.09.05 DCD19 431 2.3.10.01 Liquid Radwaste System DCD19 432 2.3.10.02a DCD19 433 2.3.10.02b DCD19 434 2.3.10.03a DCD19 435 2.3.10.03b DCD19 436 2.3.10.04a DCD19 437 2.3.10.04b DCD19 438 2.3.10.05a.i DCD19 439 2.3.10.05a.ii DCD19 440 2.3.10.05a.iii DCD19 441 2.3.10.05b DCD19 442 2.3.10.06a DCD19 443 2.3.10.06b DCD19 444 2.3.10.07a.i DCD19 445 2.3.10.07a.ii DCD19 446 2.3.10.07b DCD19 447 2.3.10.08 DCD19 448 2.3.10.09 DCD19 449 2.3.10.10 DCD19 450 2.3.11.01 Gaseous Radwaste System DCD19 451 2.3.11.02.i DCD19 452 2.3.11.02.ii DCD19 453 2.3.11.02.iii DCD19 454 2.3.11.03a DCD19 455 2.3.11.03b DCD19 456 2.3.11.03c DCD19 457 2.3.12.01 Solid Radwaste System DCD19 458 2.3.12.02 DCD19 459 2.3.13.01 Primary Sampling System DCD19 460 2.3.13.02 DCD19 461 2.3.13.03 DCD19 462 2.3.13.04 DCD19 463 2.3.13.05.i DCD19 464 2.3.13.05.ii DCD19 465 2.3.13.05.iii DCD19 466 2.3.13.06a.i DCD19 467 2.3.13.06a.ii DCD19

12/05/2017 Revised Draft C-11 No.

ITAAC No.

Plant System ITAAC Source 468 2.3.13.06b DCD19 469 2.3.13.06c DCD19 470 2.3.13.07 Primary Sampling System (contd)

DCD19 471 2.3.13.08 DCD19 472 2.3.13.09 DCD19 473 2.3.13.10a DCD19 474 2.3.13.10b DCD19 475 2.3.13.11a DCD19 476 2.3.13.11b DCD19 477 2.3.13.12 DCD19 478 2.3.14.01 Demineralized Water Transfer and Storage System DCD19 479 2.3.14.02 DCD19 480 2.3.14.03 DCD19 481 2.3.14.04 DCD19 482 2.3.15.01 Compressed and Instrument Air System DCD19 483 2.3.15.02 DCD19 484 2.3.15.03 DCD19 485 2.3.19.01a Communication System DCD19 486 2.3.19.01b DCD19 487 2.3.19.02a DCD19 488 2.3.19.02b DCD19 489 2.3.29.01 Radioactive Waste Drain System DCD19 490 2.3.29.02 DCD19 491 2.3.29.03 DCD19 492 2.3.29.04 DCD19 493 2.4.01.01 Main and Startup Feedwater System DCD19 494 2.4.01.02 DCD19 495 2.4.01.03 DCD19 496 2.4.01.04 DCD19 497 2.4.02.01 Main Turbine System DCD19 498 2.4.02.02a DCD19 499 2.4.02.02b DCD19 500 2.4.02.02c DCD19 501 2.4.02.03.i DCD19 502 2.4.02.03.ii DCD19 503 2.4.02.03.iii DCD19 504 2.4.06.01 Condensate System DCD19 505 2.4.06.02 DCD19 506 2.5.01.01 Diverse Actuation System DCD19 507 2.5.01.02a DCD19 508 2.5.01.02b DCD19 509 2.5.01.02c.i DCD19 510 2.5.01.02c.ii DCD19 511 2.5.01.02d DCD19 512 2.5.01.03a DCD19 513 2.5.01.03b DCD19 514 2.5.01.03c DCD19 515 2.5.01.03d DCD19 516 2.5.01.03e DCD19

12/05/2017 Revised Draft C-12 No.

ITAAC No.

Plant System ITAAC Source 517 2.5.01.03f DCD19 518 2.5.01.03g DCD19 519 2.5.01.03h Diverse Actuation System (contd)

DCD19 520 2.5.01.04 DCD19 521 2.5.01.05 DCD19 522 2.5.02.01 Protection and Safety Monitoring System DCD19 523 2.5.02.02.i DCD19 524 2.5.02.02.ii DCD19 525 2.5.02.02.iii DCD19 526 2.5.02.03 DCD19 527 2.5.02.04 DCD19 528 2.5.02.05a DCD19 529 2.5.02.05b DCD19 530 2.5.02.06a.i DCD19 531 2.5.02.06a.ii DCD19 532 2.5.02.06b DCD19 533 2.5.02.06c.i DCD19 534 2.5.02.06c.ii DCD19 535 2.5.02.07a DCD19 536 2.5.02.07b DCD19 537 2.5.02.07c DCD19 538 2.5.02.07d DCD19 539 2.5.02.07e DCD19 540 2.5.02.08a.i DCD19 541 2.5.02.08a.ii DCD19 542 2.5.02.08a.iii DCD19 543 2.5.02.08b.i DCD19 544 2.5.02.08b.ii DCD19 545 2.5.02.08c DCD19 546 2.5.02.09a DCD19 547 2.5.02.09b DCD19 548 2.5.02.09c DCD19 549 2.5.02.09d DCD19 550 2.5.02.10 DCD19 551 2.5.02.11 DCD19 552 2.5.02.12 DCD19 553 2.5.02.13 DCD19 554 2.5.02.14 DCD19 555 2.5.03.01 Plant Control System DCD19 556 2.5.03.02 DCD19 557 2.5.04.01 Data Display and Processing System DCD19 558 2.5.04.02.i DCD19 559 2.5.04.02.ii DCD19 560 2.5.04.02.iii DCD19 561 2.5.04.03 DCD19 562 C.2.5.04.04a COL8 563 C.2.5.04.04b COL8 564 C.2.5.04.04c COL8 565 2.5.05.01 In-Core Instrumentation System DCD19

12/05/2017 Revised Draft C-13 No.

ITAAC No.

Plant System ITAAC Source 566 2.5.05.02.i DCD19 567 2.5.05.02.ii DCD19 568 2.5.05.02.iii In-Core Instrumentation System (contd)

DCD19 569 2.5.05.03a.i DCD19 570 2.5.05.03a.ii DCD19 571 2.5.05.03b DCD19 572 2.5.05.03c DCD19 573 2.5.05.04 DCD19 574 2.5.06.01 Special Monitoring System DCD19 575 2.5.06.02 DCD19 576 2.5.09.01 Seismic Monitoring System DCD19 577 2.5.09.02 DCD19 578 2.5.09.03 DCD19 579 2.6.01.01 Main AC Power System DCD19 580 2.6.01.02.i DCD19 581 2.6.01.02.ii DCD19 582 2.6.01.02.iii DCD19 583 2.6.01.03a DCD19 584 2.6.01.03b DCD19 585 2.6.01.04a DCD19 586 2.6.01.04b DCD19 587 2.6.01.04c DCD19 588 2.6.01.04d DCD19 589 2.6.01.04e DCD19 590 2.6.01.04f DCD19 591 2.6.01.05 DCD19 592 2.6.01.06 DCD19 593 2.6.02.01 Non-Class 1E DC & Uninterruptible Power Supply System DCD19 594 2.6.02.02a DCD19 595 2.6.02.02b DCD19 596 2.6.02.02c DCD19 597 2.6.03.01 Class 1E DC & Uninterruptible Power Supply System DCD19 598 2.6.03.02.i DCD19 599 2.6.03.02.ii DCD19 600 2.6.03.02.iii DCD19 601 2.6.03.03 DCD19 602 2.6.03.04a DCD19 603 2.6.03.04b DCD19 604 2.6.03.04c DCD19 605 2.6.03.04d DCD19 606 2.6.03.04e DCD19 607 2.6.03.04f DCD19 608 2.6.03.04g DCD19 609 2.6.03.04h DCD19 610 2.6.03.04i DCD19 611 2.6.03.05a DCD19 612 2.6.03.05b DCD19 613 2.6.03.05c DCD19 614 2.6.03.05d.i DCD19

12/05/2017 Revised Draft C-14 No.

ITAAC No.

Plant System ITAAC Source 615 2.6.03.05d.ii DCD19 616 2.6.03.06 DCD19 617 2.6.03.07 Class 1E DC & Uninterruptible Power Supply System DCD19 618 2.6.03.08 (contd)

DCD19 619 2.6.03.09 DCD19 620 2.6.03.10 DCD19 621 2.6.03.11 DCD19 622 2.6.04.01 Onsite Standby Power System DCD19 623 2.6.04.02a DCD19 624 2.6.04.02b DCD19 625 2.6.04.02c DCD19 626 2.6.04.03 DCD19 627 2.6.04.04 DCD19 628 2.6.05.01 Lighting System DCD19 629 2.6.05.02.i DCD19 630 2.6.05.02.ii DCD19 631 2.6.05.03.i DCD19 632 2.6.05.03.ii DCD19 633 2.6.05.04 DCD19 634 2.6.05.05.i DCD19 635 2.6.05.05.ii DCD19 636 2.6.05.06.i DCD19 637 2.6.05.06.ii DCD19 638 2.6.06.01.i Grounding and Lightning Protection System DCD19 639 2.6.06.01.ii DCD19 640 2.6.06.01.iii DCD19 641 2.6.06.01.iv DCD19 642 2.6.09.01 Plant Security System DCD19 643 2.6.09.03 DCD19 644 2.6.09.04 DCD19 645 2.6.09.05a DCD19 646 2.6.09.05b DCD19 647 2.6.09.05c DCD19 648 2.6.09.06 DCD19 649 2.6.09.07a DCD19 650 2.6.09.07b DCD19 651 2.6.09.08 DCD19 652 2.6.09.09 DCD19 653 2.6.09.13a DCD19 654 2.6.09.13b DCD19 655 2.6.09.13c DCD19 656 2.6.09.15a DCD19 657 2.6.09.15b DCD19 658 2.6.09.16 DCD19 659 C.2.6.09.01 Physical Security COL8 660 C.2.6.09.02 COL8 661 C.2.6.09.03a COL8 662 C.2.6.09.03b COL8 663 C.2.6.09.04a COL8

12/05/2017 Revised Draft C-15 No.

ITAAC No.

Plant System ITAAC Source 664 C.2.6.09.04b COL8 665 C.2.6.09.05a COL8 666 C.2.6.09.05b Physical Security (contd)

COL8 667 C.2.6.09.06 COL8 668 C.2.6.09.07 COL8 669 C.2.6.09.08a COL8 670 C.2.6.09.08b COL8 671 C.2.6.09.09 COL8 672 C.2.6.12.01 Offsite Power System COL8 673 C.2.6.12.02 COL8 674 C.2.6.12.03 COL8 675 C.2.6.12.04 COL8 676 C.2.6.12.05 COL8 677 C.2.6.12.06 COL8 678 C.2.6.12.07i COL8 679 C.2.6.12.07ii COL8 680 2.7.01.01 Nuclear Island Nonradioactive Ventilation System DCD19 681 2.7.01.02a DCD19 682 2.7.01.02b DCD19 683 2.7.01.03a DCD19 684 2.7.01.03b DCD19 685 2.7.01.04a DCD19 686 2.7.01.04b DCD19 687 2.7.01.05.i DCD19 688 2.7.01.05.ii DCD19 689 2.7.01.05.iii DCD19 690 2.7.01.06a DCD19 691 2.7.01.06b DCD19 692 2.7.01.07 DCD19 693 2.7.01.08a DCD19 694 2.7.01.08b DCD19 695 2.7.01.08c DCD19 696 2.7.01.08d DCD19 697 2.7.01.09 DCD19 698 2.7.01.10a DCD19 699 2.7.01.10b DCD19 700 2.7.01.11 DCD19 701 2.7.01.12 DCD19 702 2.7.01.13 DCD19 703 2.7.01.14 DCD19 704 2.7.02.01 Central Chilled Water System DCD19 705 2.7.02.02 DCD19 706 2.7.02.03a DCD19 707 2.7.02.03b DCD19 708 2.7.02.04 DCD19 709 2.7.02.05 DCD19 710 2.7.03.01 Annex/Auxiliary Building Nonradioactive Ventilation System DCD19 711 2.7.03.02a DCD19 712 2.7.03.02b DCD19

12/05/2017 Revised Draft C-16 No.

ITAAC No.

Plant System ITAAC Source 713 2.7.03.03 DCD19 714 2.7.03.04 DCD19 715 2.7.04.01 Diesel Generator Building Ventilation System DCD19 716 2.7.04.02a DCD19 717 2.7.04.02b DCD19 718 2.7.04.02c DCD19 719 2.7.04.03 DCD19 720 2.7.04.04 DCD19 721 2.7.05.01 Radiologically Controlled Area Ventilation System DCD19 722 2.7.05.02.i DCD19 723 2.7.05.02.ii DCD19 724 2.7.05.02.iii DCD19 725 2.7.05.03 DCD19 726 2.7.06.01 Containment Air Filtration System DCD19 727 2.7.06.02.i DCD19 728 2.7.06.02.ii DCD19 729 2.7.06.03.i DCD19 730 2.7.06.03.ii DCD19 731 2.7.06.03.iii DCD19 732 2.7.06.04 DCD19 733 2.7.06.05 DCD19 734 2.7.07.01 Containment Recirculation Cooling System DCD19 735 2.7.07.02 DCD19 736 3.1.00.01 Emergency Response Facilities DCD19 737 3.1.00.02 DCD19 738 3.1.00.03 DCD19 739 3.1.00.04 DCD19 740 3.1.00.05 DCD19 741 3.1.00.06 DCD19 742 3.2.00.01a Human Factors Engineering DCD19 743 3.2.00.01b DCD19 744 3.2.00.01c.i DCD19 745 3.2.00.01c.ii DCD19 746 3.2.00.01d DCD19 747 3.2.00.01e DCD19 748 3.2.00.02 DCD19 749 3.2.00.03.i DCD19 750 3.2.00.03.ii DCD19 751 3.2.00.03.iii DCD19 752 3.2.00.03.iv DCD19 753 3.2.00.03.v DCD19 754 3.2.00.04 DCD19 755 3.2.00.05 DCD19 756 3.2.00.06.i DCD19 757 3.2.00.06.ii DCD19 758 3.2.00.06.iii DCD19 7589 3.2.00.07 DCD19 760 3.2.00.08 DCD19 761 3.2.00.09 DCD19

12/05/2017 Revised Draft C-17 No.

ITAAC No.

Plant System ITAAC Source 762 3.3.00.01 Buildings DCD19 763 3.3.00.02a.i.a DCD19 764 3.3.00.02a.i.b Buildings (contd)

DCD19 765 3.3.00.02a.i.c DCD19 766 3.3.00.02a.i.d DCD19 767 3.3.00.02a.ii.a DCD19 768 3.3.00.02a.ii.b DCD19 769 3.3.00.02a.ii.c DCD19 770 3.3.00.02a.ii.d DCD19 771 3.3.00.02a.ii.e DCD19 772 3.3.00.02a.ii.f DCD19 773 3.3.00.02b DCD19 774 3.3.00.02c DCD19 775 3.3.00.02d DCD19 776 3.3.00.02e DCD19 777 3.3.00.02f DCD19 778 3.3.00.02g DCD19 779 3.3.00.02h DCD19 780 3.3.00.03a DCD19 781 3.3.00.03b DCD19 782 3.3.00.03c DCD19 783 3.3.00.03d DCD19 784 3.3.00.04a DCD19 785 3.3.00.04b DCD19 786 3.3.00.04c DCD19 787 3.3.00.05a DCD19 788 3.3.00.05b DCD19 789 3.3.00.05c DCD19 790 3.3.00.06a DCD19 791 3.3.00.06b DCD19 792 3.3.00.07aa DCD19 793 3.3.00.07ab DCD19 794 3.3.00.07ac DCD19 795 3.3.00.07ba DCD19 796 3.3.00.07bb DCD19 797 3.3.00.07bc DCD19 798 3.3.00.07c.i.a DCD19 799 3.3.00.07c.i.b DCD19 800 3.3.00.07c.ii.a DCD19 801 3.3.00.07c.ii.b DCD19 802 3.3.00.07d.i DCD19 803 3.3.00.07d.ii.a DCD19 804 3.3.00.07d.ii.b DCD19 805 3.3.00.07d.ii.c DCD19 806 3.3.00.07d.iii.a DCD19 807 3.3.00.07d.iii.b DCD19 808 3.3.00.07d.iii.c DCD19 809 3.3.00.07d.iv.a DCD19 810 3.3.00.07d.iv.b DCD19

12/05/2017 Revised Draft C-18 No.

ITAAC No.

Plant System ITAAC Source 811 3.3.00.07d.iv.c DCD19 812 3.3.00.07d.v.a DCD19 813 3.3.00.07d.v.b Buildings (contd)

DCD19 814 3.3.00.07d.v.c DCD19 815 3.3.00.07e DCD19 816 3.3.00.08 DCD19 817 3.3.00.09 DCD19 818 3.3.00.10.i DCD19 819 3.3.00.10.ii DCD19 820 3.3.00.10.iii DCD19 821 3.3.00.12 DCD19 822 3.3.00.13 DCD19 823 3.3.00.14 DCD19 824 3.3.00.16 DCD19 825 3.3.00.17 DCD19 826 3.5.00.01.i Radiation Monitoring DCD19 827 3.5.00.01.ii DCD19 828 3.5.00.01.iii DCD19 829 3.5.00.02.i DCD19 830 3.5.00.02.ii DCD19 831 3.5.00.03 DCD19 832 3.5.00.04 DCD19 833 3.5.00.05 DCD19 834 3.5.00.06 DCD19 835 3.5.00.07 DCD19 836 3.5.00.08 DCD19 837 3.6.00.01.i Reactor Coolant Pressure Boundary Leak Detection System DCD19 838 3.6.00.01.ii DCD19 839 3.6.00.01.iii DCD19 840 3.6.00.01.iv DCD19 841 3.6.00.01.v DCD19 842 3.6.00.01.vi DCD19 843 3.6.00.01.vii DCD19 844 3.7.00.01 Design Reliability Assurance Program DCD19 845 C.3.8.01.01.01 Emergency Planning - Emergency Classification System COL8 846 C.3.8.01.01.02 COL8 847 C.3.8.01.02.01 Emergency Planning - Notification Methods and Procedure COL8 848 C.3.8.01.02.02 COL8 849 C.3.8.01.02.03 COL8 850 C.3.8.01.03.01 Emergency Planning - Emergency Communications COL8 851 C.3.8.01.03.02 COL8 852 C.3.8.01.04.01 Emergency Planning - Public Education and Information COL8 853 C.3.8.01.05.01.01 Emergency Planning - Emergency Facilities and Equipment COL8 854 C.3.8.01.05.01.02 COL8 855 C.3.8.01.05.01.03 COL8 856 C.3.8.01.05.01.04 COL8 857 C.3.8.01.05.01.05 COL8 858 C.3.8.01.05.01.06 COL8 859 C.3.8.01.05.01.07 COL8

12/05/2017 Revised Draft C-19 No.

ITAAC No.

Plant System ITAAC Source 860 C.3.8.01.05.01.08 Emergency Planning - Emergency Facilities and Equipment (contd)

COL8 861 C.3.8.01.05.02.01 COL8 862 C.3.8.01.05.02.02 COL8 863 C.3.8.01.05.02.03 COL8 864 C.3.8.01.06.01 Emergency Planning - Accident Assessment COL8 865 C.3.8.01.06.02 COL8 866 C.3.8.01.06.03 COL8 867 C.3.8.01.06.04 COL8 868 C.3.8.01.06.05 COL8 869 C.3.8.01.06.06 COL8 870 C.3.8.01.06.07 COL8 871 C.3.8.01.06.08 COL8 872 C.3.8.01.06.09 COL8 873 C.3.8.01.07.01 Emergency Planning - Protective Response COL8 874 C.3.8.01.08.01.01 Emergency Planning - Exercises and Drills COL8 875 C.3.8.01.08.01.02 COL8 876 C.3.8.01.08.01.03 COL8 877 C.3.8.01.09.01 Emergency Planning - Implementing Procedures COL8 878 C.3.8.02.01 Pipe Rupture Hazard Analysis COL8 879 C.3.8.03.01 Piping Design COL8 880 C.3.8.04.01 Waterproof Membrane COL8 881 C.3.8.05.01 Concrete Fill COL8 882 C.3.8.05.02a COL8 883 C.3.8.05.02b COL8 884 C.3.8.06.01.i Seismic Category I Structure Foundation Grouting COL8 885 C.3.8.06.01.ii COL8