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Category:Audit Plan
MONTHYEARML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML17220A3282017-08-10010 August 2017 Nuclear Regulatory Commission Audits of Licensee Responses to Phase 2 of Order EA-13-109 to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16313A0742016-11-0808 November 2016 NextEra Audit Plan Nov 2016 (DAEC SFP Criticality LAR) ML15160A7152015-06-17017 June 2015 Nuclear Regulatory Commission Plan for the Audit of NextEra Energy, Inc.'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Duane Arnold Energy Center ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 2023-08-03
[Table view] Category:Memoranda
MONTHYEARML22040A2752022-02-11011 February 2022 NSIR Staff Review of the Duane Arnold Energy Center Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, for the Verification of ASM EA-02-104 Incorporation ML21062A0932021-04-21021 April 2021 Memo to File: Final Ea/Fonsi of 2012 and 2015 Decommissioning Funding Plans for Duane Arnold Energy Center Independent Spent Fuel Storage Installation (2012 and 2015) ML21078A1272021-03-30030 March 2021 Final-LIC-504 Closure Memo - 03/30/2021 ML20315A1172020-12-25025 December 2020 DAEC-LIC504-Immediate-Determination-11-02 ML20233A7902020-08-20020 August 2020 Summary of the July 30, 2020, Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Duane Arnold Energy Center and the Point Beach Nuclear Plant ML17115A0782017-04-24024 April 2017 Summary of Outreach/Open House to Discuss the NRC 2016 End-Of-Cycle Plant Performance Assessment of the Duane Arnold Energy Center ML16313A0742016-11-0808 November 2016 NextEra Audit Plan Nov 2016 (DAEC SFP Criticality LAR) ML16225A6772016-08-11011 August 2016 FEMA Letter Dated August 11, 2016, Regarding Approval of Boundary Change for the Duane Arnold Energy Center 10-mile Emergency Planning Zone for Linn County, Iowa ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML14104A9272014-04-23023 April 2014 U.S. Nuclear Regulatory Commission Staff'S Spot-Check Review of Corn Belt Power Cooperative'S 10 Percent Ownership Interest in Duane Arnold Energy Center, Docket No. 50-331, on April 9, 2014 -Finding of No Potential Issues ML14104A9032014-04-23023 April 2014 U.S. Nuclear Regulatory Commission Staff'S Spot-Check Review of Central Iowa Power Cooperative'S 20 Percent Ownership Interest in Duane Arnold Energy Center, Docket No. 50-331, on April 10, 2014- Finding of No Potential Issues ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13154A5112013-06-0404 June 2013 Rai'S Following Ifib Analysis of NextEra Energy'S 2013 Decommissioning Funding Status Reports for Duane Arnold Energy Center and Point Beach Units 1 and 2 ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML1106104272011-03-0707 March 2011 Notice of Forthcoming Pre-Application Meeting with Florida Power & Light Company and NextEra Energy Regarding Turkey Point, Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1, and 2, and Duane Arnold ML1027301332010-10-0707 October 2010 Filing of Federal Register Notice of Availability for the Final Plant-Specific Supplement 42 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants (GEIS) Regarding Duane Arnold Energy Center ML1025301122010-09-10010 September 2010 Minutes for the Meeting of the Duane Arnold Plant License Renewal Subcommittee, June 8, 2010 - Rockville, MD ML1023805222010-09-0202 September 2010 Advisory Committee on Reactor Safeguards Review of the Duane Arnold Energy Center, License Renewal Application-Safety Evaluation Report ML1011303682010-05-0606 May 2010 ACRS Issuance Letter ML1010310002010-04-14014 April 2010 Docketing of April 6, 2010 Nuclear Regulatory Teleconference Notes Pertaining to the License Renewal of the Duane Arnold Energy Center ML0934300622010-03-15015 March 2010 03/31/2010 Notice of Public Meeting to Discuss Draft Supplemental Environmental Impact Statement for the License Renewal of Duane Arnold Energy Center ML1004800772010-02-17017 February 2010 Docketing of February 2, 2010 U.S. Nuclear Regulatory Conference Notes Pertaining to the License Renewal of the Duane Arnold Energy Center ML0924702222009-09-0808 September 2009 Notice of Closed Meeting with Duane Arnold to to Discuss Nextera'S Assessment of the Results of the Duane Arnold Baseline Inspection Conducted NRC ML0921805182009-08-0606 August 2009 Notice of Public Meeting with Florida Power & Light Energy ML0919100122009-07-17017 July 2009 04/22/2009-Summary of Public License Renewal Overview and Environmental Scoping Meetings Related to the Review of the Duane Arnold Energy Center License Renewal Application ML0908505372009-04-0808 April 2009 Forthcoming Meeting to Discuss the Safety Review Process and Environmental Scoping Process for Duane Arnold Energy Center ML0901401912009-01-13013 January 2009 DNMS Input to Integrated Report No. 05000331/2008-005 ML0835705522009-01-0707 January 2009 12/16/08 Summary of Telephone Conference Call Between NRC and FPL Energy Duane Arnold, LLC, Pertaining to the Review Status of Duane Arnold Energy Center, License Renewal Application ML0810601482008-04-0303 April 2008 RAI, MD7420- Draft - Request for Additional Information ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0720000582007-07-26026 July 2007 7/18/07 Public Meeting Summary on the Reactor Oversight Process ML0717602212007-06-22022 June 2007 Receipt of Report on PNNL Review of Ultrasonic Data on Dissimilar Metal Welds at Duane Arnold Energy Center, Unit 1 ML0629903782006-11-0202 November 2006 TSTF-484 LAR SE ML0608901792006-04-0404 April 2006 Forthcoming Meeting with Duane Arnold Energy Center - to Discuss Calculations Associated with the Submittal Pertaining to the Elimination of Main Steamline Radiation Monitor Trips ML0602502942006-01-25025 January 2006 Canceled Notice of Meeting with Nuclear Management Company Regarding Fleet Transition to NFPA Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants ML0533500192005-12-14014 December 2005 Transmittal Related to TAC Nos. MC8713, MC9784 and MC8785 ML0532101352005-11-18018 November 2005 Notice of Meeting with Duane Arnold Energy Center Regarding the Cork Screw Convection Methodology ML0232903632004-09-29029 September 2004 RAI Data for Incorporation Into Power Uprate Review Standard ML0421003322004-06-30030 June 2004 Close-out of Tacs Relating to the Review of 35-day Letters Submitted in Response to the April 29, 2003, Orders Revising the Design Basis and Security Guard Force Training Enhancements and Physical Fitness Requirements ML0417400862004-06-21021 June 2004 All Region III Facility Training Managers Revised NRC Form 398 - Personal Qualification Statement Licensee ML0322701972003-08-26026 August 2003 Transmittal of Electronic Mail on Proprietary Withholding Request Regarding Pressure-Temperature Limit Curves ML0321900062003-08-15015 August 2003 Transmittal of Draft Request for Additional Information on Proposed Amendment to Change Pressure-Temperature Limit Curves ML0311205132003-04-25025 April 2003 Draft RAI and Phone Call Summary Regarding Two New Emergency Action Levels ML0225400802002-09-17017 September 2002 Duane Anold - Draft Requests for Additional Information Regarding Risk-Informed Inservice Inspection Submittal ML0212904652002-05-10010 May 2002 Meeting with Nuclear Management Company, LLC to Discuss the Aspects of Security Orders ML0213400812002-05-0505 May 2002 Risk-Informed Section of Safety Evaluation Pertaining to Duane Arnold Energy Center Proposed Amendment for One-Time On-Line Safety-Related Battery Replacement NRC Generic Letter 1989-111989-06-30030 June 1989 NRC Generic Letter 1989-011: Resolution of Generic Issue 101 Boiling Water Reactor Water Level Redundancy 2022-02-11
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML22005A0862022-01-0404 January 2022 1-4-2022 Email Communication to Duane Arnold Regarding Its ISFSI Related Exemption Request on Supplemental Information Needed ML21335A0712021-12-0101 December 2021 Request for Additional Information - Duane Arnold Energy Center ISFSI Only Emergency Plan ML21335A0702021-12-0101 December 2021 Cover Letter to B. Coffey from K. Conway - Duane Arnold Energy Center RAI Re License Amendment Request for ISFSI Only Emergency Plan ML21250A3002021-09-0808 September 2021 Defueled Physical Security Plan RAI Cover Letter ML21006A4052021-01-0606 January 2021 NRR E-mail Capture - Final RAI - Duane Arnold - Post-Shutdown Decommissioning Activities Report ML20316A0212020-11-10010 November 2020 NRR E-mail Capture - Final RAI - Duane Arnold - Duane Arnold Amendment for Proposed Defueled EP and EAL Scheme ML20153A3772020-05-28028 May 2020 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center Quality Assurance Topical Report (FPL-3) - EPID L-2020-LLQ-0002) ML20141L8132020-05-19019 May 2020 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center (DAEC) - Exemption Request for Security Training Requirements Due to COVID-19 Pandemic - EPID L-2020-LLE-0042 to 45, L-2020-LLE-0051 ML20133K0482020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20127H8662020-05-0505 May 2020 NRR E-mail Capture - Duane Arnold Energy Center (DAEC) - Request for Additional Information (RAI) - Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 1O CFR 50.75(h)(1)(iv) - EPID L-2020-LLE-0011 ML19280A0352019-10-0404 October 2019 NRR E-mail Capture - Final - RAI Related to License Amendment Request (TSCR-182) for Proposed Changes to the Emergency Plan for Permanently Defueled Conditions at Duane Arnold Energy Center (DAEC) - L-2019-LLA-0075 ML18283B0522018-10-0909 October 2018 NRR E-mail Capture - Final Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18255A2922018-09-11011 September 2018 NRR E-mail Capture - Draft Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18247A2002018-08-21021 August 2018 E-Mailed Request for Information for Duane Arnold, Dated 08/21/18 (DRS-M.Holmberg) ML18166A2982018-06-15015 June 2018 NRR E-mail Capture - Draft Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 - EPID L-2017-LLA-0420 ML18088A0102018-03-28028 March 2018 NRR E-mail Capture - Final RAI for Duane Arnold (DAEC) 5th-10 Year ISI (RR-05) ML18058A0522018-02-27027 February 2018 Enclosurequest for Additional Information (Letter: RAI Regarding Florida Power and Light/Nextera Decommissioning Funding Plan Updates for St. Lucie, Units 1 & 2; Seabrook Station; Duane Arnold Energy Center; and Point Beach, Units 1 and 2) ML18037B0032018-02-0606 February 2018 NRR E-mail Capture - Draft Request for Additional Information - Duane Arnold Energy Center (DAEC) - License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, ECCS-Operating - EPID L-2017-LLA-0288 ML17347A8752017-12-12012 December 2017 NRR E-mail Capture - Second Round of Request for Additional Information - Duane Arnold Energy Center (DAEC) - LAR to Adopt TST-542, Revision 2, Reactor Pressure Vessel Water Inventory Control - CAC No. MF9829 ML17277A3652017-10-0404 October 2017 NRR E-mail Capture - Final Request for Additional Information - Duane Arnold - Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control - CAC No. MF9829 ML17240A0082017-08-25025 August 2017 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center (DAEC) - Fifth Ten Year Service Inspection Interval - Relief Request No. RR-04, Rev. 0 - Proposed Alternative for Seal Weld Procedure Qualification - MF937 ML17220A3332017-08-0808 August 2017 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center - Relief Request No. RR-03 - Alternative Requirements for Nozzle Inner Radius and Nozzle-To-Shell Welds - CAC No. MF9374 ML17159A7962017-06-0707 June 2017 17 Duane Arnold Energy Center - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML17068A0632017-03-0808 March 2017 NRR E-mail Capture - Final - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - Revision to Staff Augmentation Times in the Duane Arnold Energy Center (DAEC) Emergency Plan (Eplan) - MF8390 ML16333A4622016-11-28028 November 2016 NRR E-mail Capture - Final Request for Additional Information - Duane Arnold Energy Center - LAR - SFP Criticality - MF7486 ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16313A0742016-11-0808 November 2016 NextEra Audit Plan Nov 2016 (DAEC SFP Criticality LAR) ML16075A0032016-03-14014 March 2016 NRR E-mail Capture - Request for Additional Information - Duane Arnold Energy Center - LAR to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specifications 2.1.1, Reactor Core Safety Limits - MF6618 ML16074A3142016-03-14014 March 2016 NRR E-mail Capture - Second Round RAIs - Duane Arnold Energy Center - LAR (TSCR-143) to Extend Containment Leakage Test Frequency - MF6619 ML16021A0122016-01-21021 January 2016 Request for Additional Information by the Containment & Ventilation Branch and PRA Licensing Branch License Amendment Request - Extension of the 10 CFR 50 Appendix J Containment Type a & Type C Test Intervals ML16022A0092016-01-21021 January 2016 NRR E-mail Capture - Request for Additional Information - LAR to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF6617 ML16014A6962016-01-0707 January 2016 E-Mail: Duane Arnold, MOD/50.59 Inspection Request for Information (Jsp) ML16005A6082015-12-24024 December 2015 E-Mail: Duane Arnold Request for Information; December 24, 2015 (AAS) ML15175A0652015-06-23023 June 2015 Ltr. 06/23/15 Duane Arnold Energy Center - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information Inspection Report 05000331/2015003 (Axd) ML14057A7562014-02-25025 February 2014 14 Duane Arnold CDBI Request for Information ML14031A1462014-01-29029 January 2014 Update to NextEra Energy Duane Arnold, Llc'S Response to NRC Request for Additional Information Associated with Near-Term Task Force Recommendations ML13323B4432013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13255A1982013-09-16016 September 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13175A3932013-06-27027 June 2013 Request for Additional Information for Review Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML13154A5112013-06-0404 June 2013 Rai'S Following Ifib Analysis of NextEra Energy'S 2013 Decommissioning Funding Status Reports for Duane Arnold Energy Center and Point Beach Units 1 and 2 ML12107A0592012-04-11011 April 2012 NRR E-mail Capture - ME7246 - DAEC - Request for Additional Information (RAI) Relief Requests NDR-R003, R010, R011, R014, R015 ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML1201203182012-01-17017 January 2012 Request for Additional Information Amendment to Change Emergency Action Levels ML12011A0602012-01-0404 January 2012 NRR E-mail Capture - ME6508 - DAEC - Emergency Action Level (EAL) Changes ML1132105812011-11-28028 November 2011 Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies. 2024-07-12
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November 8, 2016 MEMORANDUM TO: David J. Wrona, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Robert G. Lukes, Chief /RA/ Nuclear Performance & Code Review Branch Division of Safety Systems Office of Nuclear Reactor Regulation SUBJECT: NUCLEAR REGULATORY COMMISSION PLAN FOR THE AUDIT OF DUANE ARNOLD ENERGY CENTER, REGARDING DRAFT REQUEST FOR ADDITIONAL INFORMATION RESPONSES RELATING TO THE LICENSE AMENDMENT TO REVISE TECHNICAL SPECIFICATIONS FUEL STORAGE REQUIREMENTS (CAC NO. MF7486)
By letter dated March 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16077A234), NextEra Energy Duane Arnold submitted a License Amendment Request (LAR) for the Duane Arnold Energy Center. The proposed amendment would revise Technical Specification 4.3.1, "Fuel Storage, Criticality," and TS 4.3.3, "Fuel Storage, Capacity," to reflect an updated current licensing basis for the facility, as well as add a new requirement in TS 5.5, "Programs and Manuals," for a Spent Fuel Pool (SFP) neutron absorber monitoring program.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed a nuclear criticality safety analysis that was included with the LAR to demonstrate that NRC requirements associated with SFP subcriticality will be met. The staff sent draft Requests for Additional Information (RAIs) to the licensee via email on September 21, 2016, to address potential non-conservatisms in the analysis. Subsequent teleconferences were conducted with the licensee on September 26, 2016, and October 4, 2016, to clarify the RAIs and determine the best approach for a timely resolutions of the issues identified in the RAIs. The staff agreed on a subset of the RAIs that, if adequately addressed, would be sufficient to allow the staff to make a safety determination on this LAR. The licensee committed to develop draft RAI responses, and to support an audit to allow the staff to determine whether the RAI responses are adequate to address the most significant issues. Upon completion of the audit, the draft RAIs will be revised as necessary and issued as final, and the licensee would be expected to provide the needed information on the docket.
CONTACT: Scott T. Krepel, NRR/DSS 301-302-0399 D. Wrona -2- This letter documents the NRC staff's plan to perform a regulatory technical audit of NextEra Energy Duane Arnold's draft RAI responses to determine if any further information will be needed to support a timely completion of the LAR review process.
The enclosed audit plan outlines the process that the NRC staff will follow.
Docket No.: 50-331 Enclosures:
1. Audit Plan 2. Draft Requests for Additional Information D. Wrona -2- This letter documents the NRC staff's plan to perform a regulatory technical audit of NextEra Energy Duane Arnold's draft RAI responses to determine if any further information will be needed to support a timely completion of the LAR review process.
The enclosed audit plan outlines the process that the NRC staff will follow.
Docket No.: 50-331 Enclosures:
1. Audit Plan 2. Draft Requests for Additional Information
DISTRIBUTION: SNPB/RF RLukes SKrepel RidsNrrPMDuaneArnold MChawla
Accession No.: ML16313A074 NRR-106 Office DSS/SNPB DSS/SNPB: BC Name SKrepel RLukes Date 11/8/2016 11/8/2016 OFFICIAL RECORD COPY U.S. NUCLEAR REGULATORY COMMISSION PLAN FOR THE AUDIT OF DUANE ARNOLD ENERGY CENTER, REGARDING DRAFT REQUEST FOR ADDITIONAL INFORMATION RESPONSES RELATING TO THE LICENSE AMENDMENT TO REVISE TECHNICAL SPECIFICATIONS FUEL STORAGE REQUIREMENTS DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 BACKGROUND AND AUDIT BASIS By letter dated March 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16077A234), NextEra Energy Duane Arnold, the licensee, submitted a License Amendment Request (LAR) for the Duane Arnold Energy Center. The proposed amendment would revise Technical Specification (TS) 4.3.1, "Fuel Storage, Criticality," and TS 4.3.3, "Fuel Storage, Capacity," to reflect an updated current licensing basis for the facility, as well as add a new requirement in TS 5.5, "Programs and Manuals," for a Spent Fuel Pool (SFP) neutron absorber monitoring program. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed a nuclear criticality safety analysis that was included with the LAR to demonstrate that NRC requirements associated with SFP subcriticality will be met. The staff sent draft Requests for Additional Information (RAIs) to the licensee via email on September 21, 2016, to address potential non-conservatisms in the analysis. Subsequent teleconferences were conducted with the licensee on September 26, 2016, and October 4, 2016, to clarify the RAIs and determine the best approach for a timely resolutions of the issues identified in the RAIs. The staff agreed on a subset of the RAIs that, if adequately addressed, would be sufficient to allow the staff to make a safety determination on this LAR.
Since this subset of RAIs must be satisfactorily addressed to allow the staff to base a safety finding without requiring further information, the licensee committed to developing draft RAI responses and to support this audit. The purpose of this audit is to allow the NRC staff to review the licensee's draft RAI responses and determine if the responses from the licensee will be adequate. This was determined to be the most efficient approach toward a timely resolution of this LAR review, since the staff will have an opportunity to verify that no further rounds of RAIs will be necessary and no unnecessary burden will be imposed by requiring the licensee to address issues that are no longer necessary to make a safety determination.
Upon completion of this audit, the staff and licensee are expected to make any needed revisions to the draft RAIs and RAI responses to ensure that the information provided will be sufficient to allow the staff to complete the LAR review. The final RAIs will be issued soon after the audit, with an expected response being delivered by the licensee by mid-January. ENCLOSURE 1
- 2 - REGULATORY AUDIT SCOPE AND METHODOLGY The areas of focus for the regulatory audit is the information that will be requested by the NRC staff as part of a series of RAIs. The draft RAIs are included as Enclosure 2, but the final RAIs may be different based on any additional information that is determined to be necessary as a result of this audit. The audit will be conducted and completed over the course of one day.
INFORMATION AND OTHER MATERIAL NECESSARY FOR THE REGULATORY AUDIT The information required for the audit is the licensee's draft responses to the draft RAIs in Enclosure 2.
NRC AUDIT TEAM Title Team Member Affiliation Team Leader, NRR/DORL Mahesh Chawla NRC Technical Lead, NRR/DSS Scott Krepel NRC LOGISTICS The audit will be conducted on November 21, 2016, at the NextEra engineering offices in Jupiter, FL. The licensee will provide four (4) paper copies of the draft RAI responses for the NRC staff's use during the audit. If there is any supporting documentation that may be useful for elaboration and/or clarification of the information provided in the draft RAI responses, the licensee should make it available on demand (paper copy or electronic copy on a licensee-provided laptop are both satisfactory).
Key licensee personnel involved in the development of the draft RAI responses should be made available to respond to any questions from the NRC staff. A conference room should be provided for use by the NRC staff during the audit. DELIVERABLES The NRC team will develop an audit summary report to convey the audit results. The report will be placed in ADAMS within 30 days of the completion of the final audit session. The NRC will also finalize the RAIs as soon as feasible, and issue them to the licensee. The information discussed in the audit may be included, fully or in part, in the development of the NRC technical staff's assessments as a result of this review.
DRAFT REQUESTS FOR ADDITIONAL INFORMATION The applicable Code of Federal Regulations 50.68 requirement is that the k-effective of the Spent Fuel Pool (SFP) storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water. NextEra Duane Arnold, LLC submitted a criticality analysis (Enclosure 4 to the License Amendment Request (LAR)) performed to demonstrate that this regulatory limit will be met if the proposed Technical Specification (TS) limit on the reactivity for fuel stored in the Duane Arnold Energy Center (DAEC) SFP is satisfied. The staff has identified some instances where it is not clear if the reactivity impact due to specific conditions was adequately addressed in the criticality analysis. The potential reactivity impacts may be positive, so the staff needs additional information to verify the regulatory limit will not be challenged by these potential impacts. 1. The proposed TS 4.3.1.1.a revision provides an updated value for the Standard Cold Core Geometry (SCCG) k-infinity limit applicable to the Programmed and Remote Systems Corporation (PaR) SFP racks. The TS is silent regarding which code is to be used to calculate this value, but the DAEC Updated Final Safety Analysis Report (UFSAR) indicates that the lattice code used in licensing applications is TGBLA. Please clarify if the SCCG k-infinity values used for comparison to the TS 4.3.1.1.a limit are to be calculated using TGBLA or CASMO-4, and: a. If TGBLA is to be used, describe why the analysis performed based on CASMO-4 as described in Enclosure 4 to the LAR would be applicable to SCCG k-infinity values as calculated by TGBLA. Include any considerations due to code-to-code biases and uncertainties. b. If CASMO-4 is to be used, describe how the licensing basis and Quality Assurance control program for DAEC will be updated to reflect this intention. 2. Section 5.1.2 of Enclosure 4 to the LAR states that for the MCNP6 calculations, "[t]he initial source is placed in the highest reactive area of the model." Please clarify how the source distribution was established for different calculations, including the interface and accident conditions. In particular, discuss whether a single point source, multiple point sources, or a distributed source was used. 3. Section 6.1 of Enclosure 4 to the LAR discusses sensitivity studies performed to determine limiting conditions to use for depletion. Please confirm that the k-infinity values obtained to determine the reactivity changes are the peak reactivity values from each depletion calculation performed as part of the sensitivity studies. ENCLOSURE 2
- 2 - 4. The sensitivity studies documented in Section 6.1 of Enclosure 4 to the LAR appear to have been performed using controlled conditions, and only consider the reactivity impact to the SCCG k-infinity. Please discuss why the results from the sensitivity study would be expected to remain applicable for uncontrolled conditions, and how the determination of limiting depletion conditions for determination of the maximum SCCG k-infinity would translate to limiting depletion conditions for determination of a limiting bound on the correlation between the SCCG k-infinity and the rack k-infinity. 5. Section 6.6 to Enclosure 4 to the LAR discusses calculations performed to assess the impact of eccentric positioning or rotation of fuel assemblies in the SFP rack cells. The report indicates that the calculations used the base model, which the NRC staff interprets to mean that the limiting GNF2 lattice described in Section 6.4 was used, which was based on an unrodded depletion at 0% void. The radial burnup distribution for the fuel lattice may have a significant impact on these configurations, and control rod insertion would significantly change the radial burnup distribution. There is not sufficient information to evaluate the potential reactivity impact and how it might be offset by any reduction in peak reactivity due to the use of different depletion conditions. Please provide further information regarding the expected reactivity impact for eccentric positioning or rotation in the SFP cells of fuel that has been located in controlled core locations. 6. Section 6.7 of Enclosure 4 to the LAR describes an analysis performed to account for potential blistering on the Boral panels. This possibility is considered to be bounded by the complete displacement of the water between the Boral panels and the surrounding SFP cell walls. Section 9.1.2.2.2 of the DAEC UFSAR indicates that the PaR racks were manufactured in such a way that "[t]he outer can is formed into the inner can at the ends and totally seal welded to isolate the Boral from the pool water." This discussion appears to describe that of an unvented, completely encased installation of the Boral panels in the PaR cell walls. Please discuss whether the UFSAR description is an accurate reflection of the current SFP rack configuration. If it is, Information Notices 1983-29 and 2009-26 describe past incidents where Boral-containing SFP cell walls with this type of configuration experienced issues with bulging. Please address the potential for moderator displacement due to cell wall bulging. 7. Section 6.8 of Enclosure 4 to the LAR discusses the interface between racks. For the interface between PaR racks and the Holtec racks, the criticality analysis report states,
"[t]he density of the fuel pellet in the Holtec rack was reduced by 23% so the infinite keff of both racks was approximately the same-" According to the proposed TS 4.3.1.1.a, the SCCG k-infinity limit for the PaR and Holtec racks would be the same. Therefore, the same limiting fuel lattices could be loaded in both racks. If the Holtec rack configuration is more reactive than the PaR rack configuration, this may impact the interface reactivity by increasing the neutron flux from the Holtec racks into the PaR racks. In addition, this
- 3 - analysis only considered normal conditions. Please provide further discussion of the interface between the PaR racks and Holtec racks, including: a. Justification for the analysis approach discussed in Section 6.8 to capture the reactivity impact of the interface condition. b. Potential impacts due to any postulated accident conditions in the licensing basis for both racks, such as a missing Boral panel from either rack. 8. Section 6.10 of Enclosure 4 to the LAR discusses the accident conditions that were considered in the criticality analysis. If a Boral panel is missing at the time that the SFP rack module is installed in the SFP, this would become part of the normal condition rather than an accident condition. The U.S. Nuclear Regulatory Commission staff is not aware of accidents that may result in movement of an entire Boral panel out of the SFP racks. Please clarify the intent for inclusion of this scenario as a potential accident condition, and if necessary, provide information demonstrating how inadvertent non-installment of a Boral panel was precluded from occurring.