ML16054A799

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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)
ML16054A799
Person / Time
Site: Cooper Entergy icon.png
Issue date: 02/16/2016
From: Limpias O A
Nebraska Public Power District (NPPD)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
EA-12-049, NLS2016008
Download: ML16054A799 (7)


Text

N Nebraska Public Power District Always there when :you need us NLS2016008 February 16, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-000 1

Subject:

References:

Nebraska Public Power District's 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)

Cooper Nuclear Station, Docket No. 50-298, DPR-46 1. 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 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. NPPD Letter, "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 29, 2012 5. NPPD Letter, "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

Dear Sir or Madam:

On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued an Order (Reference

1) to Nebraska Public Power District (NPPD). Reference 1 was immediately effective and directs NPPD to develop, implement, and maintain guidance and strategies ,to maintain or restore core cooling, containment, and spent fuel pooi cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in Attachment 2 of Reference 1.COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321 -0098 Telephone:

(402) 825-3811 / Fax: (402) 825-5211wwnp~o NLS20 16008 Page 2 of 2 Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference

2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document Nuclear Energy Institute 12-06, Revision 0 (Reference
3) with clarifications and exceptions identified in Reference
2. Reference 4 provided NPPD's initial status report for Cooper Nuclear Station (CNS) regarding mitigation strategies.

Reference 5 provided CNS' Overall Integrated Plan for diverse and flexible coping strategies (FLEX).Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports.The purpose of this letter is to provide the 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 attachment provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any.This letter contains no new regulatory commitments.

Should you have any questions regarding this report, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.I declare under penalty of perjury that the foregoing is true and correct.Executed on: 0 7_.3/1 ,/(,,'icreySo~s ear A. Limpias Vice President

-Nuclear and Chief Nuclear Officer/bk

Attachment:

Nebraska Public Power District's 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: Regional Administrator, w/attachment USNRC -Region IV Director, w/attachment USNRC -Office of Nuclear Reactor Regulation Senior Resident Inspector, w/attachment USNRC -CNS Cooper Project Manager, w/attachment USNRC -NRR Plant Licensing Branch IV-2 NPG Distribution, w/attachment CNS Records, w/attachment NLS2016008 Attachment Page 1 of 5 Attachment Nebraska Public Power District's 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 Introduction Nebraska Public Power District (NPPD) developed an overall integrated plan (OIP) for Cooper Nuclear Station (CNS) (Reference 1), documenting the diverse and flexible coping strategies (FLEX), in response to Reference

2. This attachment provides an update of milestone accomplishments since submittal of the fifth status report to the OIP (Reference 3), including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.Milestone Accomplishments The following milestone(s) have been completed since the submittal of the fifth status report for the OIP, and are current as of February 1, 2016:* The final Site Response Plan has been approved by NPPD from the National SAFER Response Center (NSRC) and the NSRC has been declared operational for CNS.Milestone Schedule Status The following table provides an update to Attachment 2 of the OIP. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed.

The revised milestone target completion dates do not impact the Order implementation date.Target Revised Target Milestone Completion Status CopeinDt DateCopeinDt 60-day Status Update October 2012 Complete Submit Overall Integrated Plan February 2013 Complete 6-month Status Update August 2013 Complete 6-month Status Update February 2014 Complete Regional Response Center September 2014 Complete Operations Develop Storage Plan May 2014 Complete Purchase FLEX Equipment December 2015 Started June 2016 Refine Strategies December 2015 Started March 2016 (post-NRC review)_______________________

NLS201 6008 Attachment Page 2 of 5 Target Revised Target Milestone Completion Status CopeinDt DateCopeinDt Issue Maintenance Procedures (fr LX qupen)June 2016 Not Started 6-month Status Update August 2014 Complete Develop Strategies

/ Contract Setm r205 C ple with Regional Response Center Setm r205 C ple Develop Training Plan December 2015 Started March 2016 Implementation Outage 1 Fall 2014 Complete Develop Online Mods and September 2015 Started March 2016 Implementing Procedures 6-month Status Update February 2015 Complete Wak-hrugs rOctober 2015 Not Started June 2016 Demonstrations Implement Training June 2016 Not Started 6-month Status Update August 2015 Complete Deeo uag osadOctober 2015 Started March 2016 Implementing Procedures Implemefrt Online Mods and Jue21Strd ProceduresJue21Strd 6-month Status Update February 2016 Complete Perform Staffing Assessment May 2016 Not Started 6-month Status Update August 2016 Not Started Implementation Outage 2 Fall 2016 Not Started Implement Outage Mods and Fal21NoStre ProceduresFal21NoStre Implement Training Updates Fall 2016 Not Started Submit Completion Report Fall 2016 Not Started Changes to Compliance Method The figure on Page 53 of CNS' OIP, "Potential FLEX Storage Locations and Travel Routes," was replaced with two aerial photos showing the finalized locations of the storage buildings and travel routes. Excerpts from the OIP with these photos have been placed on CNS' Fukushima e-portal.

NLS20 16008 Attachment Page 3 of 5 Need for Relief/Relaxation and Basis for the Relief/Relaxation NPPD expects to comply with the Order implementation date and no relief/relaxation is required at this time.Open and Confirmatory Items in the Interim Staff Evaluation In Reference 4, the Nuclear Regulatory Commission (NRC) issued the Interim Staff Evaluation (ISE) for CNS relating to the OIP. The following table provides a summary of the confirmatory items documented in the ISE and the status of each item. There were no open items identified in the ISE.ISE Confirmatory Items Item Number Description Status 3.1.1.2.A Confirm that the required debris removal equipment remains Open functional and deployable to clear obstructions from pathways between the FLEX storage locations and deployment locations, after the FLEX storage building locations are finalized.

3.1.1 .4.A Confirm the location(s) of the staging area(s) for equipment from Open the RRC, and the licensee's plans for transportation from the RRC, staging, and on-site deployment is in accordance with the guidance in NEI 12-06, Sections 5.3.4, 6.3.4, 7.3.4, and 8.3.4, or provide an acceptable alternative to that guidance.3.1.3.1 .A Confirm that when the FLEX equipment storage building Open locations are finalized, separation distance and axis of separation is reviewed to confirm that the building locations are consistent

____________with the recommendations in NEI 12-06, Section 7.3.1.3.1.4.2.A Confirm that obtaining makeup water from the Missouri River Open during an ELAP event adequately addresses NEI 12-06, Section____________8.3.2, consideration 3.3.2.1.1 .A Benchmarks must be identified and discussed which demonstrate Open that Modular Accident Analysis Program (MAAP) is an appropriate code for the simulation of an ELAP event at CNS, consistent with the NRC endorsement (ADAMS Accession No.ML13275A3

18) of the industry position paper on MAAP.3.2.1.1 .B The licensee should demonstrate that the collapsed reactor Open pressure vessel level remains above Top of Active Fuel and the reactor coolant system cool down rate is within technical specifications limits.3.2.1.1 .C The licensee should demonstrate that MAAP is used in Open accordance with Sections 4.1, 4.2, 4.3, 4.4, and 4.5 of the June 2013 position paper (ADAMS Accession No. ML 13190A201).

3.2.1.1 .D The licensee must identify, in using MAAP, the subset of key Open modeling parameters cited from Tables 4-1 through 4-6 of the___________"MAAP Application Guidance, Desktop Reference for Using NLS20 16008 Attachment Page 4 of 5 ISE Confirmatory Items Item Number Description Status MAAP Software, Revision 2" (Electric Power Research Institute Report 1020236, available at www.epri.com).

This should include response at a plant-specific level regarding specific modeling options and parameter choices for key models that would be expected to substantially affect the ELAP analysis performed for CNS.3.2.1.2.A Confirm that the analysis for a long-duration ELAP event shows Open that the reactor recirculation pump seal leakage value does not exceed the value used in analysis of a 4-hour station blackout event.3.2.1.3 .A Confirm that the method for transferring water from the hotwells Open to the ECSTs, including flow path, valves, pumps, and related equipment, when developed, is reliable.3.2.1 .3.B Confirm that the RCIC room heatup evaluation and RCIC room Open___________flooding time evaluation are completed with acceptable results.3.2.1.3.C Confirm that the licensee's staffing assessment is completed and Open it shows that proposed actions from the FLEX strategies can be_____________completed within the specified time constraints.______

3.2.1 .4.A Confirm that the Phase 2 FLEX equipment performance Open criterion, when developed, supports the licensee's mitigation strategies.

3.2.2.1.A Confirm that modifications to the reactor building roof hatch Open provide the ability to maintain adequate SFP area ventilation.

_____3.2.3.A Confirm that CNS's containment venting strategy is finalized and Open that the strategy supports both containment pressure protection and proposed RCIC and Phase 2 FLEX pump operation._____

3.2.3.B With regard to maintaining containment, the implementation of Open BWROG Emergency Procedure Guideline/Severe Accident Guideline, Revision 3, including any associated plant-specific evaluations, must be completed in accordance with the provisions of NRC letter dated January 9, 2014 (ADAMS Accession No. ML13358A206).

3.2.4.2.A Confirm that fan sizing evaluations support adequate ventilation Open in the main control room, in the RCIC room, and in other applicable plant areas.3.2.4.6.A Confirm that analyses addressing heat up in areas that might Open have personnel habitability considerations conform to the guidance in NEI 12-06, Section 3.2.2, Guideline 11, or provide an acceptable alternative to that guidance.3.2.4.7.A Confirm that the design provisions, as well as operational and Open protection requirements for the new on-site well/water treatment equipment used for Phase 2 water sources adequately support___________CNS's proposedELAP strategies.

_____

NLS2016008 Attachment Page 5 of 5 ISE Confirmatory Items Item Number Description Status 3 .2.4.8.A Confirm that adequate electrical interaction and isolation Open considerations are adequately addressed.

3.2.4.8.B Confirm that the sizing of the portable FLEX diesel generators Open adequately supports CNS's ELAP mitigation strategy.3.2.4.8.C Provide single-line diagrams showing the proposed connections Open of Phase 2 and Phase 3 electrical equipment and showing protection information (e.g., breaker, relay, or fuse) and rating for the equipment used when available.

3.2.4.10.A Confirm that the minimum dc voltage and dc load profile for the Open ELAP have been determined, the minimum dc bus voltage and the associated load profile supports CNS's proposed ELAP mitigation strategy.References The following references support the status update to the OIP described in this attachment:

1. NPPD Letter, "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. NPPD Letter, "Nebraska Public Power District's 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- 12-049)," dated August 27, 2015 4. NRC Letter, "Cooper Nuclear Station -Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC No.MF0972)," dated February 11, 2014 N Nebraska Public Power District Always there when :you need us NLS2016008 February 16, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-000 1

Subject:

References:

Nebraska Public Power District's 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)

Cooper Nuclear Station, Docket No. 50-298, DPR-46 1. 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 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. NPPD Letter, "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 29, 2012 5. NPPD Letter, "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

Dear Sir or Madam:

On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued an Order (Reference

1) to Nebraska Public Power District (NPPD). Reference 1 was immediately effective and directs NPPD to develop, implement, and maintain guidance and strategies ,to maintain or restore core cooling, containment, and spent fuel pooi cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in Attachment 2 of Reference 1.COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321 -0098 Telephone:

(402) 825-3811 / Fax: (402) 825-5211wwnp~o NLS20 16008 Page 2 of 2 Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference

2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document Nuclear Energy Institute 12-06, Revision 0 (Reference
3) with clarifications and exceptions identified in Reference
2. Reference 4 provided NPPD's initial status report for Cooper Nuclear Station (CNS) regarding mitigation strategies.

Reference 5 provided CNS' Overall Integrated Plan for diverse and flexible coping strategies (FLEX).Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports.The purpose of this letter is to provide the 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 attachment provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any.This letter contains no new regulatory commitments.

Should you have any questions regarding this report, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.I declare under penalty of perjury that the foregoing is true and correct.Executed on: 0 7_.3/1 ,/(,,'icreySo~s ear A. Limpias Vice President

-Nuclear and Chief Nuclear Officer/bk

Attachment:

Nebraska Public Power District's 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: Regional Administrator, w/attachment USNRC -Region IV Director, w/attachment USNRC -Office of Nuclear Reactor Regulation Senior Resident Inspector, w/attachment USNRC -CNS Cooper Project Manager, w/attachment USNRC -NRR Plant Licensing Branch IV-2 NPG Distribution, w/attachment CNS Records, w/attachment NLS2016008 Attachment Page 1 of 5 Attachment Nebraska Public Power District's 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 Introduction Nebraska Public Power District (NPPD) developed an overall integrated plan (OIP) for Cooper Nuclear Station (CNS) (Reference 1), documenting the diverse and flexible coping strategies (FLEX), in response to Reference

2. This attachment provides an update of milestone accomplishments since submittal of the fifth status report to the OIP (Reference 3), including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.Milestone Accomplishments The following milestone(s) have been completed since the submittal of the fifth status report for the OIP, and are current as of February 1, 2016:* The final Site Response Plan has been approved by NPPD from the National SAFER Response Center (NSRC) and the NSRC has been declared operational for CNS.Milestone Schedule Status The following table provides an update to Attachment 2 of the OIP. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed.

The revised milestone target completion dates do not impact the Order implementation date.Target Revised Target Milestone Completion Status CopeinDt DateCopeinDt 60-day Status Update October 2012 Complete Submit Overall Integrated Plan February 2013 Complete 6-month Status Update August 2013 Complete 6-month Status Update February 2014 Complete Regional Response Center September 2014 Complete Operations Develop Storage Plan May 2014 Complete Purchase FLEX Equipment December 2015 Started June 2016 Refine Strategies December 2015 Started March 2016 (post-NRC review)_______________________

NLS201 6008 Attachment Page 2 of 5 Target Revised Target Milestone Completion Status CopeinDt DateCopeinDt Issue Maintenance Procedures (fr LX qupen)June 2016 Not Started 6-month Status Update August 2014 Complete Develop Strategies

/ Contract Setm r205 C ple with Regional Response Center Setm r205 C ple Develop Training Plan December 2015 Started March 2016 Implementation Outage 1 Fall 2014 Complete Develop Online Mods and September 2015 Started March 2016 Implementing Procedures 6-month Status Update February 2015 Complete Wak-hrugs rOctober 2015 Not Started June 2016 Demonstrations Implement Training June 2016 Not Started 6-month Status Update August 2015 Complete Deeo uag osadOctober 2015 Started March 2016 Implementing Procedures Implemefrt Online Mods and Jue21Strd ProceduresJue21Strd 6-month Status Update February 2016 Complete Perform Staffing Assessment May 2016 Not Started 6-month Status Update August 2016 Not Started Implementation Outage 2 Fall 2016 Not Started Implement Outage Mods and Fal21NoStre ProceduresFal21NoStre Implement Training Updates Fall 2016 Not Started Submit Completion Report Fall 2016 Not Started Changes to Compliance Method The figure on Page 53 of CNS' OIP, "Potential FLEX Storage Locations and Travel Routes," was replaced with two aerial photos showing the finalized locations of the storage buildings and travel routes. Excerpts from the OIP with these photos have been placed on CNS' Fukushima e-portal.

NLS20 16008 Attachment Page 3 of 5 Need for Relief/Relaxation and Basis for the Relief/Relaxation NPPD expects to comply with the Order implementation date and no relief/relaxation is required at this time.Open and Confirmatory Items in the Interim Staff Evaluation In Reference 4, the Nuclear Regulatory Commission (NRC) issued the Interim Staff Evaluation (ISE) for CNS relating to the OIP. The following table provides a summary of the confirmatory items documented in the ISE and the status of each item. There were no open items identified in the ISE.ISE Confirmatory Items Item Number Description Status 3.1.1.2.A Confirm that the required debris removal equipment remains Open functional and deployable to clear obstructions from pathways between the FLEX storage locations and deployment locations, after the FLEX storage building locations are finalized.

3.1.1 .4.A Confirm the location(s) of the staging area(s) for equipment from Open the RRC, and the licensee's plans for transportation from the RRC, staging, and on-site deployment is in accordance with the guidance in NEI 12-06, Sections 5.3.4, 6.3.4, 7.3.4, and 8.3.4, or provide an acceptable alternative to that guidance.3.1.3.1 .A Confirm that when the FLEX equipment storage building Open locations are finalized, separation distance and axis of separation is reviewed to confirm that the building locations are consistent

____________with the recommendations in NEI 12-06, Section 7.3.1.3.1.4.2.A Confirm that obtaining makeup water from the Missouri River Open during an ELAP event adequately addresses NEI 12-06, Section____________8.3.2, consideration 3.3.2.1.1 .A Benchmarks must be identified and discussed which demonstrate Open that Modular Accident Analysis Program (MAAP) is an appropriate code for the simulation of an ELAP event at CNS, consistent with the NRC endorsement (ADAMS Accession No.ML13275A3

18) of the industry position paper on MAAP.3.2.1.1 .B The licensee should demonstrate that the collapsed reactor Open pressure vessel level remains above Top of Active Fuel and the reactor coolant system cool down rate is within technical specifications limits.3.2.1.1 .C The licensee should demonstrate that MAAP is used in Open accordance with Sections 4.1, 4.2, 4.3, 4.4, and 4.5 of the June 2013 position paper (ADAMS Accession No. ML 13190A201).

3.2.1.1 .D The licensee must identify, in using MAAP, the subset of key Open modeling parameters cited from Tables 4-1 through 4-6 of the___________"MAAP Application Guidance, Desktop Reference for Using NLS20 16008 Attachment Page 4 of 5 ISE Confirmatory Items Item Number Description Status MAAP Software, Revision 2" (Electric Power Research Institute Report 1020236, available at www.epri.com).

This should include response at a plant-specific level regarding specific modeling options and parameter choices for key models that would be expected to substantially affect the ELAP analysis performed for CNS.3.2.1.2.A Confirm that the analysis for a long-duration ELAP event shows Open that the reactor recirculation pump seal leakage value does not exceed the value used in analysis of a 4-hour station blackout event.3.2.1.3 .A Confirm that the method for transferring water from the hotwells Open to the ECSTs, including flow path, valves, pumps, and related equipment, when developed, is reliable.3.2.1 .3.B Confirm that the RCIC room heatup evaluation and RCIC room Open___________flooding time evaluation are completed with acceptable results.3.2.1.3.C Confirm that the licensee's staffing assessment is completed and Open it shows that proposed actions from the FLEX strategies can be_____________completed within the specified time constraints.______

3.2.1 .4.A Confirm that the Phase 2 FLEX equipment performance Open criterion, when developed, supports the licensee's mitigation strategies.

3.2.2.1.A Confirm that modifications to the reactor building roof hatch Open provide the ability to maintain adequate SFP area ventilation.

_____3.2.3.A Confirm that CNS's containment venting strategy is finalized and Open that the strategy supports both containment pressure protection and proposed RCIC and Phase 2 FLEX pump operation._____

3.2.3.B With regard to maintaining containment, the implementation of Open BWROG Emergency Procedure Guideline/Severe Accident Guideline, Revision 3, including any associated plant-specific evaluations, must be completed in accordance with the provisions of NRC letter dated January 9, 2014 (ADAMS Accession No. ML13358A206).

3.2.4.2.A Confirm that fan sizing evaluations support adequate ventilation Open in the main control room, in the RCIC room, and in other applicable plant areas.3.2.4.6.A Confirm that analyses addressing heat up in areas that might Open have personnel habitability considerations conform to the guidance in NEI 12-06, Section 3.2.2, Guideline 11, or provide an acceptable alternative to that guidance.3.2.4.7.A Confirm that the design provisions, as well as operational and Open protection requirements for the new on-site well/water treatment equipment used for Phase 2 water sources adequately support___________CNS's proposedELAP strategies.

_____

NLS2016008 Attachment Page 5 of 5 ISE Confirmatory Items Item Number Description Status 3 .2.4.8.A Confirm that adequate electrical interaction and isolation Open considerations are adequately addressed.

3.2.4.8.B Confirm that the sizing of the portable FLEX diesel generators Open adequately supports CNS's ELAP mitigation strategy.3.2.4.8.C Provide single-line diagrams showing the proposed connections Open of Phase 2 and Phase 3 electrical equipment and showing protection information (e.g., breaker, relay, or fuse) and rating for the equipment used when available.

3.2.4.10.A Confirm that the minimum dc voltage and dc load profile for the Open ELAP have been determined, the minimum dc bus voltage and the associated load profile supports CNS's proposed ELAP mitigation strategy.References The following references support the status update to the OIP described in this attachment:

1. NPPD Letter, "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. NPPD Letter, "Nebraska Public Power District's 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- 12-049)," dated August 27, 2015 4. NRC Letter, "Cooper Nuclear Station -Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC No.MF0972)," dated February 11, 2014