RS-17-069, Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe..: Difference between revisions

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#REDIRECT [[RS-17-069, Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe]]
| number = ML17178A079
| issue date = 06/27/2017
| title = Sixth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe..
| author name = Simpson P
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000254, 05000265
| license number = DPR-029, DPR-030
| contact person =
| case reference number = EA-13-109, RS-17-069, TAC MF4460, TAC MF4461
| document type = Letter type:RS, Status Report
| page count = 26
| project = TAC:MF4460, TAC:MF4461
| stage = Other
}}
 
=Text=
{{#Wiki_filter:. Iddonow
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                                                .
ANUP-Exelon Generation,,,,
Order No. EA-13-109 RS-17-069 June 27, 2017 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 For Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
 
==References:==
: 1. NRC Order Number 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
: 2. NRC Interim Staff Guidance JLD-ISG-2013-02, "Compliance with Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions", Revision 0, dated November 14, 2013
: 3. NRC Interim Staff Guidance JLD-ISG-2015-01, "Compliance with Phase 2 Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions", Revision 0, dated April 2015
: 4. NEI 13-02, "Industry Guidance for Compliance With Order EA-13-109, BWR Mark I & II Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions", Revision 1, dated April 2015
: 5. Exelon Generation Company, LLC's Answer to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated June 26, 2013
: 6. Exelon Generation Company, LLC Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated June 30, 2014 (RS-14-063)
: 7. Exelon Generation Company, LLC First Six-Month Status Report Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated December 17, 2014 (RS-14-306)
 
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-13-109 June 27, 2017 Page 2
: 8. Exelon Generation Company, LLC Second Six-Month Status Report Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated June 30, 2015 (RS-15-152)
: 9. Exelon Generation Company, LLC Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated December 16, 2015 (RS-15-304)
: 10. Exelon Generation Company, LLC Fourth Six-Month Status Report For Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated June 30, 2016 (RS-16-110)
: 11. Exelon Generation Company, LLC Fifth Six-Month Status Report For Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109), dated January 26, 2017 (RS-17-008)
: 12. 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 Phase 1 of Order EA-13-109 (Severe Accident Capable Hardened Vents) (TAC Nos.
MF4460 and MF4461), dated April 1, 2015
: 13. 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 Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) (TAC Nos.
MF4460 and MF4461), dated April 28, 2017 On June 6, 2013, 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 require their BWRs with Mark I and Mark II containments to take certain actions to ensure that these facilities have a hardened containment vent system (HCVS) to remove decay heat from the containment, and maintain control of containment pressure within acceptable limits following events that result in loss of active containment heat removal capability while maintaining the capability to operate under severe accident (SA) conditions resulting from an Extended Loss of AC Power (FLAP). Specific requirements are outlined in Attachment 2 of Reference 1.
Reference 1 required submission of an Overall Integrated Plan (OIP) by June 30, 2014 for Phase 1 of the Order, and an OIP by December 31, 2015 for Phase 2 of the Order. The interim staff guidance (References 2 and 3) provide direction regarding the content of the OIP for Phase 1 and Phase 2. Reference 3 endorses industry guidance document NEI 13-02, Revision 1 (Reference 4) with clarifications and exceptions identified in References 2 and 3. Reference 5 provided the EGC initial response regarding reliable hardened containment vents capable of operation under severe accident conditions. Reference 6 provided the Quad Cities Nuclear Power Station, Units 1 and 2, Phase 1 OIP pursuant to Section IV, Condition D.1 of Reference 1.
References 7 and 8 provided the first and second six-month status reports pursuant to Section IV, Condition D.3 of Reference 1 for Quad Cities Nuclear Power Station. Reference 9 provided the Quad Cities Nuclear Power Station, Units 1 and 2, Phase 1 updated and Phase 2 OIP pursuant to
 
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-13-109 June 27, 2017 Page 3 Section IV, Conditions D.2 and D.3 of Reference 1. References 10 and 11 provided the fourth and fifth six-month status reports pursuant to Section IV, Condition D.3 of Reference 1 for Quad Cities Nuclear Power Station.
The purpose of this letter is to provide the sixth six-month update report for Phases 1 and 2, pursuant to Section IV, Condition D.3 of Reference 1, that delineates progress made in implementing the requirements of Reference 1 for Quad Cities Nuclear Power Station, Units 1 and 2. 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 items contained in References 12 and 13.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David J. Distel at 610-765-5517.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 27`" day of June 2017.
Res ectfully, Patrick R. Simpson Manager - Licensing Exelon Generation Company, LLC
 
==Enclosure:==
 
Quad Cities Nuclear Power Station, Units 1 and 2 Sixth Six-Month Status Report for Phases 1 and 2 Implementation of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station NRC Project Manager, NRR - Quad Cities Nuclear Power Station Mr. Raj Auluck, NRR/JLD/TSD/JCBB, NRC Mr. Brian E. Lee, NRR/JLD/JCBB, NRC Mr. John P. Boska, NRR/JLD/JOMB, NRC Illinois Emergency Management Agency - Division of Nuclear Safety
 
Enclosure Quad Cities Nuclear Power Station, Units 1 and 2 Sixth Six-Month Status Report for Phases 1 and 2 Implementation of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (22 pages)
 
I'(::nicllosure Quad Cities Sixth Six Month Status Report for the Implementation of Order EA  109, "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" 1 Introduction Quad Cities developed an Overall Integrated Flan (Reference 1 in Section 8),
documenting the installation of a Hardened Containment Vent System (RCVS) that provides a reliable hardened venting capability for pre-core damage and under severe accident conditions, including those involving a breach of the reactor vessel by molten core debris, in response to Reference 2. Updates of milestone accomplishments will be based on the combined Phases 1 and 2 Overall Integrated Plan dated December 16, 2015.
Quad Cities developed an updated and combined Phases 1 and 2 Overall Integrated Plan (Reference 7 in Section 8), documenting:
The installation of a Hardened Containment Vent System (RCVS) that provides a reliable hardened venting capability for pre-core damage and under severe accident conditions, including those involving a breach of the reactor vessel by molten core debris, iti response to Reference 2.
: 2. An alternative venting strategy that makes it unlikely that a drywell vent is needed to protect the containment from overpressure related failure under severe accident conditions, including those that involve a breach of the reactor vessel by molten core debris, in response to Reference 2 This enclosure provides an update of milestone accomplishments since the Fifth Six-Month Update of the combined Phases 1 and 2 Overall Integrated Plan, including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
In Reference 24, EGC requested an extension to comply with NRC Order EA-13-109 based on the earlier decision to permanently cease power operations at Quad Cities Nuclear Power Station, Units 1 and 2 by June 1, 2018, which caused engineering design and plant modification activities supporting Order implementation to be discontinued. As a result of the recent reversed cessation of operation decision, in Reference 25, EGC withdrew this request for extension to comply and provided a revised request for extension to comply with NRC Order EA-13-109 based on the continued operation of both units. EGC has now resumed work to complete full implementation of NRC Order EA-13-109 at Quad Cities Nuclear Power Station, Units 1 and 2 in accordance with this update to the Overall Integrated Plan, Section 3, milestone Schedule, which is consistent with the requested extension letter (Reference 25), as approved by the NRC in Reference 33.
Page I of 22
 
The following milestone(s) have been completed since the Fifth Six-Month Update to the combined Phases 1 and 2 Overall Integrated Plan (Ref. 31), and are current as of June 1, 2017.
04 Outage specific portion installed on Unit 1 Phase 1 A  Completed conceptual and detailed design on Unit 2 Phase 1 Started construction on Unit 2 Phase 1 a Completed Phase 2 conceptual design and started detailed design for both Units Status The following provides an update to Attachment 2 of the combined Phases 1 and 2 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 EA-13-109 implementation date.
Phase 1 and Phase 2 HCVS Milestone Table Comments Target Milestone                  Completion    Activity Status      {Include date Date                            changes in this column}
Submit Overall Integrated Plan          Jun 2014        Complete Submit 6 Month Updates:
Update 1                              Dec. 2014        Complete Update 2                              Jun. 2015        Complete Update 3                            N  Dec. 2015        Complete Update 4                              Jun 2016        Complete Update 5                                an 2017        Complete i
I                Complete with this Update 6                            ~  Jun 2017 submittal Page 2 of 22
 
Phase 1 and Phase 2 HCVS Milestone Table Comments Target Milestone                  Completion      Activity Status    {Include date Date                          changes in this column}
Update 7                                  Dec 2017        Not Started Update 8                                  Jun 2018        Not Started Update 9                                  Dec 2018        Not Started Phase 1 Specific Milestones UNIT 1 Phase I Unit I Modi-uications:
Complete Conceptual Design                    Jun 2014          Complete Complete Detailed Design and Issue Mar 2016          Complete Modification Package Begin Online Portion of the Installation      Jan 2016          Complete Schedule relief granted Complete Online Installation                  Dec 2017          Started under Ref. 33.
Outage specific portion Begin Outage Portion of the Installation      Mar 2017          Complete    of installation completed during Q1 R24.
Outage specific portion Complete Outage Installation                  Apr 2017          Complete    of installation completed during 01 R24.
Schedule relief granted Installation Operational Acceptance          June 2018        Not Started under Ref. 33.
Phase 1 Unit 1 Procedure Changes Active Operations Procedure Changes                                            Schedule relief granted Dec 2017          Started Developed                                                                      under Ref. 33.
Schedule relief granted Site Specific Maintenance Procedure                                          under Ref. 33.
Dec 2017          Started Developed Schedule relief granted Procedure Changes Complete                Dec 2017        Not Started under Ref. 33.
'rocedure Final Validation and                                              Schedule relief granted June 2018        Not Started npiementation                                                                  under Ref. 33.
Page 3 of 22
 
Phase 1 and Phase 2 HCVS Milestone Table
_.._
Comments_
Target Milestone                  Completion      Activity Status    {Include date Date                          changes in this column}
Phase 1 Unit 1 1t'rai ring:
Schedule relief granted Simulator Upgrade Completion              Dee 2017        Not Started under Ref. 33.
Schedule relief granted Training Complete                        April 2018      Not Started under Ref. 33.
Phase 1 Unit 1 Completion Schedule relief granted Phase 1 Unit 1 RCVS Implementation          June 2018        Not Started under Ref. 33.
UNH 2 Phase 1 Unit 2 Modifiications:
Complete Conceptual Design                    Jun 20141        Complete Construction Complete Detailed Design and Issue                                          proceeding on major JW 2017          Started Modification Package                                                          components. Detail work still under review.
Begin Online Portion of the Installation    Nov 2018          Complete Complete Online Installation                Mar 2018          Started Begin Outage Portion of the Installation    Mar 2018        Not Started Complete Outage Installation                Apr 2018        Not Started Schedule relief granted Installation Operational Acceptance        wane 2018        Not Started      under Ref. 33.
Phase 1 Unit 2 Procedure Changes Active Operations Procedure Changes Apr 2018          Started Developed Site Specific Maintenance Procedure Apr 2018          Started Developed Procedure Changes Active              I  Apr 2018        Not Started Procedure Final Validation and                                              Schedule relief granted
                                            .Dune 2018        Not Started Implementation                                                                  under Ref. 33.
Page 4 of 22
 
Phase 1 and Phase 2 HCVS Milestone Table Comments Target Milestone                    Completion        Activity Status  {Include date Date                        changes in this column)
Phase 1 Unit 2 Training:
Meets 2017/2018 Simulator Upgrade Completion                Dec 2017          Not Started training cycle.
Training Complete                          Apr 2018          Not Started Phase 1 Unit 2 Completion Schedule relief granted Phase 1 Unit 2 HCVS Implementation            wane 2018          Not Started under Ref. 33.
Phase 2 Specific Milestones Phase 2 Unu t 1 u1/daev6 leations:
Begin Conceptual Design                        Apr 2016          Complete Common design with Complete Conceptual Design                    Feb 2017          Complete Unit 2.
Common design with Begin Detailed Design                          Apr 2017          Complete Unit 2.
Common design with Complete Detailed Design and Issue                                                    Unit 2.
Jul 2017          Started Modification Package Common install with Begin Online Portion of the Installation      Sep 2017          Not Started Unit 2.
Common install with Complete Online Installation                  lllliar 2018      Not Started Unit 2.
Begin Outage Portion of the Installation            N/A            N/A        No outage scope Complete Outage Installation                        N/A            N/A        No outage scope Installation Operational Acceptance            April 2019        Not Started Pease 2 Unit 1 Procedure Changes Active Operations Procedure Changes Apr 2019          Not Started Developed Page 5 of 22
 
Phase 1 and Phase 2 HCVS Milestone Table Comments Target Milestone                  Completion      Activity Status      {Include date Date                            changes in this column}
Site Specific Maintenance Procedure Apr 2019        Not Started Developed Procedure Changes Active                  Apr 2019        Not Started Phase 2 Unit 1 sumo ng:
Training Complete                        Apr 2019        Not Started Phase 2 Unit 1 Comu p etion Phase 2 Unit 1 HCVS Implementation          Apr 2019        Not Started Submit Phases 1 and 2 Unit 1 Jun 2019        Not Started Completion Report (60 day letter)
Phase 2 Unit 2 VVVodli-Jications:
Begin Conceptual Design                      Apr 2016        Complete Common design with Complete Conceptual Design                  Feb 2017        Complete Unit 1.
Common design with Begin Detailed Design                        Apr 2017        Complete Unit 1.
Common design with Complete Detailed Design and Issue Jup 2017          Started        Unit 1. Formerly Mar Modification Package 2017.
Common install with Begin Online Portion of the Installation    Sep 2017        Not Started Unit 1.
Common install with Complete Online Installation                Mar 2018        Not Started Unit 1.
Begin Outage Portion of the Installation      N/A              N/A            No outage install E
Complete Outage Installation            (    N/A              N/A            No outage install Schedule relief granted Installation Operational Acceptance        June 2018        Not Started under Ref. 33.
i Phase 2 Unit 2 Procedure Changes 1
Active Operations Procedure Changes
                                        ?  Apr 2010        Not Started Developed Page 6 of 22
 
Phase 1 and Phase 2 HCVS Milestone Table Comments Target Milestone              Completion    Activity Status  {Include date Date                        changes in this column}
Site Specific Maintenance Procedure Apr 2018      Not Started Developed Procedure Changes Active              Apr 2018      Not Started Procedure Final Validation and                                      Schedule relief granted June 2018      Not Started Implementation                                                          under Ref. 33.
Phase 2 Unit 2 Training:
Training Complete                    Apr 2018      Not Started Phase 2 Unit 2 Completion Schedule relief granted Phase 2 Unit 2 HCVS Implementation    June 2018      Not Started under Ref. 33.
Submit Phases 1 and 2 Unit 2 Aug 2018        Not Started Completion Report (60 day letter)
Page 7 of 22
 
4 Changes to Compliance Method Phase 1 Changes None Phase 2 Changes No changes needed since Fifth Six-Month Update (Ref. 31).
5  Need for                      and Basis for 21he IfI'IeH -,'WIRell (Din)
Quad Cities has received schedule relaxation from the NRC via letter dated larch 21 7 2017 (Ref. 33).
No additional need for relief/relaxation relative to Order FA-13-109 (Ref 2), other than as described above, has been identified at this time.
Page 8 of 22
 
6 Open Items from Combined Phases 1 and 2 Overall Integrated Plan and Interim Staff Evaluations The following tables provide a summary of the open items documented in the combined Phases 1 and 2 Overall Integrated Plan or the Interim Staff Evaluation (ISE) and the status of each item.
Combined Phases 1 and 2 OIP Open Items                                              Status Phase 1 Open Items 01-1      Determine how Motive Power and/or HCVS          Complete  Per QDC detailed design, HCVS primary Battery Power will be disabled during normal      control panel will be provided with a key lock switch operation.                                        to activate the system. Normally system remains de-energized. This must be unlocked prior to performing any actuations of the DC powered components. With the panel being located in the MCR, unlocking and turning the switch can be performed in an FLAP with minimal operator action. Detailed in December 2015 01P (Ref. 7).
01-2      Confirm that the Remote Operating Stutiun          Closed to ISE Open Item number 4.
(ROS) will be in an accessible area following a Reference 16 has been provided in e-portal.
Severe Accident (SA).
01-3      Confirm diameter on new common HCVS                Closed to ISE Open Item number 5.
Piping.
01-4      Confirm suppression pool heat capacity.          Complete - The MAAP analysis verified that the vent is not required for at least 5 hours (Ref. 12). At 5 hours, the decay heat will be less than 1 %. Reference 12 has been provided in e-portal.
0I-5      Determine the approach for combustible            Closed to ISE Open Items 10 and 11.
gases.
01-6      Develop a procedure for HCVS out-of-service      Started. Will be incorporated into QCAP 1500-07, requirements and compensatory measures.          Administrative Tracking Requirements for Unavailable FLEX Equipment.
01-7      Provide procedures for HCVS Operation.            Closed to ISE Open Item No. 14.
Page 9 of 22
 
Combined Phases J -and 2 OIP Open Items                                        Status 01-8  Confirm 125 Volt DC Station Battery Life.      Complete per QDC calculation - QDC-8300-E-2100 (Ref. 13) confirms that the 125 VDC Station Battery will continue to supply necessary power during the 8-hour duration prior to aligning the FLEX diesel generator. Also, refer to NRC ISE Open Item No. 1.
Reference 13 has been provided in e-portal.
Phase 2 Open Items 01-9  Supply Part 3 Drywell Boundary Condition.      Complete  the Phase 2 Alternate option (SA WA/SAWM) was added to the December 2015 OIP (Ref. 7).
01-10  Determine deployment path for Discharge        Started  Similar to FLEX deployment through Bay booster pump with respect to HCVS dose      Mechanical Maintenance shop, with hose connections on Turbine Building west wall for convenience and shorter deployment path in Turbine Building dose shadow. Will complete with detailed Phase 2 design.
Page 10 of 22
 
Phase 1 Interim Staff Evaluation Open Items Status (Reference 18)
ISE-1  Make available for NRC staff audit the          Complete - Supplied to NRC Audit team during onsite calculation (QDC-8300-E-2100) that confirms      FLEX evaluation (Jan 2015). (Ref. 13).
that Order EA-12-49 actions to restore power Calculation QDC-8300-E-2100 confirms that Order EA-are sufficient to ensure continuous operation 12-49 actions to restore power are sufficient to ensure of non-dedicated containment continuous operation of non-dedicated containment instrumentation.
instrumentation.
Reference 13 has been provided in e-portal.
ISE-2  Make available for NRC staff audit the final    Started - HCVS Battery design has been completed.
sizing evaluation for HCVS batteries/battery    (Refs. 14 and 17) charger including incorporation into FLEX DG Calculation QDC-1600-E-2200 evaluates the sizing of loading calculation.
the HCVS battery. (Ref. 28)
References have been provided in e-portal.
Incorporation into FLEX DG loading calculations is in pro_ress.
ISE-3  Make available for NRC staff audit              Started- Unit 1 nitrogen system installed. Calculation documentation of the HCVS nitrogen              QDC-1600-M-2212 for sizing approved and applicable pneumatic system design including sizing and    to both Units. Unit 2 system location in progress.
location.                                        (Refs. 14 and 17)
ISE-4  Make available for NRC staff audit an            Complete- Temperature evaluation (Calculation 2014-evaluation of temperature and radiological      02948) was made available to NRC Audit team during conditions to ensure that operating              onsite FLEX evaluation (Jan 2015)(Ref. 21).
personnel can safely access and operate phase I Radiological evaluation has been completed.
controls and support equipment.
(Ref.16).
Phase 11 Radiological evaluation has been completed (Ref. 6).
Evaluations of temperature and radiological conditions ensure that operating personnel can safely access and operate controls and support equipment.
References have been provided in e-portal.
Page 11 of 22
 
ISE-5  Make available for NRC staff review              Started. Refer to the response to ISE open item 6.
documentation that confirms the final design diameter of the HCVS piping.
ISE-6  Make available for NRC staff audit analyses      Started. Calculation QDC-1600-M-2188 for Unit 1 line demonstrating that HCVS has the capacity to      sizing complete (Ref. 19). Calculation QDC-1600-M-vent the steam/energy equivalent of one          2247 for Unit 2 line sizing in progress. (Ref. 30) percent of licensed/rated thermal power In addition, MAAP analyses (Ref. 12) are credited to (unless a lower value is justified), and that verify that (1) venting can be delayed for at least three the suppression pool and the HCVS together (3) hours and (2) anticipatory venting sufficiently limits are able to absorb and reject decay heat, the suppression pool heat up to maintain RCIC such that following a reactor shutdown from functional.
full power containment pressure is restored and then maintained below the primary            References have been provided in e-portal.
containment design pressure and primary containment pressure limit.
ISE-7  Make available for NRC staff audit the            Complete The HCVS stack seismic design meets the seismic and tornado missile final design          Station's design basis earthquake design criteria. (Ref.
criteria for the HCVS stack.                      20)
Reference has been provided in e-portal.
The information provided in December 2015 OIP (Ref.
: 7) demonstrates that the external piping meets the tornado missile protection criteria of HCVS-WP-04.
ISE-8 Make available for NRC staff audit the            Started  Component location design and local descriptions of local conditions (temperature, conditions impact are in progress. The HCVS primary radiation and humidity) anticipated during        control panel will be located in the MCR (Refs. 14, 15 FLAP and severe accident for the components and 17).
(valves, instrumentation, sensors, Reactor Building temperatures are as noted in transmitters, indicators, electronics, control devices, etc.) required for HCVS venting          calculation 2014-02948 (Ref. 21).
including confirmation that the components Turbine Building temperatures at the ROS are as are capable of performing their functions noted in evaluation EC 402709 (Ref. 22).
during FLAP and severe accident conditions.
Limiting radiation conditions for equipment as per calculation QDC-0000-M-2199, HCVS 7-Day Dose Analysis (Ref. 16).
References have been provided in e-portal.
Page 12 of 22
 
ISE-9  Make available for NRC staff audit                Started  QCOP 0050-09 FLEX Response documentation that demonstrates adequate          Instrumentation and Communication Equipment communication between the remote HCVS              provides a detailed description of Communications operation locations and HCVS decision              equipment dedicated to FLEX response utilized for makers during ELAP and severe accident            Severe Accident Response. This equipment includes conditions.                                        radios programed for talk around mode with additional batteries and Sound powered phones which can be used for communications between the Main Control Room and local control stations. QCOS 0050-04 FLEX Sound Powered Phone Surveillance is being revised to test two additional connection points that can be utilized for Severe Accident response and control  of SAWA/SAWM flow and local operation of the HCVS valves.
ISE-10 Provide a description of the final design  of      Complete  As stated in the December 2015 OIP, the HCVS to address hydrogen detonation            Quad Cities will utilize Argon purge system to address and deflagration.                                  combustible gases in the HCVS piping. A summary    of the design features is included in the December 2015 OIP (Ref. 7).
ISE-11 Provide a description  of the strategies for        Completed - As described in the December 2015 OIP hydrogen control that minimizes the                (Ref. 7), the HCVS torus vent path in each Quad Cities potential for hydrogen gas migration and            unit, starting at and including the downstream PCIV, ingress into the Reactor Building or other          will be a dedicated HCVS flow path. There are no buildings.                                          interconnected systems downstream      of the downstream, dedicated HCVS PCIV. Interconnected systems are upstream    of the downstream HCVS PCIV and are isolated by normally shut, fail shut PCIVs which, if open, would shut on on ELAP. There is no shared HCVS piping between the two units.
The vent path will rely on Argon purge system to prevent the formation    of a combustible gas mixture from forming within the line (Refs. 14, 15 and 17).
References have been provided in e-portal.
ISE-12 Make available for NRC staff audit                Started  the Quad Cities seismic evaluation will be documentation    of a determination of seismic      based on the Quad Cities design basis earthquake.
qualification evaluation of the HCVS components.
                                                  ''age 13 of 22
 
ISE-13 Make available for NRC staff audit              Started. Instrument design is in progress (Refs. 14, 15 descriptions of all instrumentation and        and 17).
controls (existing and planned) necessary to References have been provided in e-portal.
implement this order including qualification methods.
ISE-14 Make available for NRC staff audit the          Started. Procedures are under development by procedures for HCVS operation.                  Operations.
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Phase 2 Interim Staff Evaluation Open Items Status (Reference 33)
ISE-1    Licensee to demonstrate that the hydraulic          Started. FLEX calculation QDC-0000-M-2097 (Ref. 11) analysis for the FLEX pump is capable to support    will be revised with hydraulic parameters for addition the required 400 gpm SAWA flow rate.                of SAWA scenarios.
ISE-2    Licensee to evaluate the SAWA equipment and        Started.
controls, as well as the ingress and egress paths for the expected severe accident conditions          Equipment and Controls (temperature, humidity, radiation) for the          Plant instrumentation for SAWM that is qualified to sustained operating period.                        RG 1.97 or equivalent is considered qualified for the sustained operating period without further evaluation. The following plant instruments are qualified to RG 1.97:
D Pressure                  P11(2)-1640-11A/B Suppression Pool Level Ll 1(2)-1640-10A/B Passive components that do not need to change state after initially establishing SAWA flow do not require evaluation beyond the first 8 hours, at which time they are expected to be installed and ready for use to support SAWA/SAWM.
The following additional equipment performing an active SAWA/SAWM function is considered:
SAWA/SAWM flow instrument.
SAWA/SAWM pump SAWA/SAWM generator (the FLEX generator for the associated Unit)
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Ingress and Egress For locations outside the Reactor Building between 7 hours and 7 days when SAWA is being utilized, quantitative evaluation of expected dose rates has been performed per HCVS-WP-02 and found the dose rates at deployment locations including ingress/egress paths are acceptable. (QDC-0000-M-2223, Ref. 6)
ISE-3 I Licensee to demonstrate how instrumentation      Started.
and equipment being used for SAWA and supporting equipment is capable to perform for  Equipment and Controls the sustained operating period under the          Plant instrumentation for SAWA that is qualified to expected temperature and radiological            RG 1.97 or equivalent is considered qualified for the conditions.                                      sustained operating period without further evaluation. The following plant instruments are qualified to RG 1.97:
DW Pressure                PI 1(2)-1640-11A/B Suppression Pool Level LI 1(2)-1640-10A/B Passive components that do not need to change state after initially establishing SAWA flow do not require evaluation beyond the first 8 hours, at which time they are expected to be installed and ready for use to support SAWA/SAWM.
The following additional equipment performing an active SAWA/SAWM function is considered for temperature and radiation effects:
SAWA/SAWM flow instrument.
SAWA/SAWM pump (may be the FLEX pump)
SAWA/SAWM generator (may be the FLEX generator)
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Temperature The location of the distribution manifold is one floor below the ROS, and has similar or better temperature conditions as at the ROS. The location of the SAWA pump is similar to the FLEX pump, i.e. outside, but on the West side of the Site vs. East side.
The location of SAWA equipment and controls are the same or similar as FLEX, and are bounded by the FLEX evaluations for temperature.
FROM M!,InT11T1, For equipment locations outside the Reactor Building between 7 hours and 7 days when SAWA is being utilized, quantitative evaluation of expected dose rates has been performed per HCVS-WP-02 and found the dose rates at deployment locations are acceptable. (QDC-0000-M-2223, Ref. 6)
ISE-4  Licensee to demonstrate that containment            Started. The Wetwell vent has been designed and failure as a result of overpressure can be            installed to meet NE113 02 Rev 1 guidance, which will prevented without a drywell vent during severe      ensure that it is adequately sized to prevent accident conditions.                                containment overpressure under severe accident conditions.
The SAWM strategy will ensure that the Wetwell vent remains functional for the period  of sustained operation. Quad Cities will follow the guidance (flow rate and timing) for SAWA/SAWM described in BWROG-TP-15-008 and BWROG-TP-15-011. These documents have been posted to the ePortal for NRC staff review. The Wetwell vent will be opened prior to exceeding the PCPL value of 52 PSIG. Therefore, containment over pressurization is prevented without the need for a drywell vent.
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ISE-5      Licensee shall demonstrate how the plant is          Started.      i bounded by the reference plant analysis that shows the SAWM strategy is successful in making it unlikely that a drywell vent is needed. re'fe'rence Plant            Quad Cities Torus freeboard volume        Torus freeboard volume is 1902 is 525,0001 gallons          619,      gallons SAWA flow is 500 GPM at SAWA flow is 400 GPM at 8 8 hours followed by 100      hours followed by 80 GPM GPM from 12 hours to        from 12 hours to 168 hours 168 hours The above parameters for Quad Cities compared to the reference plant that determine success of the SAWM strategy demonstrate that the reference plant values are bounding. SAWA flow rates are based on RCIC design flow as allowed by NE113-02, Rev. 1, Section 4.1.1.2.2. Therefore, the SAWM strategy implemented at Quad Cities makes it unlikely that a DW vent is needed to prevent containment overpressure related failure.
ISE-6      Licensee to demonstrate that there is adequate      Started. Quad Cities utilizes handheld radios to communication between the MCP, and the              communicate between the MCP,, the operator at the SAWA/SAWM control location during severe            FLEX pump, and the operator at the SAWA flow accident conditions.                                control location. This communication method is the some as accepted in Order EA-12-049. These items will be powered and remained powered using the same methods as evaluated under EA-12-049 for the period of sustained operation, which may be longer than identified for EA-12-049.
      ' Peach Bottom available freeboard volume in gallons is estimated from nominal water level of 14.7 feet to 21 feet. 21 feet is the upper range of the wide range torus level instrument and the assumed loss of wetwell vent function. The Peach Bottom torus is 31 feet in diameter.
2 Quad Cities' freeboard volume is based on Torus water level from 14' to 22.5' in a torus with 30' minor diameter and 109' major diameter.
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ISE-7      Licensee to demonstrate the SAWM flow              Started. For locations outside the Reactor Building instrumentation qualification for the expected    between 7 hours and 7 days, when SAWA is being environmental conditions.                          utilized, a quantitative evaluation of expected dose rates has been performed per HCVS-WP-02, and found the dose rates at deployment locations including ingress/egress paths are acceptable. The selected instrument is designed for the expected flow rate, temperature, and pressure for SAWA over the period of sustained operation.
SAWA HOW Expected SAWA Instrument Parameter Range Qualification 2.21 to 736 GPM            80 to 400 GPM
                                                                        -4 to 140 OF              32 to 120 OF 0 to 285 PSI              0 to 120 PSI e' ~nteHm Stafi EvaIuaUord Impacts There are no potential impacts to the Interim Staff Evaluation(s) identified at this time.
Page 19 of 22
 
References The following references support the updates to the combined Phases 1 and 2 Overall Integrated Plan described in this enclosure.
: 1. Quad Cities Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order dumber EA    109)," dated June 30, 2014. (RS-14-063).
: 2. NRC Order Number EA-13-109, "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" dated June 6, 2013.
: 3. NEI 13-02, "Industry Guidance for Compliance with NRC Order EA-13-109, `To Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 1, dated April 2015.
: 4. NRC Interim Staff Guidance JLD-ISG-2013-02, "Compliance with Order EA    109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 0, dated November 2013 (Accession No. ML1330413836).
: 5. NRC Endorsement of industry "Hardened Containment Venting System (RCVS)
Phase 1 Overall Integrated Plan Template (EA-13-109) Rev 0" (Accession No.
ML14128A219).
: 6. Calculation QDC-0000-M-2223, Revision 0, RCVS Phase II 7-Day Dose Analysis.
: 7. Quad Cities Combined Phase 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)," dated December 16, 2015 (RS-15-304).
: 8. NRC Interim Staff Guidance JLD-ISG-2015-01, "Compliance with Phase 2 of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions,"
Revision 0, dated April 2015 (Accession No. ML15104A118).
: 9. Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events, dated March 12, 2012.
: 10. Exelon Calculation LIP-ODC-001, Rev. 4A, Quad Cities Local Intense Precipitation Evaluation.
: 11. Exelon Calculation QDC-0000-M-2097, PIPE FLO Analysis of FLEX Strategy.
: 12. Exelon Calculation QC-MISC-015, Rev. 0, MAAP Analysis to Support RCVS Design.
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: 13. Exelon Calculation CDC-8300-E-2100, Unit 1(2) 125 VDC Battery Coping Calculation for Beyond Design Basis FLEX Event.
: 14. EC 392256 - Unit 1 Hardened Containment Vent System (Non-Outage Portion) as Required by NRC Order EA-13-109, Rev. 001.
: 15. EC 392257 - Unit 1 Hardened Containment Vent System (Outage Portion) as Required by NRC Order EA-13-109, Rev. 000.
: 16. Exelon Calculation QDC-0000-M-2199, RCVS 7 Day Dose Analysis.
: 17. EC 400666 Hardened Containment Vent System as Required by NRC Order EA-13-109  Unit 2.
: 18. NRC Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase One of Order EA-13-109 (Severe Accident Capable Hardened Vents)
JAC NOS. MF4460 and MF4461) (ML15089A421), dated April 1, 2015.
: 19. Exelon Calculation QDC-1600-M-2188, HCVS Vent Line Sizing Calculation, Rev.
0.
: 20. Exelon Calculation QDC-0020-S-2192, HCVS Steel Tower Structural Calculation, Rev. 0.
: 21. Exelon Calculation 2014-02948, Reactor Building Temperature Analysis Resulting from Extended Loss of AC Power.
: 22. Exelon Evaluation EC 402709  Temperature in Proposed Location of Remote Operating Station.
: 23. Quad Cities Units 1 and 2, Fourth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA    109), dated June 30, 2016 (RS-16-110).
: 24. Exelon Generation Company, LLC Request for Extension to Comply with NRC Order EA-13-109, "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" and NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated November 16, 2016 (RS-16-210).
: 25. Exelon Generation Company, LLC Request for Extension to Comply with NRC Order EA-13-109, "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" and NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated January 12, 2017 (RS-17-006).
: 26. Exelon Generation Company, LLC Letter to USNRC, Certification of Permanent Cessation of Power Operations at Quad Cities Nuclear Power Station, Units 1 and 2, dated June 20, 2016.
Page 21 of 22
: 27. Exelon Generation Company, LLC Letter to USNRC, Withdrawal of Certification of Permanent Cessation of Power Operations for Quad Cities Nuclear Power Station, Units 1 and 2 and Previously Submitted Licensing Actions in Support of Decommissioning, dated December 14, 2016 (RS-16-253).
: 28. Exelon Calculation QDC-1600-E-2200, 125 VDC Battery Sizing Calculation for Hardened Containment Vent System for 24-Hour Duty Cycle, Rev. 0.
: 29. Exelon Calculation QDC-1600-M-2212, RCVS Nitrogen Bottle Sizing and Pressure Regulator Set Point Determination, Rev. 0.
: 30. Exelon Calculation QDC-1600-M-2247, Unit 2 RCVS Vent Line Sizing Calculation, Rev. 0.
: 31. Quad Cities Units 1 and 2, Fifth Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA    109), dated January 26, 2017 (RS-17-008).
: 32. Quad Cities Nuclear Power Station, Units 1 and 2  Interim Staff Evaluation Relating to Overall Integrated Plan In Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) (CAC Nos. MF4460 and MF 4461)1 dated April 28, 2017 (Accession No. ML17109A077).
: 33. Quad Cities Nuclear Power Station, Units 1 and 2  Relaxation of Schedule Requirements for Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" and Order EA-13-109, "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" (CAC Nos. MF1048, MF1049, MF4460, and MF 4461), dated March 21 7 2017 (Accession No. ML17025A248).
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