Text

Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses Re Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)
	ML16057A218
Person / Time
Site:	Quad Cities
Issue date:	02/26/2016
From:	Kaegi G; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	EA-12-049, RS-16-027
	Download: ML16057A218 (24)
	v • d • e

^~ ExeLon Generation.

Order No. EA-12-049 RS-16-027 February 26, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Sixth 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-13-025)

6. Exelon Generation Company, LLC 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 049), dated August 28, 2013 (RS-13-129)

7. Exelon Generation Company, LLC Second 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 049), dated February 28, 2014 (RS-14-015)

U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 February 26, 2016 Page 2

8. Exelon Generation Company, LLC Third 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 049), dated August 28, 2014 (RS-14-213)

9. Exelon Generation Company, LLC Fourth 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 049), dated February 27, 2015 (RS-15-024) 10.Exelon Generation Company, LLC Fifth 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 049), dated August 28, 2015 (RS-15-215) 11.NRC letter to Exelon Generation Company, LLC, Quad Cities Nuclear Power Station, Units 1 and 2 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC Nos. MF1048 and MF1049), dated November 22, 2013 12.NRC letter to Exelon Generation Company, LLC, Quad Cities Nuclear Power Station, Units 1 and 2 Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 (TAC Nos. MF1 048, MF1 049, MF1 052, and MF1 053), dated June 25, 2015 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.

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 Quad Cities Nuclear Power Station, Units 1 and 2 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. References 6, 7, 8, 9, and 10 provided the first, second, third, fourth, and fifth six-month status reports, respectively, pursuant to Section IV, Condition C.2, of Reference 1 for Quad Cities Station. The purpose of this letter is to provide the sixth 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. The enclosed report also addresses the NRC Interim Staff Evaluation Open and Confirmatory Items contained in Reference 11, and any NRC Audit Report open items contained in Reference 12.

U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 February 26, 2016 Page 3 This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-765-5525.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 26' day of February 2016.

Respectfully submitted, Glen T. Kaegi Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC

Enclosure:

1. Quad Cities Nuclear Power Station, Units 1 and 2 Sixth 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: NRC Regional Administrator - Region III NRC Senior Resident Inspector Quad Cities Nuclear Power Station, Units 1 and 2 NRC Project Manager, NRR Quad Cities Nuclear Power Station, Units 1 and 2 Mr. John P. Boska, NRR/JLD/JOMB, NRC Illinois Emergency Management Agency - Division of Nuclear Safety

Quad Cities Nuclear Power Station, Units 1 and 2 Sixth 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 (20 pages)

Enclosure Quad Cities Nuclear Power Station, Units 1 and 2 Sixth 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 Quad Cities Nuclear Power Station, Units 1 and 2, 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 last status report, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.

2 Milestone Accomplishments Construction of a deep well, the Robust Storage Building and the ASCE 7-10 FLEX +1 Storage Building have been completed since the last update.

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 target completion dates impact the Order implementation date. An explanation of the impact of these changes is provided in Section 5 of this enclosure.

Milestone Schedule Target Revised Target Milestone Completion Activity Status Completion Date Date Submit 60 Day Status Report Oct 2012 Complete Submit Overall Integrated Plan Feb 2013 Complete Contract with RRC Complete Submit 6 Month Updates:

Update 1 Aug 2013 Complete Update 2 Feb 2014 Complete Update 3 Aug 2014 Complete Update 4 Feb 2015 Complete Update 5 Aug 2015 Complete Update 6 Feb 2016 Complete with Page 1 of 20

Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 Target Revised Target Milestone Completion Activity Status Completion Date Date this submittal Update 7 Aug 2016 Not Started Modifications Development &

Implementation:

Unit 1 Modification Development (All Feb 2014 Completed April 2014 FLEX Phases)

Unit I Modification Implementation (All Apr 2015 Completed Mar 2015 FLEX Phases)

Unit 2 Modification Development (All Mar 2015 Completed FLEX Phases)

Unit 2 Modification Implementation (All Apr 2016 Started FLEX Phases)

Common Unit Modification Development (Interim Storage Pads and Mar 2015 Completed Dec 2015 Deep Well)

Common Unit Modification Implementation (Interim Storage Pads Mar 2015 Completed Dec 2015 and Deep Well)

Robust Storage Building Oct 2015 Completed ASCE 7-10 FLEX +1 Storage Building Apr 2016 Completed Jan 2016 Procedures:

Create Site-Specific Procedures Apr 2015 Completed Mar 2015 Validate Procedures (NEI 12-06, Sect.

Apr 2015 Completed Mar 2015 11.4.3)

Create Maintenance Procedures Apr 2015 Completed Mar 2015 Perform Staffing Analysis Nov 2014 Completed Storage Plan and Construction Apr 2015 Completed Jan 2016 FLEX Equipment Acquisition Apr 2015 Completed Mar 2015 Training Completion Apr 2015 Completed Mar 2015 National SAFER Response Center Completed Dec 2014 Mar 2015 Operational Unit 1 FLEX Implementation Apr 2015 Started Apr 2017 Page 2 of 20

Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 Target Revised Target Milestone Completion Activity Status Completion Date Date See Section 5 of this enclosure.

Apr 2018 Unit 2 FLEX Implementation Apr 2016 Started See Section 5 of this enclosure.

June 2017 Submit Unit 1 Compliance Report June 2015 Not Started See Section 5 of this enclosure.

June 2018 Submit Unit 2 Compliance Report June 2016 Not Started See Section 5 of this enclosure.

4 Changes to Compliance Method Change I- Interim FLEX Equipment Storage Alternative Approach:

Quad Cities Station has completed construction of the FLEX equipment storage buildings for the N and N+1 equipment. Therefore, Alternative Approach Change 1 - Interim FLEX Equipment Storage Alternative Approach is no longer applicable and FLEX Equipment is stored in accordance with Change 2 Alternative Approach below.

Change 2 - Storage, Maintenance and Testing Alternative Approach:

Exelon proposes an alternative approach to NEI 12-06, Revision 0 for protection of FLEX equipment as stated in Section 5.3.1 (seismic,) Section 7.3.1 (severe storms with high winds), and Section 8.3.1 (impact of snow, ice and extreme cold). This alternative approach will be to store "N" sets of equipment in a fully robust building and the +1 set of equipment in a commercial building. For all hazards scoped in for the site, the FLEX equipment will be stored in a configuration such that no one external event can reasonably fail the site FLEX capability (N).

To ensure that no one external event will reasonably fail the site FLEX capability (N), Exelon will ensure that N equipment is protected in the robust building. To accomplish this, Exelon will develop procedures to address the unavailability allowance as stated in NEI 12-06, Revision 0, Section 11.5.3., (see Maintenance and Testing section below for further details). This section allows for a 90-day period of unavailability. If a piece of FLEX equipment stored in the robust building were to become or found to be unavailable, Exelon will impose a shorter allowed outage time of 45 days. For portable equipment that is expected to be unavailable for more than 45 days, actions will be initiated within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of this determination to restore the site FLEX capability (N) in the Page 3 of 20

Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 robust storage location and implement-compensatory measures (e.g., move the +1 piece of equipment into the robust building) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months where the total unavailability time is not to exceed 45 days. Once the site FLEX capability (N) is restored in the robust storage location, Exelon will enter the 90-day allowed out of service time for unavailable equipment with an entry date and time based on the discovery date and time.

MAINTENANCE AND TESTING

1. The unavailability of equipment and applicable connections that directly performs a FLEX mitigation strategy for core, containment, and SFP should be managed such that risk to the mitigating strategy capability is minimized.

a. The unavailability of plant equipment is controlled by existing plant processes such as the Technical Specifications. When plant equipment which supports FLEX strategies becomes unavailable, then the FLEX strategy affected by this unavailability does not need to be maintained during the unavailability.

b. The required FLEX equipment may be unavailable for 90 days provided that the site FLEX capability (N) is met. If the site FLEX (N) capability is met but not protected for all of the site's applicable hazards, then the allowed unavailability is reduced to 45 days.'

c. The duration of FLEX equipment unavailability, discussed above, does not constitute a loss of reasonable protection from a diverse storage location protection strategy perspective.

d. If FLEX equipment or connections become unavailable such that the site FLEX capability (N) is not maintained, initiate actions within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore the site FLEX capability (N) and implement compensatory measures (e.g., use of alternate suitable equipment or supplemental personnel) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

e. If FLEX equipment or connections to permanent plant equipment required for FLEX strategies are unavailable for greater than 45/90 days, restore the FLEX capability or implement compensatory measures (e.g., use of alternate suitable equipment or supplemental personnel) prior to exceeding of the 45/90 days.

For Section 5, seismic hazard, Exelon will also incorporate these actions:

1 Large portable FLEX equipment such as pumps and power supplies should be secured as appropriate to protect them during a seismic event (i.e., Safe Shutdown Earthquake (SSE) level).

2. Stored equipment and structures will be evaluated and protected from seismic interactions to ensure that unsecured and/or non-seismic components do not damage the equipment.

For Section 7, severe storms with high winds, Exelon will also incorporate this action:

For a 2-unit site, 3 sets (N+l) of on-site FLEX equipment are required. The plant screens in per Sections 5 through 9 for seismic, flooding, wind (both tornado and hurricane), snow, ice and extreme cold, and high temperatures.

1 The spare FLEX equipment is not required for the FLEX capability to be met. The allowance of 90-day unavailability is based on a normal plant work cycle of 12 weeks. In cases where the remaining N equipment is not fully protected for the applicable site hazards, the unavailability allowance is reduced to 45 days to match a 6 week short cycle work period. Aligning the unavailability to the site work management program is important to keep maintenance of spare FLEX equipment from inappropriately superseding other more risk-significant work activities.

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Quad Cities Nuclear Power Station, Units I and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 o To meet Section 7.3.1.1.a, either of the following are acceptable:

o All three sets (N+I) in a structure(s) that meets the plant's design basis for high wind hazards, or o Two sets (N) in a structure(s) that meets the plant's design basis for high wind hazards and one set (+I) stored in a location not protected for a high wind hazard.

For Section 8, impact of snow, ice and extreme cold, Exelon will also incorporate this action:

Storage of FLEX equipment should account for the fact that the equipment will need to function in a timely manner. The equipment should be maintained at a temperature within a range to ensure its likely function when called upon. For example, by storage in a heated enclosure or by direct heating (e.g.,

jacket water, battery, engine block heater, etc.).

Exelon will meet all of the requirements in NEI 12-06, Revision 0 for Section 6.2.3.1 for external flood hazard and Section 9.3.1 for impact of high temperatures.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 Change 3 - N+1 Hoses and Cables Alternative Approach:

Issue:

An alternative is being proposed to the N+1 requirement applicable to hoses and cables as stated in Section 3.2.2 of NEI 12-06.

Background

NEI 12-06, Section 3.2.2 specifically states that a site will have FLEX equipment to meet the needs of each unit on a site plus one additional spare. This is commonly known as N+1 where N is the number of units at a given site. The relevant text from NEI 12-06 is as follows:

NEI 12-06, Section 3.2.2 states:

"In order to assure reliability and availability of the FLEX equipment required to meet these capabilities, the site should have sufficient equipment to address all functions at all units on-site, plus one additional spare, i.e., an N+1 capability, where "N" is the number of units on-site. Thus, a two-unit site would nominally have at least three portable pumps, three sets of portable ac/dc power supplies, three sets of hoses & cables, etc."

NEI 12-06, Section 11.3.3 states:

"FLEX mitigation equipment should be stored in a location or locations informed by evaluations performed per Sections 5 through 9 such that no one external event can reasonably fail the site FLEX capability (N)."

Typically the hoses utilized to implement a FLEX strategy are not a single continuous hose but are composed of individual sections of a smaller length joined together to form a sufficient length. In the case of cables, multiple individual lengths are used to construct a circuit such as in the case of 3-phase power.

Alternative:

NEI 12-06 currently requires N+1 sets of hoses and cables. As an alternative, the spare quantity of hose and cable is adequate if it meets either of the two methods described below:

Method 1: Provide additional hose or cable equivalent to 10% of the total length of each type/size of hose or cable necessary for the "N" capability. For each type/size of hose or cable needed for the "N" capability, at least 1 spare of the longest single section/length must be provided.

Example 1-1: An installation requiring 5,000 ft. of 5 in. diameter fire hose consisting of one hundreds 50 ft. sections would require 500 ft. of 5 in. diameter spare fire hose (i.e., ten 50 ft. sections).

Example 1-2: A pump requires a single 20 ft. suction hose of 4 in. diameter, its discharge is connected to a flanged hard pipe connection. One spare 4 in. diameter 20 ft. suction hose would be required.

Example 1-3: An electrical strategy requires 350 ft. cable runs of 4/0 cable to support 480 volt loads.

The cable runs are made up of 50 ft. sections coupled together. Eight cable runs (2 cable runs per phase and 2 cable runs for the neutral) totaling 2800 ft. of cable (56 sections) are required. A minimum of 280 ft. spare cable would be required or 6 spare 50 ft. sections.

Example 1-4: An electrical strategy requires 100 ft. of 4/0 cable (4 cables, 100 ft. each) to support one set of 4 kv loads and 50 ft. of 4/0 (4 cables, 50 ft. each) to support another section of 4 kv loads.

The total length of 4/0 cable is 600 ft. (100 ft. x 4 plus 50 ft. x 4). One spare 100' 4/0 cable would be required representing the longest single section/length.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 Method 2: Provide spare cabling and hose of sufficient length and sizing to replace the single longest run needed to support any single FLEX strategy.

Example 2-1 A FLEX strategy for a two unit site requires 8 runs each of 500 ft. of 5 in. diameter hose (4000 ft. per unit). The total length of 5 in. diameter hose required for the site is 8000 ft. with the longest run of 500 ft. Using this method, 500 ft. of 5 in. diameter spare hose would be required.

For either alternative method, both the N sets of hoses or cables and the spare set of hoses or cables would all be kept in a location that meets the reasonable protection requirements for the site.

The NRC has endorsed (ML15125A442) the NEI position paper (ML15126A135) for the above stated alternative approach. If using Method 2, per the endorsement letter, Exelon will ensure that the FLEX pumps and portable generators are confirmed to have sufficient capability to meet flow and electrical requirements when a longer spare hose/cable is substituted for a shorter length. Exelon acknowledges that the NRC staff has not reviewed and is not endorsing the specific examples included in the NEI endorsement request dated May 1, 2015.

Hoses and cables are passive devices unlikely to fail provided they are appropriately inspected and maintained.

The most likely cause of failure is mechanical damage during handling provided that the hoses and cables are stored in areas with suitable environmental conditions (e.g., cables stored in a dry condition and not subject to chemical or petroleum products). The hoses and cables for the FLEX strategies will be stored and maintained in accordance with manufacturers' recommendations including any shelf life requirements. Initial inspections and periodic inspections or testing will be incorporated into the site's maintenance and testing program implemented in accordance with Section 11.5 of NEI 12-06.

Therefore, the probability of a failure occurring during storage is minimal, resulting in the only likely failure occurring during implementation. Mechanical damage will likely occur in a single section versus a complete set of hose or cable. Therefore, the N+1 alternative addresses the longest individual section/length of hose or cable.

Providing either a spare cable or hose of a length of 10% of the total length necessary for the "N" capability or alternatively providing spare cabling or hose of sufficient length and sizing to replace the single longest run needed to support any single FLEX strategy is sufficient to ensure a strategy can be implemented. Mechanical damage during implementation can be compensated for by having enough spares to replace any damaged sections with margin. It is reasonable to expect that an entire set of hoses or cables would not be damaged provided they have been reasonably protected.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 Change 4 - Seismic Water Source Alternative Approach The station installed a single Deep Well as a seismically qualified source of water for the FLEX mitigation strategy. This single Deep Well is fully capable of supplying both Units 1 and 2 FLEX requirements simultaneously. Schedule relief for this well has been approved under References 13, 14 and 15. This configuration does not utilize a redundant seismic deep well. As such, Quad Cities will implement an Alternative Approach to meet the Order for allowed unavailability time on the single seismic deep well.

Background

Since only one deep well was installed, this alternative approach provides the actions that will occur upon unavailability of this deep well during maintenance and testing, or its unavailability during a FLEX event response. The plant circulating water discharge bay will be utilized as a source of backup water during deep well unavailablilty periods. The discharge bay has not been seismically evaluated but there is reasonable assurance that this water supply will remain available as a source of water following a seismic event due to the size of the two diffuser pipes which connect to the main channel of the Mississippi River.

To the extent to which the guidance of JLD-ISG-2012-01 and NEI 12-06 is being followed, deviations should be identified. The allowed unavailability time requirements are stated in NEI 12-06, Section 11.5.3 and are described as: "The unavailability of equipment and applicable connections that directly performs a FLEX mitigation strategy for core, containment, and SFP should be managed such that risk to mitigating strategy capability is minimized." As such, this alternative approach is an acceptable deviation from the guidance of JLD-ISG-2012-01 and NEI 12-06 as described below.

Alternative Unavailability Alternative Approach (Consistent with NEI 12-06, Section 11.5.3)

1. The unavailability of the seismic deep well equipment and applicable connections that directly performs a FLEX mitigation strategy for core, containment, and SFP should be managed such that risk to mitigating strategy capability is minimized.

a. The unavailability of installed plant equipment is controlled by existing plant processes such as the Technical Specifications (TS). When installed plant equipment which supports FLEX strategies becomes unavailable, then the FLEX strategy affected by this unavailability does not need to be maintained during the unavailability.

b. The required seismic deep well equipment may be unavailable for 90 days provided that the site seismic water supply capability is met. If the site seismic water supply capability is met but not fully protected for the site's applicable hazards, then the allowed unavailability is reduced to 45 days.

c. If seismic deep well equipment or connections become unavailable such that the site seismic water supply capability is not maintained, initiate actions within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore the site seismic water supply capability and implement compensatory measures (ensure equipment for use of the discharge Page 8 of 20

Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 bay water supply is ready for deployment) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and then initiate a concurrent 45-day period to repair the seismic well to full availability.

d. If seismic deep well permanently installed equipment required for FLEX strategies are expected to be unavailable for greater than 45 days, initiate actions to restore the seismic deep well capability and implement compensatory measures (e.g., use of alternate suitable equipment) prior to exceeding the 45 days.

Actions During a Seismic FLEX Event For an FLAP event with a seismic initiator the station will perform the following actions:

1. Phase I Actions:

Initiate RCIC for FLEX RPV water injection. RCIC will operate under these conditions for > 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . This will allow time for station staff to deploy Phase 2 FLEX strategies.

2. Phase 2:

Deploy FLEX generator to power the deep well for primary source of water for FLEX requirements for Suppression Chamber level control, Spent Fuel Pool level and Reactor Pressure Vessel water level control. The deep well pump is powered by one FLEX generator and the well is sufficient to provide water to both Units. Two additional FLEX generators are deployed, one per unit, to restore voltage to the 480V buses.

3. ERO Response Actions:

Following the initial stabilization actions for Phase 2, establish a backup water supply using a FLEX pump taking suction from the discharge bay.

Monitor the condition of Lock and Dam 14 for a potential failure and/or the discharge bay for level change that may be indicating a degradation of this source.

Upon indication or prediction of degradation of the discharge bay level, deploy a submersible pump with the suction placed in low point of the discharge bay with the discharge of the submersible pump connected to the FLEX pump suction to provide additional NPSH should the discharge bay level drop.

4. Continue to operate well pump or the submersible and FLEX pumps as required to supply the FLEX water needs.

Actions 1 4 above can be performed within the minimum time requirements needed for FLEX injection.

The discharge bay used in this strategy provides access for use of NSRC Phase 3 equipment as a backup to Phase 2 equipment and addresses indefinite coping time.

Actions During Maintenance or Testing Should the Deep Well Become Unavailable

1. Initiate actions to restore well pump within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. Verify FLEX and submersible pumps and necessary support components are ready for deployment and are protected from the seismic hazard. This contingency action is required to be completed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

3. Restore well pump to operation within 45 days.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 During times when the single seismic deep well is unavailable, Quad Cities will compensate by use of an Alternative Approach which consists of a FLEX pump and portable submersible pump that will take suction from Quad Cities Station discharge bay. The discharge bay will supply the necessary backup water supply.

Access to the river as a water source remains available during this event. This method provides a compensatory separate and diverse FLEX water supply, should the single seismic deep well become unavailable.

As a result, if the single seismic deep well becomes unavailable for a FLEX event (specifically a seismic event),

the Alternative Approach described herein will be utilized. This Approach applies a reduced Unavailability Time to the single seismic deep well, which when coupled with the associated compensatory measures, will be used to compensate when the seismic deep well is not available. If the equipment is not protected from the applicable hazards, instead of the NEI recommended 90-day unavailability period, an allowed unavailability period of 45 days will apply. This is based on the 6-week short cycle work scheduling. This will allow the station to continue to manage work associated with equipment important to safety. Placing the seismic deep well equipment into the site work schedule at the 6-week period still allows proper planning and resource loading while maintaining schedule compliance and stability. This action will not cause the station to be distracted from other scheduled work.

The probability of an event causing an FLAP and loss of the UHS is low and reducing the allowed unavailability time will further reduce the probability of an event during this period. Therefore, it is reasonable to expect equipment availability during periods when it is required.

Supporting Plant Conditions

Discharge Bay Water Level:

o Normal discharge bay and Mississippi River level is 572 feet controlled by downstream Lock and Dam 14.

o Per UFSAR 2.4.4, the minimum elevation of the discharge bay is 561 feet, should Lock and Dam 14 fail, which is the normal elevation downstream of Lock and Dam 14.

o Bottom elevation of discharge bay is 557 feet.

o Godwin FLEX pumps will provide the necessary water to a suction level of 565 feet which will be reached 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months after the Lock and Dam 14 failure per UFSAR 2.4.4.

o At 565 feet or lower, the station plans to use a submersible booster pump to provide additional required NPSH for the FLEX Godwin pump.

Torus and Reactor:

o Per EC 395980 and calc QDC-1300-M-2074 analysis, the RCIC system pump will have sufficient NPSH and is capable of operation greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Spent Fuel Pool:

o From Calculation QDC-1900-M-2079 for a Full Core Offload time to 12 ft. above fuel is 31.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and the time to 10 ft. is 38.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The more restrictive time of 31.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months will be utilized for this alternative approach.

Therefore, the shortest time that Phase 2 FLEX water injection is required is 31.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months based on Spent Fuel Pool water needs.

Discharge bay remains open to the river following the event. The diffuser piping (Two-16 ft. pipes) remains open to allow sufficient backflow from the Mississippi river main channel to the discharge bay and remains open to the river following the event.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016

The discharge bay bottom elevation is 557 feet. The minimum water level is 561 feet which is consistent with the normal water level downstream of Lock and Dam 14, should it fail. Therefore, a depth of 4 feet of usable water will remain available in the discharge bay and will be maintained by open path to the Mississippi River main channel via the diffuser piping.

The discharge bay is expected to remain accessible following the event due to its construction that utilizes a sheet pile enclosure reinforced with rip-rap slope stabilization.

The discharge bay pump pad was designed and installed to be seismically robust.

The travel path to the discharge bay was evaluated for liquefaction.

The station stores one FLEX pump in the FLEX storage building.

The NSRC will provide a diesel driven hydraulic submersible booster pump to provide the additional NPSH for the FLEX pump if the discharge bay level continues to drop below or is expected to degrade below 565 feet. Changes to the SAFER Response plan for Quad Cities Station have been completed to provide this pump as part of the Quad Cities Power Station equipment package within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of notification. (Reference 18) 5 Need for Relief/Relaxation and Basis for the Relief/Relaxation By letter dated February 27, 2014 (Ref. 5), Quad Cities Station requested relaxation from certain schedule requirements of Order EA-12-049 (Ref. 2) related to installation of the severe accident capable containment vent required by Order EA-13-109 (Ref. 3). The NRC granted that schedule relief via letter dated April 15, 2014 (Ref. 9).

By letter dated March 4, 2015 (Ref. 13) and supplemented by a letter dated March 6, 2015 (Ref. 14) Quad Cities Station requested schedule relaxation of the requirements of Order EA-12-049 (Ref. 2) related to the completion of installation of the mitigating strategies equipment and modifications to implement the strategies. The NRC granted the schedule relief via letter dated March 11, 2015(Ref. 15). The seismic deep well installation and associated modifications to implement the strategies were completed and made fully functional prior to the requested schedule relaxation date of December 11, 2015. As such, compliance with the requested schedule relaxation concerning the seismic deep well has been achieved.

No additional need for relief/relaxation relative to Order EA-12-049 has been identified at this time.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 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 (Reference 1) or the Draft Safety Evaluation (SE) (Reference 7), and the status of each item.

Section Overall Integrated Plan Open Item Status Reference Sequence of 1.The times to complete actions in the Completed - See August 2015 Six-month Events (p. 4) Events Timeline are based on operating Update.

judgment, conceptual designs, and current supporting analyses. The final timeline will be time validated once detailed designs are completed and procedures are developed, and the results will be provided in a future 6-month update.

Sequence of 2. Issuance of BWROG document NEDC- Completed - See August 2013 Six-Month Events (p. 33771P, "GEH Evaluation of FLEX update.

4,5) Implementation Guidelines," on 01/31/2013 did not allow sufficient time to perform the analysis of the deviations between Exelon's engineering analyses and the analyses contained in the BWROG document prior to submittal of this Integrated Plan. This analysis is expected to be completed, documented on Attachment I B, and provided to the NRC in the August 2013 Six-Month status update.

Sequence of 3. Additional work will be performed Completed - See August 2014 Six-Month Events (p. 6) during detailed design development to update.

ensure Suppression Pool temperature will support RCIC operation, in accordance with approved BWROG analysis, throughout the event.

Sequence of 4. Initial calculations were used to Completed - See August 2014 Six-Month Events (p. 7) determine the fuel pool timelines. Formal update.

calculations will be performed to validate this information during development of the Spent Fuel Pool Cooling strategy detailed designs, and will be provided in a future 6-month update.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation ofFLEX Section Overall Integrated Plan Open Item Status Reference Multiple 5. Procedures and programs will be Completed - See August 2015 Six-month Sections developed to address storage structure Update.

requirements, haul path requirements, and FLEX equipment requirements relative to the external hazards applicable to Quad Programmatic 6. Quad Cities Nuclear Power Station will Completed - See August 2015 Six-month controls (p. 8) implement an administrative program for Update.

FLEX to establish responsibilities, and testing and maintenance requirements.

Multiple 7. Detailed designs based on the current No additional design changes are required Sections conceptual designs will be developed to for implementation of FLEX. Installation determine the final plan and associated of all previously identified physical mitigating strategies. Analysis will be changes, except the HCVS components, performed to validate that the plant will be completed and authorized for use modifications, selected equipment, and in April 2016.

identified mitigating strategy can satisfy the safety function requirements of NEI 12-06.

Once these designs and mitigating strategies have been fully developed, Exelon will update the integrated plan for Quad Cities Nuclear Power Station during a scheduled 6-month update. This update will include any changes to the initial designs as submitted in this Integrated Plan.

Maintain 8. Guidance will be provided to ensure that Completed - See August 2015 Six-month Core Cooling sufficient area is available for deployment Update.

Phase 1 and that haul paths remain accessible (p. 13) without interference from outage equipment during refueling outages.

Maintain 9. Evaluation of the spent fuel pool area for Completed - See August 2015 Six-month Spent Fuel steam and condensation has not yet been Update.

Pool Cooling performed. The results of this evaluation Phase I and the vent path strategy, if needed, will be (p.32) provided in a future 6-month update.

Safety 10. Habitability conditions will be Completed - See August 2015 Six-month Function evaluated and a strategy will be developed Update.

Support (p. to maintain RCIC habitability.

42)

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 Section Overall Integrated Plan Open Item Status Reference Safety 11. Habitability conditions will be Complete. Duplicate of 3.2.4.6.A Function evaluated and a strategy will be developed Support (p. to maintain Main Control Room

42) habitability.

Safety 12. Battery Room Ventilation: Alternate Completed - See August 2015 Six-month Function ventilation will be provided to address Update.

Support (p. Hydrogen generation and cold weather, as

43) required.

Safety 13. Fuel Oil Supply to Portable Equipment: Completed - See August 2015 Six-month Function A detailed fuel oil supply plan will be Update.

Support (p. developed.

43) 4. Provide alternate cooling to the RCIC Completed - See August 2015 Six-month 1A, Item 20 rooms. Procedure to be developed. Update.

(p.59)

Section Interim Safety Evaluation Status Reference Open/Confirmatory Items 3.2.3.A SIGNIFICANT OPEN Item. Generic Completed - See February 2014 Six-concern related to adoption of Revision 3 to Month update.

the BWROG EPG/SAG [Emergency Procedure Guidelines/Severe Accident Guidelines] relating to potential detrimental effects on containment response.

3.2.4.6.A OPEN Item Licensee asserts 120 OF used Completed - See August 2015 Six-month for habitability in SBO is adequate for Update.

FLEX. Habitability of the control room should consider 110 degree F temperature limits of NUMARC 87-00 and MIL-STD-1472C.

3.3.2.A OPEN Item Control of equipment and Completed - See August 2015 Six-month connections for unavailability needs to be Update.

addressed.

3.4.B OPEN Item Details not provided to Completed - See February 2014 Six-demonstrate the minimum capabilities for Month update.

offsite resources will be met per NEI 12-06, Section 12.2.

3.1.1.2.A Confirmatory Item Studies for liquefaction Completed - See August 2015 Six-month and the effects on haul paths and storage Update.

location(s) are not complete.

3.1.1.2.B Confirmatory Item A postulated Completed - See August 2015 Six-month downstream dam failure from a seismic Update.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 event is still being evaluated.

3.1.1.2.0 Confirmatojy Item Need to confirm Completed - See August 2015 Six-month implementation of strategy for power to Update.

move or deploy FLEX equipment and opening of doors.

3.1.1.3.A Confirmatory Item Plans for strategies Completed - See August 2015 Six-month have insufficient information to Update.

demonstrate alternate sources of instrument readings and adequate tolerances/accuracies if there is seismic impact to primary sources. Also, need identification of installed instrumentation location and power source.

3.1.1.3.13 Confirmatory Item Need identification of Completed - See August 2014 Six-Month instrumentation used to monitor FLEX update.

electrical power equipment including measurement tolerance/accuracy.

3.1.2.2.A Confirmatory Item A detailed fuel supply Completed - See August 2015 Six-month plan is to be provided in a future 6-month Update.

status update including what is needed, what is available, and how it will be transported.

3.1.3.2.A Confirmatory Item Completion of Completed - See August 2015 Six-month development of an administrative program Update.

to ensure pathways remain clear or compensatory actions will be implemented to ensure all strategies can be deployed during all modes of operation. Procedures and programs are to be developed.

3.1.3.2.13 Confirmatory Item Completion of Completed - See August 2015 Six-month assessment on the adequacy of the debris Update.

removal equipment and the effect on the timeline to assure the critical times are capable of being met. This will be tracked as an open item in the 6-month update.

3.2.1. LA Confirmatory Item Need benchmarks to Completed - See August 2014 Six-month demonstrate Modular Accident Analysis update.

Program (MAAP)4 is the appropriate code for simulation of ELAP.

3.2.1.1.B. Confirmatory Item The collapsed level Completed - See August 2014 Six-Month must remain above Top of Active Fuel update.

(TAF) and the cool down rate must be within technical specification limits in the MAAP4 analysis.

3.2.1.1.C. Confirmatory Item MAAP4 must be used Completed - See August 2014 Six-Month in accordance with Sections 4.1, 4.2, 4.3, update.

4.4, and 4.5 of the June 2013 position paper.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 3.2. 1. I.D. Confirmatory Item In using MAAP4, the Completed - See August 2014 Six-Month licensee must identify and justify the subset update.

of key modeling parameters cited from Tables 4-1 through 4-6 of the "MAAP4 Application Guidance, Desktop Reference for Using MAAP4 Software, Revision 2" (Electric Power Research Institute Report 1 020236).

3.2. 1. I.E. Confirmatory Item The specific MAAP4 Completed - See August 2014 Six-Month analysis case that was used to validate the update.

timing of mitigating strategies in the integrated plan must be identified and available on the eportal for NRC staff to view. Alternately, a comparable level of information may be included in the supplemental response.

3.2.1.2.A. Confirmatory Item Questions remain Completed - See August 2015 Six-month unanswered regarding recirculation pump Update.

seal leakage rates. Aspects such as pressure dependence, leakage phase assumptions (single phase liquid, steam, mixed) are not discussed.

3.2.1.3.A. Confirmatory Item Need gap analysis Completed - See August 2015 Six-month between results of the licensee's analysis Update.

results and those of BWROG document NEDC-33771 P. Results are presented in 6- month update; however, there is no analysis of the relevance of differences.

3.2.1.3.B. Confirmatory Item Licensee plans further Completed - See August 2015 Six-month review and analysis to ensure suppression Update.

pool temperature will support RCIC operation.

3.2.1.3.0. Confirmatory Item Need identification of Completed - See February 2014 Six-the minimum voltage required for the dc Month update.

buses and the basis of that determination.

3.2.1.4.A. Confirmatory Item Water quality issue and Completed - See August 2015 Six-month guidance on priority of water source usage Update.

need to be addressed.

3.2.1.4.13. ConfirmatoKy Item Need completion of Completed - See August 2015 Six-month current evaluation of FLEX generator Update.

sizing calculation.

3.2.1.4.C. Confirmatory Item Need design and Completed - See August 2015 Six-month working pressure of hoses and fittings. Update.

3.2.1.6.A. Confirmatory Item Licensee identified Completed - See August 2015 Six-month protection of equipment for Hardened Vent Update.

is to Order EA-13-109 (Reference 22).

Explain if this is equivalent to Order EA-12-049, as Order EA-13-109 does not Page 16 of 20

Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 require protection from external events.

3.2.2.A. Confirmatory Item The licensee identified Completed - See August 2015 Six-month modifications and procedures for SFP Update.

cooling are in development.

3.2.4.2.A. Confirmatory Item Modifications to restore Completed - See August 2014 Six-Month RCIC room cooling are being developed by update.

the licensee.

3.2.4.2.B. Confirmatory Item Modifications to restore Completed - See August 2014 Six-Month ventilation to the battery rooms via use of update.

the portable FLEX generators to address hydrogen and cold weather are being developed by the licensee.

3.2.4.4.A. Confirmatory Item Procedures for Completed - See August 2015 Six-month emergency lighting are to be developed for Update.

deployment of hands free flashlights.

3.2.4.4.B. Confirmatory Item Confirm upgrades to Completed - See August 2015 Six-month communication system that resulted from Update.

the licensee communications assessment.

(ADAMS Accession Nos. ML12306A199 and ML13056A135.)

3.2.4.5.A. Confirmatory Item Verify completion of Completed - See August 2015 Six-month drafted procedures for protected and Update.

internal locked area access.

3.2.4.6.B. Confirmatory Item Site industrial Completed - See February 2014 Six-procedures and identification of protective Month Update.

clothing, ice vests/packs, bottled water, etc.

is needed.

3.2.4.6.C. Confirmatory Item Need to address the use Completed - See August 2015 Six-month of appropriate human performance aids Update.

(e.g., component marking, connection schematics, installation sketches, photographs, etc.) which shall be included in the FLEX guidance implementing the FLEX strategies.

3.2.4.8.A. Confirmatory Item The licensee did not Completed - See August 2015 Six-month provide any information regarding Update.

loading/sizing calculations of portable diesel generators(s) and strategy for electrical isolation for FLEX electrical aenerators from installed plant equipment.

3.2.4.9.A. Confirmatory Item Need detailed fuel plan Completed - See August 2015 Six-month including fuel storage tank, truck, and day Update.

tank volumes and how fuel quality is maintained in the day tanks and in portable FLEX equipment.

3.2.4.10.A. Confirmatory Item Need detailed battery Completed - See August 2015 Six-month load profile for all mitigating strategies and Update.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 a detailed discussion of loads that will be shed, how they will be shed, and what are the effects of the load shed.

3A.A. Confirmatory Item Procedures for interface Completed - See August 2015 Six-month with the NSRC need to be developed. Update.

I I I I NRC FLEX Audit Report Open Items 3.1.1.2.13 Confirmatory Item A postulated Completed - See August 2015 Six-month downstream dam failure from a seismic Update.

event is still being evaluated.

AQ 28-B The licensee stated that it can mitigate the Completed - See August 2015 Six-month effects of an ELAP indefinitely using phase Update.

two portable equipment and utilizing the Phase 3 NSRC equipment as back-up for reliability if needed. However, for a seismic event the licensee only has one seismically qualified well pump, and there is no NSRC equipment that can substitute for the well pump. Although there will be a spare well pump at the site, the replacement time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AQ 49-B, SE Provide details of the maintenance and Completed - See August 2015 Six-month 3-E testing plan for portable/FLEX electrical Update.

equipment that is credited for events that require mitigating strategies. Please describe how Regulatory Guidance documents, IEEE Standards, manufacturer recommendations, etc. will be used to establish the maintenance and testing programs for the portable/FLEX electrical equipment, especially for batteries and diesel generators.

SE 9-E For a design basis Mississippi River flood, Completed - See August 2015 Six-month most of the site will have several feet of Update.

water. The license's plan is to remove the drywell heads, and the RPV heads, and flood the refueling cavity, connecting both RPVs and both SFPs. There will be a loss of all AC power due to the flood. Gasoline powered pumps will be used to refill the refueling cavity. Please provide an Page 18 of 20

Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016 assessment of the reliability of this action, including the timeline for getting to cold shutdown and removing the heads and flooding the refueling cavity, the reliability of offsite power to perform these actions, the availability of backup power supplies, and the availability of critical equipment such as the crane for head removal and stud detensioners.

SE 10-E Final robust FLEX building configuration - Completed - See August 2015 Six-month Current plan using one robust building with Update.

N equipment and one commercial building with the +1 equipment is an Alternate Strategy approach to NEI Guidelines NEI 12-06.

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 enclosure.

1. Quad Cites 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. NRC Order EA-13-109, "Issuance of Order to Modify Licenses with Regard to reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013.

4. Quad Cities Nuclear Power Station, Units I and 2 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," dated August 28, 2013.

5. Quad Cites Nuclear Power Station's Request for Relaxation from NRC Order EA-12-049, "Order Modifying Licenses With Regard To Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated February 27, 2014.

6. RCIC Pump and Turbine Durability Evaluation Pinch Point Study, February 2013, 0000-0155-1545-RO, DRF 0000-0155-1541, Revision 0.

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Quad Cities Nuclear Power Station, Units 1 and 2- Sixth Six-Month Status Report for the Implementation of FLEX February 2016

7. Quad Cities Nuclear Power Station, Units I and 2 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC Nos.MF 1048 and MF 1049), dated November 22, 2013.

8. Quad Cities Nuclear Power Station, Units I and 2 Second 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," dated February 28, 2014.

9. NRC Approval of Exelon/Quad Cities Request for Relaxation from NRC Order EA-12-049, dated April 15, 2014 (ADAMS Accession No. ML14071A531).

10. Quad Cities Nuclear Power Station, Units I and 2 Third 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," dated August 28, 2014.

11. Quad Cities MAAP Analysis to Support FLEX Initial Strategy, QC-MISC-013 Rev. 2, dated February 14, 2014.

12. Quad Cities Nuclear Power Station, Units I and 2 Fourth 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," dated February 27, 2015.

13. Quad Cites Nuclear Power Station's Request for Relaxation from NRC Order EA-12-049, "Order Modifying Licenses With Regard To Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 4, 2015 (ADAMS Accession No. ML15064A090).

14. Quad Cites Nuclear Power Station's Request for Relaxation from NRC Order EA-12-049, "Order Modifying Licenses With Regard To Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 6, 2015 (ADAMS Accession No. ML 15068AO64 ).

15. NRC Approval of Exelon/Quad Cities Unit 1 Request for Relaxation from NRC Order EA-12-049, dated March 11, 2015 (ADAMS Accession No. ML15068A206 ).

16. NRC Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-51, dated June 25, 2015 (ADAMS Accession No. MI-1515613134).

17. Quad Cities Nuclear Power Station, Units I and 2 Fifth 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," dated August 28, 2015.

18. SAFER Response Plan for Quad Cities Generating Station, Rev. 003, dated 11/18/15, Quad Cities Station procedure CC-QC-118-1001, Rev. 001 9 Attachments None Page 20 of 20