RS-13-131, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)

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First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
ML13241A035
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 08/28/2013
From: Jim Barstow
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
EA-12-049, RS-13-131, TMI-13-072
Download: ML13241A035 (19)


Text

1 Exelon Generation Order No. EA-12-049 RS-13-131 TMI-13-072 August 28, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)

References:

1. NRC Order Number EA-12-049, " Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12,2012
2. NRC Interim Staff Guidance JLD-ISG-2012-01 , "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," Revision 0, dated August 29, 2012
3. NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide,"

Revision 0, dated August 2012

4. Exelon Generation Company, LLC's Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated October 25, 2012
5. Exelon Generation Company, LLC Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated February 28, 2013 (RS-13-026)

On March 12, 2012, the Nuclear Regulatory Commission ("NRC" or "Commission") issued an order (Reference 1) to Exelon Generation Company, LLC (EGC). Reference 1 was immediately effective and directs EGC to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in of Reference 1.

u.s. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28, 2013 Page 2 Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI 12-06, Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the EGC initial status report regarding mitigation strategies. Reference 5 provided the Three Mile Island Nuclear Station, Unit 1 overall integrated plan.

Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports. The purpose of this letter is to provide the first six-month status report pursuant to Section IV, Condition C.2, of Reference 1, that delineates progress made in implementing the requirements of Reference 1. The enclosed report provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any.

This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-765-5525.

th I declare under penalty of perjury that the foregoing is true and correct. Executed on the 28 day of August 2013.

Respectfully submitted,

~~ ~

James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC

Enclosure:

1. Three Mile Island Nuclear Station, Unit 1 First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region I NRC Senior Resident Inspector - Three Mile Island Nuclear Station, Unit 1 NRC Project Manager, NRR - Three Mile Island Nuclear Station, Unit 1 Ms. Jessica A. Kratchman, NRR/JLD/PMB, NRC Mr. Robert J. Fretz, Jr, NRR/JLD/PMB, NRC Mr. Robert L. Dennig, NRRlDSS/SCVB, NRC Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Resources Chairman, Board of County Commissioners of Dauphin County, PA Chairman, Board of Supervisors of Londonderry Township, PA R. R. Janati, Commonwealth of Pennsylvania

u.s. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28, 2013 Page 3 bcc: Site Vice President - Three Mile Island Nuclear Station, Unit 1 Vice President Operations Support Plant Manager, Three Mile Island Nuclear Station, Unit 1 Site Engineering Director - Three Mile Island Nuclear Station, Unit 1 Regulatory Affairs Manager Regulatory Assurance Manager - Three Mile Island Nuclear Station, Unit 1 Severe Accident Management Director Site Operations Director - Three Mile Island Nuclear Station, Unit 1 Corporate licensing Manager - East Corporate licensing Director - East Exelon Records Management Vinod Aggarwal Steven Pierson David Schupp Mike Wynne

Enclosure Three Mile Island Nuclear Station, Unit 1 First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (15 pages)

Enclosure Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events 1 Introduction Three Mile Island Nuclear Station, Unit 1 (TMI) developed an Overall Integrated Plan (Reference 1 in Section 8), documenting the diverse and flexible strategies (FLEX), in response to Reference 2. This enclosure provides an update of milestone accomplishments since submittal of the Overall Integrated Plan, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.

2 Milestone Accomplishments None 3 Milestone Schedule Status The following provides an update to Attachment 2 of the Overall Integrated Plan. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed.

The revised milestone target completion dates do not impact the order implementation date.

Original Target Activity Status Completion Date

{Include date changes in this column}

Submit 60 Day Status Report Complete Submit Overall Integrated Complete Implementation Plan Contract with RRC Complete 6 Month Updates Update 1 Aug., 2013 Complete with this submittal Update 2 Feb., 2014 Not Started Update 3 Aug., 2014 Not Started Update 4 Feb., 2015 Not Started Page 1 of 15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Original Target Activity Status Completion Date

{Include date changes in this column}

Update 5 Aug., 2015 Not Started Update 6 Feb., 2016 Not Started Modification Development Oct 2014

  • Phase 1 modifications Not applicable Oct 2014
  • Phase 2 modifications Started Oct 2014
  • Phase 3 modifications Not Started Modification Implementation Nov 2015
  • Phase 1 modifications Not Applicable Nov 2015
  • Phase 2 modifications Not Started Nov 2015
  • Phase 3 modifications Not Started Procedure development Jun 2015
  • Create Site-Specific Started Procedures Nov 2015
  • Validate Procedures (NEI12- Started 06, Sect. 11.4.3)

Jun 2015

  • Create Maintenance Started Procedures Jul2015 Staffing analysis Not started Nov 2015 Storage Plan Started Nov 2015 FLEX equipment acquisition Started Nov 2015 Training completion Started Jul2015 Regional Response Center Started Operational Nov 2015 Unit 1 Implementation date Not Started 4 Changes to Compliance Method The following significant changes have been made to the FLEX conceptual designs
  • FLEX Diesel Generator Fuel Oil (Reference lE-919-21-001, DRAFT, attached)

Page 2 of 15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28, 2013 o One (1) 5000 gallon fuel oil tank replaces the two (2) 2600 gallons fuel oil tanks. This 5000 gallon tank will normally contain 100 gallons, enough to start and initially load the generators.

o Fuel oil tank supply is provided from 30,000 gallon underground tank (DF-T-l) using DF-P-l C or DF-P-l D.

  • FLEX Electrical Generation and Distribution (Reference lE-919-21-002, DRAFT, attached) o Flex Diesel Generators now feed a new, separate FLEX MCCIDistribution panel.

o Output from the generators is fed from the FLEX MCC to the crosstie buswork between the IP and IS 480V ES Buses o The FLEX Feedwater Pumps will be powered from the FLEX MCC.

  • FLEX RCS/Spent Fuel Pool Make-up (Reference lE-919-21-004, DRAFT, attached) oRCS Make Up system tie-in will be upstream of MU-V-16C and MU-V-16D, vice downstream.

oRCS Low-pressure make-up (when OTSGs are unavailable) is via the Low Pressure Injection lines

  • FLEX Feedwater (Reference lE-919-21-003, DRAFT, attached) o A diverse location for staging the FLEX Diesel-driven Feedwater Pump is established.

Sequence of Events Time-line Modifications (See Attachment 1A) - The following significant changes have been made to the time-line based on on-going strategy development:

1. Provisions have been added to isolate RC-P Controlled Bleed-off (CBO) flow early in the sequence.
2. RCS Cooldown has been deferred until Pressurizer Level is recovered and CBO flow has been isolated.
3. Back-up Feedwater capability will not be available until the RCS cool down has been completed to achieve an OTSG Pressure < 200 psig.
4. Actions to set-up off-site communications trailer have been incorporated.
5. Actions added to line-up and fill FLEX Diesel Generator Fuel Oil Tank.

5 Need for RelieflRelaxation and Basis for the ReIieflRelaxation TMI expects to comply with the order implementation date and no relief/relaxation is required at this time.

6 Open Items from Overall Integrated Plan and Draft Safety Evaluation The following tables provide a summary of the open items documented in the Overall Integrated Plan or the Draft Safety Evaluation (SE) and the status of each item.

Section Reference OveraJJ Integrated Plan Open Item Status Key Site Assumptions (pg 3) and Routes from the storage locations have Started Strategy Deployment (pg 5) not yet been assessed for hazard impact.

Page 3 of 15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Section Reference Overall Integrated Plan Open Item Status This will be completed and communicated in a future 6-month update following evaluation.

Sequence of Events (pg 4) The times to complete actions in the Started Events Timeline are based on operating judgment, the conceptual designs, and the current supporting analyses. The final timeline will be validated once detailed designs are completed, procedures are developed, and the results will be provided in a future six (6) month update.

Maintain RCS Inventory (pg 17) Core cooling and RCS inventory analysis Started is not complete at this time. Completion of this analysis is an open item. Closure of this item will be documented in a future six (6) month update.

Maintain Core Cooling and Heat ECR 13-00071 FLEX Feedwater System Started Removal (pg 10) is not finalized. Changes will be provided in a 6-month update.

Maintain Core Cooling and Heat ECR 13-00074 FLEX Storage Building Started Removal (pg 10) is not finalized. Changes will be provided in a six (6) month update.

Maintain RCS Inventory (pg 16) ECR 13-00099 RC-P Low Leakage Seals Started is not finalized. Changes will be provided in a six (6) month update.

New ECR, no reference. ECR 13-00078 Turbine Building Started Structural Modifications is not finalized.

Changes will be provided in a six (6) month update.

New ECR, no reference. ECR 13-00164 FLEX Fuel Oil and Fire Started Protection is not finalized. Changes will be provided in a six (6) month update.

Maintain Core Cooling and Heat A portable refueling vehicle with a large Started Removal (pg 14) diesel oil bladder will be available on site to support refilling our portable equipment diesel tanks. An additional means (river makeup is available) of delivering condensate may also be developed, details to beprovided in a Page 4 of 15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Section Reference Overall Integrated Plan Open Item Status future 6-month update.

Maintain Spent Fuel Pool Spent Fuel Pool - These strategies utilize Started Cooling (pg 29) a vent path for steam. The effects of this steam on other systems and equipment will be evaluated, and the results will be provided in a future six month update.

Maintain Spent Fuel Pool ECR 13-00084 for Spent Fuel Pool Started Cooling (pg 30) Instrumentation. This ECR is an open item. Closure of this item will be documented in a future six (6) month update.

Maintain RCS Inventory (pg 18) ECR 13-00072, FLEX RCS Make-up Started System - This ECR is an open item.

Closure of this item will be documented in a future six (6) month update.

Maintain RCS Inventory (pg 22) A plan will be developed to re-supply Started borated water to the BWST or SF pool.

Maintain RCS Inventory (pg 17) TM-FLEX-OOl, Core Cooling Analysis, Started DRAFT, is not approved. The results of this analysis will be integrated into a future 6-month update.

Maintain Containment (pg 26) TM-FLEX-002, RB Pressure Analysis, Complete Rev 0 (Reference 4) , results show that Reactor Building pressure will remain below design pressure without any active means of RB cooling for any event where the OTSG is available to remove core heat.

Safety Function Support (pg 37) ECR 13-00070 FLEX Electrical Power Started Supply. This ECR is an open item.

Closure of this item will be documented in a future six (6) month update.

Safety Function Support (pg 37) Within the Main Control Room, Statted habitability conditions will be evaluated and a strategy will be developed to maintain Main Control Room habitability. The strategy will be provided in a future six (6) month update.

Page 5 of 15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28, 2013 Section Reference Overall Integrated Plan Open Item Status Draft Safety Evaluation Open Item Status TMI has not received a Draft Safety Not applicable Evaluation 7 Potential Draft Safety Evaluation Impacts There are no potential impacts to the Draft Safety Evaluation identified at this time.

8 References The following references support the updates to the Overall Integrated Plan described in this 6-month update.

1. Three Mile Island Nuclear Station, Unit 1, Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated February 28, 2013.
2. NRC Order Number EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, dated March 12,2012.
3. NEI 12-06, Rev. 0, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, dated August 2012.
4. TM-FLEX-002, Reactor Building Pressure Analysis for FLEX, Rev. 0 9 Attachments 1A. Sequence of Events Timeline Page 6 of 15

Attachment lA Sequence of Events Timeline Action item Elapsed Action Time Constraint Remarks I Applicability Time YIN 1 1 0 Earthquake or Tornado Event NA Plant @100% power Causes LOOP and damages unprotected equipment 2 0 All control rods inserted and NA Failures per reactor is shutdown.

JLD-ISG-2012-01 and NE112-Emergency Diesel Generators fail 06 to energize ES buses.

3 0 EFW actuated. N Automatic plant response Steam driven pump, EF-P-l, supplies feedwater.

MSSV & ADV control OTSG pressure 4 < 1 min EOP Initiated N 5 < 2min Letdown isolates (MU-V-3) N automatically on high temperature.

6 3 min Operators ensure each of the N following are closed:

Letdown isolation (MU-V-3)

RCP Controlled Bleed Off Isolation Valve (MU-V-26) 7 <5 min Operators attempt to start and N Failures per JLD-ISG-2012-01 load SBO Diesel Generator, and and NEI12-06. This signals an identify SBO DG is inoperable. ELAP condition.

S < 10 min Operators verify core cooling via N OTSG with RCS natural circulation, and throttle ADV to stabilize OTSG pressure 9 15 min Operator places ES Pumps, DC N Pumps and Breaker Extension 1 Instructions: Provide justification if No or NA is selected in the remark column If yes include technical basis discussion as requires by NEI 12-06 section 3.2.1.7 Page 7 of 15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28 , 2013 Action item Elapsed Action Time Constraint Remarks I Applicability Time YIN 1 Controls in PULL-TO-LOCK 10 15 min Operators locally open Main N This is a pre-condition to Condenser vent to atmosphere reduce DC loads, LO-P-6 and (Break Vacuum) and line up valves GN-P-2.

to vent Main Generator H2 to atmosphere 11 0:15 -1:15 Operator opens breakers on vital Y Load shedding required to instrument buses to shutdown maintain instrument buses.

instrument systems not required (C-ll01-734-E420-009, TMI-l for ELAP mitigation.

Extending Station Battery Life to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> under ELAP, DRAFT).

12 0:15 -1:15 Operators locally strip loads from N Pre-condition to lP/lS 480V Buses,lA & lB ES Item 21 MCC 13 0:15 -1:15 Operators locally lineup FLEX RCS N Pre-condition to Charging Pump from BWST or Item 21 Spent Fuel Pool to RCS, strip loads on lA ESV MCC and lA RADWASTE MCC 14 0:15 - 2:15 Dispatch personnel to move N Provide B/U for Steam Driven diesel-driven feed water pump into Emergency Feedwater Pump the turbine building.

15 25 min Operator secures FW Pump lube Y DC load shedding required to oil pumps LO-P-9A and LO-P-9B maintain instrument buses.

(C-ll01-734-E420-009, TMI-l Extending Station Battery Life to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> under ELAP, DRAFT).

16 35 min Main Generator pressure is less DC load shedding required to than 15 psig, operator secures maintain instrument buses.

Y Main Generator Seal Oil Pump (C-ll01-734-E420-009, TMI-l (GN-P-2).

Extending Station Battery Life to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> under ELAP, DRAFT).

17 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> When Main Turbine speed is DC load shedding required to reduced or within one hour of the maintain instrument buses for Y

event, Main Turbine Lube Oil 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Pump LO-P-6 is shutdown.

(C-ll01-734-E420-009, TMI-l Extending Station Battery Life to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> under ELAP, DRAFT).

18 1:15 - 2:00 Operator connects temporary N cable between lA ESV MCC Page 8 of 15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28 , 2013 Action item Elapsed Action Time Constraint Remarks I Applicability Time V/N 1 Welding Receptacle and lA RW MCC welding Receptacle 19 1:15 Operator Lines up Fuel Oil for FX- N V-1A/B and begins filling FX-T-2 20 1:30 Operators locally lineup FLEX N Pre-condition to Emergency Diesel Generator for Item 21 operation.

21 1:30-1:45 Operator locally starts FLEX Emergency Diesel Generator and N

locally closes breakers to energize lP and lS 480V bus Cross-tie Feed 22 1:45 - 2:30 Energize Cross tie between lP &

lS 480V Buses to energize lP and N

lS 4 to energize lP and lS 480V ES Buses Energize lAI1B ES MCC from lP/1S 480V Bus 23 2:00 - 3:00 Operators take LOCAL MANUAL N control of EFW Valves and ADVs 24 2:15 -3:00 Maintenance personnel return to N U2 IPSH to get the Satellite Trailer 25 2:15 -6:00 Maintenance personnel Connect N Diesel Driven FLEX Feedwater Pump to FLEX EFW Header 26 2:30 -3:00 Energize selected loads on lA and V Must be accomplished prior to lB ES MCC 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to ensure vital instrument power is Battery Chargers maintained AC Sources to Inverters (C-ll01-734-E420-009, TMI-l FLEX Emergency RCS Charging Extending Station Battery Life Pumps to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> under ELAP, DRAFT).

FLEX Emergency Lighting 27 2:45 Start FLEX Emergency RCS V Must be accomplished prior to Charging Pumps to restore RCS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to ensure OTSG heat inventory and initiate boration. removal is maintained.

TM-FLEX-001, DRAFT 28 3:00-4:00 Operator locally opens doors in V This condition is part of the Control Tower to establish basis for acceptable FLEX ventilation equipment cooling.

Page 9 of 15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28 , 2013 Action item Elapsed Action Time Constraint Remarks I Applicability Time YIN 1 29 3:00-4:00 Operators energize lA ESV MCC Y Within six (6) hours of event and lA RW MCC to CLOSE MU-V- initiation (TM-FlEX-001, 33A/B/C/D (RCP CBO) DRAFT) 30 3:00 - 4:30 Maintenance personnel position N Satellite trailer outside Ul MAF 31 4:30-6:00 Maintenance personnel return to N U21PSH 32 5:00 PZR Level recovered, commence N RCS cooldown at 10°FI Hr 33 5:00 RCS boron concentration sufficient Y Xenon reactivity worth to maintain Reactor Shutdown reduces below initial without Xenon reactivity. equilibrium concentration at approx. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

34 6:00 Complete backup feedwater pump N Provide B/U for Steam Driven connections to condensate supply Emergency Feedwater Pump and feedwater header.

Backup feedwater capability will be available when OTSG Pressure is < 200 pslg 35 6:00-10:30 Maintenance personnel position a N Precondition for item 36 diesel-driven portable pump at the ramp to the river, and route discharge hose to a functional condensate source (B CST or hotwell).

36 10:30 Diesel-driven portable pump is set Y After a tornado, condensate up to draft water from the river may be depleted in 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

and makeup to a Condensate Storage Tank or directly to the hotwell.

37 12:00 Line-up FLEX condensate feed to Y Spent fuel pool would not boil the Spent Fuel Pool. Monitor SF within 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

pool level and add water as needed to maintain level.

38 24:00 RRC (Regional Response Center) N

Reference:

JLD-ISG-2012-01 resources begin arriving on site. and NE112-06 39 24-72 Continue to maintain critical N End of analytical simulation.

Hours functions of Core Cooling, RCS Inventory Control and spent fuel Page 10 of15

Three Mile Island Nuclear Station, Unit 1 First Six Month Status Report for the Implementation of FLEX August 28 , 2013 Action item Elapsed Action Time Constraint Remarks I Applicability Time V/N 1 cooling.

Note: This timeline is based on best available information. It is subject to change based on outstanding analysis results and will be updated during a 6-month update Page 11 of 15

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