IR 05000424/2017010

NRC Team Inspection Report 05000424/2017010 and 05000425/2017010

ML17345A892
Person / Time
Site:	Vogtle
Issue date:	12/11/2017
From:	Sandal S R Reactor Projects Region 2 Branch 6
To:	Myers D J Southern Nuclear Operating Co
References
IR 2017010
Download: ML17345A892 (14)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 December 11, 2017 Mr. Darin VP Nuclear Plant Site Southern Nuclear Operating Co., Inc.

Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830

SUBJECT: VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - NRC TEAM INSPECTION REPORT 05000424/2017010 AND 05000425/2017010

Dear Mr. Myers:

On November 17, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Vogtle Electric Generating Plant Units 1 and 2. The NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

The inspection examined activities conducted under your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commission's rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.

The NRC inspectors did not identify any finding or violation of more than minor significance. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov

/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely,

/RA/

Shane Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects

Docket Nos.: 50-424, 50-425

License Nos.: NPF-68, NPF-81

Enclosure: IR 05000424/2017010, 05000425/2017010 w/Attachment: Supplemental Information cc Distribution via ListServ

ML17345A892 OFFICE RII:DRP RII:DRP RII:DRP RII:DRP RII:DRP RII:DRP NAME RRodriguez AAlen SFreeman PMcKenna ABlamey SSandal DATE 11/28/2017 11/29/2017 11/28/2017 12/1/2017 12/8/2017 12/11/2017 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION II Docket No.: 50-424, 50-425 License No.: NPF-68, NPF-81 Report No.: 05000424/2017010, 05000425/2017010 Licensee: Southern Nuclear Operating Company, Inc Facility: Vogtle Electric Generating Plant, Units 1 and 2 Location: Waynesboro, GA 30830 Dates: November 13 - 16, 2017 Inspectors: P. McKenna, Senior Resident Inspector (Team Leader)

S. Freeman, Senior Reactor Analyst R. Rodriguez, Senior Project Engineer A. Alen, Resident Inspector Approved by: Shane Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects

SUMMARY

IR 05000424/2017010, 05000425/2017010; 11/13/2017 - 11/16/2017; Vogtle Electric Generating Plant, Units 1 and 2; Temporary Instruction 2515/191, Inspection of the

Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans.

The inspection covered a one-week inspection by one senior resident inspector, one senior reactor analyst, one senior project engineer, and one resident inspector. No NRC-identified or self-revealing findings were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 6.

No findings were identified.

REPORT DETAILS

OTHER ACTIVITIES

Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, and Emergency Preparedness

4OA5 Other Activities

(TI 2515/191)

The objectives of Temporary Instruction (TI) 2015/191, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans," were to verify that the licensee has adequately implemented the mitigation strategies as described in the licensee's Final Integrated Plan, which was described in a letter dated May 23, 2016, (ADAMS Accession No. ML16146A607), and the NRC's plant safety evaluation (ADAMS Accession No. ML16277A404), to verify that the licensee installed reliable water-level measurement instrumentation in the spent fuel pools. The purpose of this TI was also to verify the licensee has implemented Emergency Preparedness (EP) enhancements as described in the site-specific submittals and the NRC's safety assessments, including multi-unit dose assessment capability and enhancements to ensure that staffing was sufficient and communications can be maintained during such an event.

The inspection verified that plans for complying with NRC Orders EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond- Design-Basis External Events (ADAMS Accession No. ML12054A736) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation (ADAMS Accession No. ML12054A679) were in place and were being implemented by the licensee. Additionally, the inspection verified implementation of staffing and communications information provided in response to the March 12, 2012, request for information letter and multi-unit dose assessment information provided per COMSECY-13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons Learned, dated March 27, 2013, (ADAMS Accession No. ML12339A262).

The team discussed the plans and strategies with plant staff, reviewed documentation and, where appropriate, performed plant walkdowns to verify that the strategies could be implemented as stated in the licensee's submittals and the NRC staff prepared safety evaluation. For most strategies, this included verification that the strategy was feasible, procedures and/or guidance had been developed, training had been provided to plant staff, and required equipment had been identified and staged. Specific details of the team's inspection activities are described in the following sections.

1. Mitigation Strategies for Beyond-Design Basis External Events

a. Inspection Scope

The team examined the licensee's established guidelines and implementing procedures for the beyond-design basis mitigation strategies. The team assessed how the licensee coordinated and documented the interface/transition between existing off-normal and emergency operating procedures with the newly developed mitigation strategies. The team selected a number of mitigation strategies and conducted plant walkdowns with licensed operators and responsible plant staff to assess:

(1) the adequacy and completeness of the procedures;

(2) the familiarity of operators with the procedure objectives and specific guidance;

(3) the staging and compatibility of equipment; and

(4) the practicality of the operator actions prescribed by the procedures, consistent with the postulated scenarios. The team verified that a preventive maintenance program had been established for the Diverse and Flexible Coping Strategies (FLEX) portable equipment and that periodic equipment inventories were in place and being conducted. Additi onally, the team examined the introductory and planned periodic/refresher training provided to the Operations and Security staff most likely to be tasked with implementation of the FLEX mitigation strategies. The

team also reviewed the introductory and planned periodic training provided to the Emergency Response Organization personnel. Documents reviewed are listed in the

attachment.

b. Assessment

Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals and the associated safety evaluation and determined that the licensee was generally in compliance with NRC Order EA-12-049. The inspectors verified that the licensee satisfactorily:

• Developed and issued FLEX Support Guidelines (FSG) to implement the FLEX strategies for postulated external events.

• Integrated the FSGs into existing plant procedures such that entry into and departure from the FSGs were clear when using existing plant procedures.

• Protected FLEX equipment from site-specific hazards.

• Developed and implemented adequate testing and maintenance of FLEX equipment to ensure its availability and capability.

• Trained the staff to assure personnel proficiency in the mitigation of beyond-design-basis events.

• Developed means to ensure that the necessary off-site FLEX equipment would be available from off-site locations.

The inspectors verified that noncompliance with the current licensing requirements, and other issues identified during the inspection, were entered into the licensee's corrective action program.

c. Findings

No findings were identified.

2. Spent Fuel Pool Instrumentation

a. Inspection Scope

The team examined the licensee's newly installed spent fuel pool instrumentation. Specifically, the inspectors verified the sensors were installed as described in the plant-specific submittals and the associated safety evaluation and that the cabling for the power supplies and the indications for each channel were physically and electrically separated. Additionally, environmental conditions and accessibility of the instruments were evaluated. Documents reviewed are listed in the attachment.

b. Assessment

Based on samples selected for review, the inspectors determined that the licensee satisfactorily installed and established control of the spent fuel pool (SFP)instrumentation as described in the plant specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA-12-051. The inspectors verified that the licensee satisfactorily:

• Installed the SFP instrumentation sensors, cabling and power supplies to provide physical and electrical separation as described in the plant specific submittals and safety evaluation.

• Installed the SFP instrumentation display in the location, environmental conditions and accessibility as described in the plant specific submittals.

• Trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation.

• Developed and issued procedures for maintenance, testing, and use of the reliable SFP instrumentation.

The inspectors verified that noncompliance with the current licensing requirements, and other issues identified during the inspection, were entered into the licensee's corrective action program.

c. Findings

No findings were identified.

3. Staffing and Communication Request for Information

a. Inspection Scope

Through discussions with plant staff, review of documentation and plant walkdowns, the team verified that the licensee had implemented required changes to staffing, communications equipment, and facilities to support a multi-unit extended loss of offsite power scenario as described in the licensee's staffing assessment and the NRC safety assessment. The team also verified that the licensee had implemented dose assessment (including releases from spent fuel pools) capability using the licensee's site-specific dose assessment software and approach as described in the licensee's multi-unit dose assessment submittal. Documents reviewed are listed in the

attachment.

b. Assessment The inspectors reviewed information provided in the licensee's multi-unit dose submittal and in response to the NRC'S March 12, 2012, request for information letter and verified that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3 response to a large scale natural emergency event that resulted in an extended loss of all alternating current power (ELAP) to the site and impedes access to the site. The inspectors verified the following:

• Licensee satisfactorily implemented required staffing changes to support an ELAP scenario.

• EP communications equipment and facilities were sufficient for dealing with an ELAP scenario.

• Implemented dose assessment capabilities (including releases from spent fuel pools) using the licensee's site-specific dose assessment software and approach.

The inspectors verified that noncompliance with the current licensing requirements, and other issues identified during the inspection, were entered into the licensee's corrective action program.

c. Findings

No findings were identified.

4OA6 Exit

Exit Meeting Summary

On November 16, 2017, the inspectors presented the inspection results to Mr. D. Myers and other members of the site staff. The inspectors confirmed that proprietary information was not provided or examined during the inspection.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

T. Baker, Security Manager

R. Bunt, Fleet Program Post-Fukushima Manager

J. Deal, Emergency Preparedness Supervisor

M. Euten, Fleet Licensing Engineer

T. English, Shift Operator

D. Komm, Plant Manager

T. Maddox, Senior Program Engineer

E. Murphy, Shift Support Supervisor

D. Myers, Site Vice President

T. Petrak, FLEX Project Manager

K. Walden, Licensing Engineer

E. Tew, Licensing Supervisor

K. Yechou, Shift Operator

T. Yonce, Shift Operator

NRC personnel

J. Quinnones-Navarro, NRR/DLP/PBEB

M. Endress, Vogtle Senior Resident Inspector

LIST OF REPORT ITEMS

Opened and Closed

None

Complete TI-2515/191, Appendix A, Mitigating Strategies for Beyond Design Basis Events

TI-2515/191, Appendix B, Spent Fuel Pool Instrumentation TI-2515/191, Appendix C, Staffing and Communications Request for Information

LIST OF DOCUMENTS REVIEWED

Procedures

00012-C, Shift Manning Requirements, Ver. 20.1 11431-1, 120V AC 1E Vital Instrument Distribution System Alignment, Ver. 8.2

14958-C, Fire Brigade Equipment - Quarterly Inspection (FSAR Fire Protection Surveillance),

Ver. 44

18031-1/2, Loss of Class 1 E Elect Systems, Ver. 1.1 19100-1, ECA 0.0, Loss of all AC Power, Ver. 4 19100-2, ECA 0.0, Loss of all AC Power, Ver. 5.2

23982-1, Spent Fuel Pool Back-Up Level Indication System 1L-5331 Channel Functional Check and Channel Calibration, Ver. 4

23989-2, Spent Fuel Pool Back-Up Level Indication System 2L-5331 Channel Functional Check and Channel Calibration, Ver. 5

NMP-AD-008, Applicability Determinations, Ver. 20.0

NMP-AD-008-F01, Applicability Determination, Ver. 11.1

NMP-EP-147, Offsite Dose Assessment, Ver. 2.0

NMP-EP-147-004, Vogtle Units 1 and 2

MIDAS-NU Dose Projections, Ver. 1.0

NMP-GM-038, Diverse and Flexible Coping Strategies (FLEX) Program, Ver. 2.0

NMP-GM-038-003, Vogtle Electric Generating Plant Diverse and Flexible Coping Strategies (FLEX) Program, Ver. 1.2

NMP-OS-014-003 VNP Time Critical Operator Action Program Ver. 3.1

NMP-OS-018-305, Unit 1

FSG-5, Initial Assessment and FLEX Equipment Staging, Ver. 1.1

NMP-OS-018-306, Unit 1

FSG-6, Alternate CST Makeup, Ver. 1.0

NMP-OS-019, Beyond Design Bases Events, Ver. 1.0

NMP-OS-019-001, EOF Support for Beyond Design Bases Events, Ver. 2.0

NMP-OS-019-001, Security Support for Beyond Design Bases Events, Ver. 1.1

NMP-OS-019-003, Security Support for Beyond Design Basis Events, Ver. 1.1

NMP-OS-019-304, Unit 1

FSG-4, ELAP DC Load Management, Ver. 1.1

NMP-OS-019-305, FSG 5 Initial Assessment and FLEX Equipment Staging, Ver. 1.1

NMP-OS-019-362, Unit 1

SIG-2, 480V Power, Ver. 3.2

NMP-OS-019-363, Unit 1

SIG-3, Core Cooling, Ver. 4.1

NMP-OS-019-367, Unit C

SIG-7 Diesel Fuel Oil Transfer, Ver. 1.0

NMP-OS-019-368, Vogtle Unit C

SIG-8, Spent Fuel Pool Makeup, Ver. 1.3

NMP-OS-019-370, Vogtle Unit C

SIG-10, Ventilation, Ver. 2

NMP-OS-019-391, Steam Generator FLEX Pump Operating Instructions, Ver. 1.0

NMP-OS-019-395, Light Towers Operating Instructions, Ver. 1

SNC Standard Emergency Plan Annex for VEGP Units 1 and 2, Ver. 1

V-IC-PP-07010, I&C FLEX Equipment Set-up, Communications, Rev. 1.0

V-IC-CO-20153, Curriculum Outline Instrument and Control Maintenance, Rev. 1.0 V-IC-215, Curriculum Outline Instrument and Control Maintenance for Mitigating Core Damage,

Rev. 7

Drawings

1X3D-BH-G01X, Elementary Diagram - Diesel Gen Fuel Oil & Air Start System -

1-2403-P4-001-M01, Rev. 6 1X3D-BH-G01Z, Elementary Diagram - Diesel G

en Fuel Oil & Air Start System -

1-2403-P4-002-M01, Rev. 4 1X3D-BH-G02B, Elementary Diagram - Diesel Gen Fuel Oil & Air Start System -

1-2403-P4-003-M01, Rev. 7 1X3D-BH-G02D, Elementary Diagram - Diesel Gen Fuel Oil & Air Start System -

1-2403-P4-004-M01, Rev. 6 1X4DB161-1, P&I Diagram - Auxiliary Feedwater System Condensate Storage & Degasifier - System No. 1302, Ver. 46.0

1X4DB161-2, P&I Diagram - Auxiliary Feedwater - System No. 1302, Ver. 29.0 1X4DB161-3, P&I Diagram - Auxiliary Feedwater Pump System (Auxiliary Feedwater Pump Turbine Driver) - System No. 1302, Ver. 42.0 1X4DB184, P&I Diagram - Reactor Make-up Water Storage Tank and Degasifier - System No.

28, Ver. 33.0 2X4DB161-1, P&I Diagram - Auxiliary Feedwater System Condensate Storage & Degasifier - System No. 1302, Ver. 37.0 2X4DB161-2, P&I Diagram - Auxiliary Feedwater - System No. 1302, Ver. 26.0 2X4DB161-3, P&I Diagram - Auxiliary Feedwater Pump System (Auxiliary Feedwater Pump Turbine Driver) - System No. 1302, Ver. 38.0 2X4DB184, P&I Diagram - Reactor Make-up Water Storage Tank and Degasifier - System No.

28, Ver. 28.0 AX4DR023, Volumes and Water Elevations in the Primary System, Ver. 4.0

Condition Reports

Reviewed

10081911

10167427

10168657

10181425

10182267

10218389

225117

10263821

10280033

10284813

10329548

10333989

10343882

10345429

10373730

10375054

10388817

10393869

10397553

10406848

10417479

Condition Reports

Generated as part of the Inspection

10431404, Revise

NMP-OS-019-033

10431425, Revise Procedure

NMP-GM-038

10431490, FLEX Equipment Procedures

SIG-4 and

SIG-10 Discrepancies

10431494, FLEX Procedures Figures Unreadable

10431496, Equipment Found Parking in FLEX No Parking Zone

10431498, Review and Update

NMP-GM-038 and

NMP-GM-038-003

Work Orders/Work Requests: SNC766504, Unit 1 SFP Backup Level Channel Cal, 60 days prior to refueling outage, 02/27/16 SNC769448, Unit 1 SFP Backup Level Channel Cal, 60 days prior to refueling outage, 03/6/17

SNC766503, Unit 1 SFP Backup Level Channel Cal, 60 days prior to refueling outage, 03/8/17

SNC618138, Unit 2 SFP Primary Level Functional Check or Channel Cal (60 days prior to outage), 08/12/17 SNC813736, Unit 2 SFP Primary Level Functional Check or Channel Cal (60 days prior to outage), 08/16/17

SNC611957, Unit 1 Spent Fuel Pool Level Probe 1 Site Acceptance Test, 10/07/15 SNC576693, Unit 2 Spent Fuel Pool Level Probe 1 Site Acceptance Test, 10/21/15 SNC824575, A2800A4043 - 6 Month FLEX PM:

Rapidcom Communications Functional Test and

Inspection, 09/02/17 SNC824576, A2800A4044 - 6 Month FLEX PM:

Rapid Communications Functional Test and

Inspection, 10/19/17

SNC829177, A2800P4015 - FLEX 1Y PM - Makeup FLEX Pump Operational Inspection, 08/16/17

SNC829179, A2800P4016 - FLEX PM Makeup FLEX Pump Operational Inspection, 08/16/17

SNC829180, A2800P4001 - FLEX PM: SG FLEX Pump Operational Inspection, 08/14/17 SNC829182, A2800P4002 - FLEX PM: SG FLEX Pump Operational Inspection, 08/17/17 SNC829194, A2800G4014 - FLEX

PM 480V FLEX Generator Operational Inspection, 08/15/17 SNC829192, A2800G4012 - FLEX

PM 480V FLEX Generator Operational Inspection, 08/16/17 SNC829183, A2800P4003 - FLEX 1YR PM - SG FLEX Pump Operational Inspection, 08/16/17

SNC853909, A2800A4043 - Update Required for SAM/FLEX Satellite Communication

Equipment, 04/06/17 SNC866708, A-2800-A4-009 - 20KW FLEX D/G Battery is Assumed Dead, Rev. 0

Preventative Maintenance Procedures

A2800R5002, SG FLEX Pump Functional Test & Inspection A2800R5004, 480V FLEX Functional Test & Inspection

A2800R5005, SG FLEX Pump Functional Test & Inspection

A2800R5011, Boron Injection Pump Operational Inspection

A2800R0514, Submersible Pump Functional Test & Inspection

A2800R5016, RCS Makeup Pump Functional Test & Inspection A2800R5019, Makeup FLEX Pump Functional Test & Inspection A2800R5014, 480V FLEX Generator Operational Inspection

A2800R5027, Submersible Pump Operational Inspection & Performance Test

A2800R5038, SG FLEX Pump Operational Inspection & Performance Test

A2800R5051, 480V FLEX Generator Off-line Testing A2800R5055, 480V FLEX Generator Full Load Test A2800R5059, RCS Makeup Pump 100% Performance Test

A2800R5063, Boron Injection Pump 100% Performance Test

A2800R5066, FLEX Hose Inspection & Testing

A2800R5068, FLEX Cable Inspection & Insulation Testing A2800R5077, FLEX Standby Walkdown Visual Inspection of FSB Equipment A2800R5079, FLEX FSB Equipment Inventory

A2800R5080, FLEX Protected Area Equipment Inventory

Correspondence

NL-13-013, Vogtle Electric Generating Plant -Units 1 and 2, Southern Nuclear Operating Company's Overall Integrated Plan In Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-

2-051), 02/27/13 NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident, 03/12/12 (ADAMS Accession No. ML12053A340) NRC Letter, Vogtle Electric Generating Plant, Units 1 and 2 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders

EA-12-049 and

EA-12-051, 11/14/16 (ADAMS Accession No. ML16301A419)

Southern Nuclear Operating Company Letter (NL-13-0987), Joseph M. Farley Nuclear Plant - Units 1 &2, Edwin I. Hatch Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Nuclear Plant - Units 1 & 2, Capability to Perform Emergency Multi-Unit Offsite Dose Assessments, 06/24/13

Southern Nuclear Operating Company Letter (NL-14-0585), Vogtle Electric Generating Nuclear Plant - Units 1 & 2 - Response to Request for Information Pursuant to Title 10CFR50.54(f)

Regarding Recommendations 2.1, 2.3, and 9.3, of the NTTF Review of Insights from Fukushima Daiichi Accident, dated March 12, 2012, 05/16/14 Southern Nuclear Operating Company Letter, 60-Day Response to NRC Letter, Request for Information Pursuant to Title 10

CFR 50.54( f) Regarding Recommendations 2.1,.2.3, and 9.3 of the NTTF Review of Insights from the Fukushima Daiichi Accident, dated March 12, 2012, 05/09/12

Other AREVA Report No. 38-9238015-000, SAFER Response Plan for Vogtle Electric Generating Plant, Rev. 1 DCP SNC473105, Unit 1 FLEX Alternate Power, Ver. 4.0

DCP SNC475956, Unit 2 FLEX Core Cooling, Ver. 2.0

DCP SNC475965, Unit 2 FLEX Alternate Power, Ver. 6.0 DCP SNC475966, Unit 2 FLEX Boron Injection and RCS Feed, Ver. 3.0

DCP SNC475969, Unit 2 FLEX Tank Makeup, Ver. 3.0

DCP SNC475972, Unit 1 FLEX Tank Makeup, Ver. 2.0

DCP SNC475973, Unit 1 FLEX Boron Injection and RCS Feed, Ver. 2.0

DCP SNC477823, Unit 1 FLEX Core Cooling, Ver. 3.0

DCP SNC583177, Unit 1 Spent Fuel Pool Level Indication, Ver. 3.0 DCP SNC521783, Spent Fuel Level Instrumentation System (Unit 2), Ver. 4.0

Focused Area Self-Assessment, VEGP 1&2 FLEX Compliance, 8/17/17

NANTEL Training Records for ERO, 2014 - 2017

NEI 10-05, Assessment of On-Shift Emergency Response Organization Staffing and Capabilities, Rev. 0

NEI 12-01 , Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities, Rev. 0

NEI 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Rev. 2

Operator Course Completion Record, 2015 Licensed Operator Requalification, Segment 4, 06/15/15 to 07/17/15 NSIR/DPR-ISG-01, Interim Staff Guidance - Emergency Planning for Nuclear Power Plants, Rev. 0 (ADAMS Accession No. ML113010523)

Standing Order

C-2016-9, Tornado Missile Vulnerabilities, Rev. 2.0

RapidCom Functional Test and Inspection Work Instructions RapidCase Functional Test and Inspection Work Instructions SNC528260, FLEX Building Ground Prep and Infrastructure, Sequence 1, 10/13/14 SNC528260, FLEX Building Ground Prep and Infrastructure, Sequence 2, 10/04/15

SNCV065-PR-002, Engineering Report - Diverse and Flexible Coping Strategies (FLEX) in Response to NRC Order

EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events for Southern Nuclear Operating Company Vogtle Electric Generating Plant, Rev. 2

Southern Nuclear Operating Company STANDARD EMERGENCY PLAN ANNEX for Vogtle Electric Generating Plant Units 1 and 2, Ver. 1 Southern Nuclear Operating Company Standard Emergency Plan, Ver. 1

TE 921511, Add Additional Protection for Flex Conduit, 09/05/15

TE 947083, FLEX Transfer Switch 2ABE37T in the FLEX Position with Battery Charger 2CD1CA

Low Current, 01/21/16

TE 953763, Vogtle FLEX Staffing Study Update, 03/09/16

TE 998411, Update to FLEX Documentation, 11/16/17

Vogtle Electric Generating Plant FLEX Verification & Validation Report, approved 10/14/15

Vogtle Electric Generating Plant -Units 1 and 2, Final Integrated Plan, U.S. Nuclear Regulatory

Commission Order

EA-12-049, Strategies for beyond Design Basis External Events, Ver. 1,

Vogtle Startup Safety Assessment (Unit 2), Beyond Design Basis External Event Mitigation

Strategies, 01/08/16

Vogtle Units 1 and 2 Notification of Full Compliance of Required Action for NRC Order

EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events, 05/23/16 Vogtle Units 1 and 2 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel pool Instrumentation Related to Orders

EA-12-049 and

EA-12-051, 11/14/16 X1AR50, Procurement Specification for FLEX Equipment Storage Building for Alvin Vogtle Electric Generating Plant - Units 1 and 2, Edwin I. Hatch - Units 1 and 2, Joseph M. Farley -

Units 1 and 2, Ver. 2.0 X4C1531S05,

Main Control Room Heat-up During an Extended Loss of AC Power, Ver. 1

X4C1593S03, Vogtle Auxiliary Feedwater Pump House Heat-up Evaluation during an Extended Loss of all AC Power, Ver. 1.0