Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting
Results
Other: CNL-16-008, Update on Progress of Facility Modifications for MSIV Leak Rate, CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report, CNL-18-124, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports, CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report, ML16085A301, ML16105A441, ML16168A026, ML16176A316
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MONTHYEARML15282A2352015-09-21021 September 2015 RHR Heat Exchange K-values Utilities in EPU Containment Analyses Project stage: Request ML15282A1812015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 Project stage: Request ML15282A1522015-09-21021 September 2015 Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate Project stage: Request CNL-15-249, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information2015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information Project stage: Supplement CNL-15-250, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 72015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 7 Project stage: Supplement CNL-15-261, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 3, Interconnection System Impact Study Information2015-12-18018 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 3, Interconnection System Impact Study Information Project stage: Supplement ML16032A0442016-02-0101 February 2016 FWS to NRC, Updated List of Threatened and Endangered Species that May Occur in Your Proposed Project Location for Browns Ferry EPU Project stage: Request ML16041A3072016-02-18018 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16041A0222016-02-25025 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16040A2322016-02-25025 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16049A4632016-02-29029 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-045, Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information2016-03-0909 March 2016 Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information Project stage: Supplement ML16062A0722016-03-15015 March 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-048, Supplement 7, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU)2016-03-24024 March 2016 Supplement 7, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) Project stage: Supplement ML16084A3202016-03-25025 March 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-055, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 8, Response to Request for Additional Information2016-03-28028 March 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 8, Response to Request for Additional Information Project stage: Supplement ML16089A1372016-03-29029 March 2016 NRR E-mail Capture - Correction to Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16064A2862016-04-0404 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16091A0712016-04-0707 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16085A3012016-04-11011 April 2016 Regulatory Audit Plans for April 19 - 21, 2016, Audit at Excel Facility in Rockville, Maryland, in Support of Extended Power Uprate License Amendment Request Project stage: Other ML16085A0792016-04-14014 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16102A3392016-04-14014 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-069, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 11, Responses to Requests for Additional Information2016-04-14014 April 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 11, Responses to Requests for Additional Information Project stage: Supplement ML16104A2452016-04-20020 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016 for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information Project stage: Supplement ML16105A4412016-04-27027 April 2016 Regulatory Audit Plan for May 10-11, 2016, Audit at Excel Facility in Rockville, Maryland, in Support of Extended Power Uprate License Amendment Request Project stage: Other CNL-16-079, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 15, Responses to Requests for Additional Information2016-05-11011 May 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 15, Responses to Requests for Additional Information Project stage: Supplement ML16124A9322016-05-12012 May 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16125A4232016-05-19019 May 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance CNL-16-008, Update on Progress of Facility Modifications for MSIV Leak Rate2016-05-26026 May 2016 Update on Progress of Facility Modifications for MSIV Leak Rate Project stage: Other CNL-16-091, Brown Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Updates Associated with Interconnection System Impact Study Modifications on Proposed Technical Specifications Change TS-505 - Request for License Amendment2016-05-27027 May 2016 Brown Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Updates Associated with Interconnection System Impact Study Modifications on Proposed Technical Specifications Change TS-505 - Request for License Amendments Project stage: Response to RAI CNL-16-094, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 20, Responses to Requests for Additional Information2016-06-0909 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 20, Responses to Requests for Additional Information Project stage: Supplement ML16146A6352016-06-13013 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16161A0642016-06-15015 June 2016 Notice of Forthcoming Closed Meeting with Tennessee Valley Authority and Its Consultant, GEH, Regarding Steam Dryers Structural Adequacy for Browns Ferry Units 1, 2 & 3 Extended Power Uprate (EPU) License Amendment Request (LAR) Project stage: Meeting CNL-16-093, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 19, Responses to Requests for Additional Information2016-06-17017 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 19, Responses to Requests for Additional Information Project stage: Supplement ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16168A0262016-06-23023 June 2016 Summary Report for the April 19 to 21, 2016 Audit in Support of Replacement Steam Dryer Review Associated to Extended Power Uprate License Amendment Request (CAC Nos. MF6741, MF6742, and MF6743) Project stage: Other CNL-16-105, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information2016-06-24024 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information Project stage: Supplement ML16125A4062016-07-0606 July 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16127A6092016-07-0606 July 2016 NRC Letter Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16125A0842016-07-0707 July 2016 Approval for Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16130A6002016-07-0707 July 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16173A0262016-07-0707 July 2016 Approval for Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16176A3162016-07-11011 July 2016 Summary Report for the May 3 to May 5, 2016 Audit in Support Containment Accident Pressure Associated to Extended Power Uprate License Amendment Request Project stage: Other CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates Project stage: Supplement CNL-16-119, Brown Ferry Nuclear Plant, Unit 1, 2 and 3 - Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information Related to Replacement Steam Dryers2016-07-13013 July 2016 Brown Ferry Nuclear Plant, Unit 1, 2 and 3 - Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information Related to Replacement Steam Dryers Project stage: Supplement ML16193A4602016-07-21021 July 2016 June 23, 2016, Summary of Closed Meeting with Tennessee Valley Authority Regarding the Structural Adequacy of Steam Dryers for Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (MF6741, MF6742 Project stage: Meeting ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-116, Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 252016-07-27027 July 2016 Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 25 Project stage: Supplement CNL-16-118, Response to Request for Additional Information on Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 272016-07-29029 July 2016 Response to Request for Additional Information on Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 27 Project stage: Supplement 2016-04-07
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Category:Legal-Affidavit
MONTHYEARML24019A1122023-12-14014 December 2023 Affidavit by Alan B. Meginnis for Presentation Slide Deck Entitled, Modification of Browns Ferry TS to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth Minimizer Inoperable During Reactor Startup, Dated December 2023 ML24019A1722023-12-14014 December 2023 Affidavit by Alan B. Meginnis for ANP-3874P, Revision 2, Browns Ferry Atrium 11 Control Rod Drop Accident Analysis with the AURORA-B CRDA Methodology, Dated March 2021 CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-096, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-09-29029 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-056, Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-04-28028 April 2022 Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-061, Information Transmittal for NRC Confirmatory Calculations Regarding Transition to Atrium 11 Fuel2021-08-0606 August 2021 Information Transmittal for NRC Confirmatory Calculations Regarding Transition to Atrium 11 Fuel CNL-21-053, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535)2021-07-23023 July 2021 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535) CNL-19-125, Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition2019-12-19019 December 2019 Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition CNL-19-117, Extended Power Uprate - Units 1 and 2 Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information2019-12-12012 December 2019 Extended Power Uprate - Units 1 and 2 Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information CNL-19-076, Extended Power Uprate: Unit 1 Replacement Steam Dryer Final Load Definition and Stress Report, Revision 12019-10-10010 October 2019 Extended Power Uprate: Unit 1 Replacement Steam Dryer Final Load Definition and Stress Report, Revision 1 CNL-19-075, Extended Power Uprate - Unit 2 Replacement Steam Dryer Final Load Definition and Stress Report2019-09-19019 September 2019 Extended Power Uprate - Unit 2 Replacement Steam Dryer Final Load Definition and Stress Report CNL-19-042, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Report2019-04-29029 April 2019 Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Report CNL-19-045, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 9, Additional Information Regarding Anticipate Transient Without Scram with ...2019-04-24024 April 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 9, Additional Information Regarding Anticipate Transient Without Scram with ... CNL-19-028, Replacement Steam Dryer Revised Analysis and Limit Curves Report, Supplement 12019-02-14014 February 2019 Replacement Steam Dryer Revised Analysis and Limit Curves Report, Supplement 1 CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information2019-01-25025 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information CNL-19-006, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information2019-01-0202 January 2019 Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports - Supplemental Information CNL-18-141, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report - Supplemental Information2018-12-14014 December 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report - Supplemental Information CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 42018-12-13013 December 2018 Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4 CNL-18-131, Extended Power - Uprate Replacement Steam Dryer Core Flow Sweep Report - Supplemental Information2018-11-15015 November 2018 Extended Power - Uprate Replacement Steam Dryer Core Flow Sweep Report - Supplemental Information CNL-18-124, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports2018-10-24024 October 2018 Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports CNL-18-125, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-10-24024 October 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report CNL-18-103, Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041,.2018-09-0606 September 2018 Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041,. CNL-18-106, Extended Power Uprate Replacement Steam Dryer Core Flow Sweep Test Report2018-08-13013 August 2018 Extended Power Uprate Replacement Steam Dryer Core Flow Sweep Test Report CNL-18-081, Request for Review and Approval of Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041, Revision 12018-06-22022 June 2018 Request for Review and Approval of Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis, Calculation CDQ0000002016000041, Revision 1 CNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 12018-03-0707 March 2018 Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1 CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 302016-09-23023 September 2016 Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30 CNL-16-056, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional Information2016-04-0404 April 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional Information CNL-15-247, Brown Ferry Unit 1, Submittal of Response to NRC Request for Additional Information Re Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506). Enclosure 2 ANP-3458NP Enclose2015-12-28028 December 2015 Brown Ferry Unit 1, Submittal of Response to NRC Request for Additional Information Re Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506). Enclosure 2 ANP-3458NP Enclosed CNL-15-250, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 72015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 7 CNL-15-249, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information2015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information ML15282A2582015-09-17017 September 2015 General Electric Hitachi Affidavits NL-15-169, Browns Ferry, Units 1, 2, and 3, General Electric Hitachi Affidavits2015-09-17017 September 2015 Browns Ferry, Units 1, 2, and 3, General Electric Hitachi Affidavits CNL-15-169, Electric Power Research Institute Affidavit2015-09-14014 September 2015 Electric Power Research Institute Affidavit ML15282A2592015-08-12012 August 2015 Areva Affidavits NL-15-169, Browns Ferry, Units 1, 2, and 3, Areva Affidavits2015-08-12012 August 2015 Browns Ferry, Units 1, 2, and 3, Areva Affidavits CNL-15-103, Enclosure 2, ANP-3414NP Revision 0, Areva RAI Responses for Browns Ferry, Unit 3, Cycle 18 MCPR Safety Limits (Non-proprietary), and Enclosure 3, Affidavit2015-07-0707 July 2015 Enclosure 2, ANP-3414NP Revision 0, Areva RAI Responses for Browns Ferry, Unit 3, Cycle 18 MCPR Safety Limits (Non-proprietary), and Enclosure 3, Affidavit CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical2015-06-0303 June 2015 Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow ML13276A0632013-09-30030 September 2013 Response to Request for Additional Information on Technical Specification Change TS-478 ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML1121500962011-06-0808 June 2011 Appeal of Final Significance Determination of a Red Finding and Reply to a Notice of Violation; EA-11-018 ML1011602992010-04-16016 April 2010 Affidavit of Alan B. Meginnis Regarding Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request ML0902203942009-01-0808 January 2009 Response to Round 23 RAI Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate, Enclosure 2 - Structural Integrity Associates, Inc. Calculation Package 0006982.304, Revision 1 and Encls 4 and 5 ML0807104982008-03-0606 March 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Change TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 16 Request for Additional Information (RAI) - SRXB-74/86 and SRXB-87 Through SRXB-90 ML0721303712007-07-27027 July 2007 Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate - Steam Dryer Evaluations ML0621700042006-08-21021 August 2006 Proprietary Letter, Request for Withholding Information on EPU Round 3 (TS-431) ML0619506702006-07-0606 July 2006 Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Response to NRC Round 6 Request for Additional Information on GE Methods ML0613004362006-05-0505 May 2006 Transmittal of Browns Ferry, Units 1, 2 & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Steam Dryer Stress Report ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference ML0517201312005-07-0101 July 2005 Enclosure, Framatone Non-Propreitary Presentation 2023-12-14
[Table view] Category:Letter type:CNL
MONTHYEARCNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-105, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 222022-11-0808 November 2022 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 22 CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) CNL-22-096, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-09-29029 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-083, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).2022-09-13013 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535). CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322022-08-22022 August 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-076, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel2022-07-28028 July 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-01-17
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2022-04-0606 April 2022 Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-22-028, Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-03-18018 March 2022 Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-052, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)2021-07-21021 July 2021 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531) CNL-21-033, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components2021-04-28028 April 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components CNL-21-017, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)2020-12-29029 December 2020 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099) CNL-20-089, Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518)2020-12-21021 December 2020 Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518) CNL-20-059, Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals2020-08-10010 August 2020 Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals CNL-19-122, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights2019-12-17017 December 2019 Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...2019-08-0808 August 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water... CNL-19-052, Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second2019-07-19019 July 2019 Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information2019-01-25025 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information CNL-19-007, Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus2019-01-16016 January 2019 Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus CNL-19-011, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results2019-01-16016 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results CNL-18-139, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information2018-12-14014 December 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 42018-12-13013 December 2018 Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4 CNL-18-117, Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-462018-10-17017 October 2018 Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-46 CNL-18-120, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ..2018-10-11011 October 2018 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ... ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-032, Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program2018-03-27027 March 2018 Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program CNL-18-011, Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)2018-02-0505 February 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) CNL-17-130, Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For..2017-10-23023 October 2017 Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For.. CNL-17-109, Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Genera2017-09-18018 September 2017 Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generati CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-17-035, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information2017-03-0303 March 2017 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information CNL-17-017, Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects2017-02-0303 February 2017 Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects CNL-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects2017-01-20020 January 2017 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf2017-01-20020 January 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-12-19019 December 2016 Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-16-161, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional..2016-10-13013 October 2016 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional.. CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 302016-09-23023 September 2016 Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30 CNL-16-150, Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 312016-09-21021 September 2016 Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 31 CNL-16-133, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 72016-09-15015 September 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7 CNL-16-152, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information2016-09-12012 September 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information CNL-16-126, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)2016-08-24024 August 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) CNL-16-129, Response to Request for Additional Information Regarding Proposed Technical Specifications (TS) Change TS-505 License Amendments - Extended Power Uprate (EPU) - Supplement 292016-08-0303 August 2016 Response to Request for Additional Information Regarding Proposed Technical Specifications (TS) Change TS-505 License Amendments - Extended Power Uprate (EPU) - Supplement 29 CNL-16-127, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Upgrade (EPU) - Supplement 28, Responses to Requests for Additional Information2016-08-0303 August 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Upgrade (EPU) - Supplement 28, Responses to Requests for Additional Information CNL-16-114, Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate .2016-08-0303 August 2016 Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate . 2024-01-11
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Text
Proprietary Information Withhold from Public Disclosure Under 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 1 Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-16-145 September 23, 2016 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 30, Revised Responses to Requests for Additional Information
References:
- 1. Letter from TVA to NRC, CNL-15-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU), dated September 21, 2015 (ML15282A152)
- 2. Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743), dated June 3, 2016 (ML16144A643)
- 3. Letter from TVA to NRC, CNL-16-117, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 26, Responses to Requests for Additional Information, dated July 29, 2016
- 4. Letter from TVA to NRC, CNL-16-127, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 28, Responses to Requests for Additional Information, dated August 3, 2016 By the Reference 1 letter, Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) for the Extended Power Uprate (EPU) of Browns Ferry Nuclear
U.S. Nuclear Regulatory Commission CNL-16-145 Page 2 September 23, 2016 Plant (BFN) Units 1, 2 and 3. The proposed LAR modifies the renewed operating licenses to increase the maximum authorized core thermal power level from the current licensed thermal power of 3458 megawatts to 3952 megawatts. The Reference 2 letter provided Nuclear Regulatory Commission (NRC) Requests for Additional Information (RAls) related to the replacement steam dryers. to this letter provides revisions to the responses for NRC RAls EMCB-RAls 25, 38, 39, and 43 provided in the Reference 3 letter. Enclosure 1 to this letter also provides a revision to the response to NRC RAI EMCB-RAI 21 provided in the Reference 4 letter.
These revisions to the responses to NRC RAls EMCB-RAls 21 , 25, 38, 39, and 43 are as a result of additional reviews . GE-Hitachi Nuclear Energy Americas LLC (GEH) considers portions of the information provided in Enclosure 1 of this letter to be proprietary and, therefore, exempt from public disclosure pursuant to 10 CFR 2.390, Public inspections, exemptions, requests for withholding . An affidavit for withholding information, executed by GEH, is provided in Enclosure 3. Enclosure 2 to this letter provides a non-proprietary version of the revised responses to the RAls provided in Enclosure 1. Therefore, on behalf of GEH , TVA requests that Enclosure 1 be withheld from public disclosure in accordance with the GEH affidavit and the provisions of 10 CFR 2.390.
TVA has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in the Reference 1 letter. The supplemental information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration . In add ition, the supplemental information in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed license amendment.
Additionally, in accordance with 10 CFR 50.91 (b)(1 ), TVA is sending a copy of this letter to the Alabama State Department of Public Health.
There are no new regulatory commitments associated with this submittal. If there are any questions or if additional information is needed , please contact Edward D. Schrull at (423) 751-3850.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 23rd day of September 2016.
J.
President, Nuclear Licensing Enclosures cc: See Page 3
U.S. Nuclear Regulatory Commission CNL-16-145 Page 3 September 23, 2016
Enclosures:
- 1. Revised Responses to NRC Requests for Additional Information EMCB-RAIs 21, 25, 38, 39, and 43 (Proprietary version)
- 2. Revised Responses to NRC Requests for Additional Information EMCB-RAIs 21, 25, 38, 39, and 43 (Non-proprietary version)
- 3. General Electric Hitachi Affidavit cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama Department of Public Health (w/o Enclosure 1)
Withhold from Public Disclosure Under 10 CFR 2.390 ENCLOSURE 1 Revised Responses to NRC Requests for Additional Information EMCB RAIs 21, 25, 38, 39, and 43 (Proprietary version)
ENCLOSURE 2 Revised Responses to NRC Requests for Additional Information EMCB RAIs 21, 25, 38, 39, and 43 (Non-proprietary version)
Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 1 of 138 EMCB-RAI-21 In Section 4.1.4.4.2 of NEDC-33824P (Reference 6), the (( )) used in estimating the ((
)) of BFN at EPU conditions is based on ((
)). However, BFN and the RP have fundamental differences in the arrangement and resonance frequency of the SRVs. It is not clear why the ((
)). The licensee is requested to demonstrate that ((
)). Since the RP has additional valves other than the SRVs (e.g., ERV and TRV) which exhibited resonant response below EPU conditions, the resonant response of these other valves in the RP can be used to validate the (( ))
which is used in BFN.
GEH Response Revision 1 Two bias terms are defined in Section 4.1.4.4.2 of NEDC-33824P. ((
))
The second bias term addresses the difference in ((
)) (see response to EMCB-RAI-17).
Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 2 of 138 The overall conservatism in the BFN SRV resonance design load is addressed in the response to EMCB-RAI-15.
Changes to NEDC-33824P Revision 0 - BFN Steam Dryer Analysis Report (SDAR)
None Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 3 of 138 EMCB-RAI-25 In Section 4.1.7.4 of NEDC-33824P (pages 4-89 to 4-101 of Reference 6), several features of the dryer acoustic loading of BFN are compared with those of other plants, including the ((
)). In these comparisons, the acoustic pressure characteristics are ((
)). This type of comparison between averages does not reflect the degree of local differences and may result in underestimating the maximum dryer stress. Since the (( )) is considered to be the prototype for the BFN plant, it would be appropriate to first validate this assumption by comparing the individual acoustic sources at the MSL nozzles of both plants. This comparison is needed to substantiate the ((
)). Therefore, the licensee is requested to compare the acoustic sources at the MSL inlets for BFN and the prototype plant at CLTP conditions. These sources can be estimated by means of MSL data based plant based load evaluation (( ))
methodology. Please provide overlaid Power Spectral Density (PSDs) of the sources for each MSL separately.
GEH Response Revision 1 NOTE: This response is revised with an additional response appended to the end of the original response below, and as indicated with a revision bar in the right margin.
Original Response The intent of the comparisons ((
)) The outcome from these comparisons was ((
))
NEDC-33824P Section 4.1.7 presented different ways to compare the acoustic characteristics of the two plants ((
))
It should be noted that the key ((
))
NEDC-33824P presented summaries of these comparisons ((
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GEH Letter No. 175528-021 Page 4 of 138
))
In fact, a review of ((
)) is a good representation of the similarity of the acoustic pressure loads between the ((
)).
Note that the FIV stress analysis is performed by mapping the steam dryer acoustic nodal pressure (a total of (( )) nodes) onto the structural Finite Element (FE) model. The FIV analysis is performed with a very fine degree of localization, ((
))
The main concern raised by Request for Additional Information (RAI)-25 ((
))
The following are additional discussions and comparison plots ((
))
Also, this RAI response includes a discussion of the comparison between ((
))
(( ))
NEDC-33824P presented, in Figure 4.1-48, the BFN ((
)).
Figure 4.1-48 shows (( )). However, NEDC-33824P also presented, in Figures 4.1-49 and 4.1-50, the BFN vs. (( )) Acoustic FRFs Pressure Distribution (3D plots) at several peak frequencies ((
)). A large similarity is observed in these figures, particularly the large similarity over every local area of the BFN and (( )) steam dryers.
More discussion is presented in NEDC-33824P Section 4.1.7.4.a.
(( ))
NEDC-33824P Figure 4.1-52 presented a comparison of BFN Unit 1 ((
)).
It was preferred to present the MSL pressure PSD as ((
))
The advantage of the measured MSL comparison ((
))
Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 5 of 138 The intent of the MSL pressure comparisons ((
))
It was indicated that it would be appropriate to ((
))
Independently, it does not matter so much ((
)). See the next sub-section (On-Dryer Pressure Loads) for the on-dryer pressure loads comparison and the noted degree of local similarities between the two plants.
In addition to the (( )), the main body of NEDC-33824P and NEDC-33824P Appendix D did include several MSL pressure comparisons per ((
)).
NEDC-33824P (Main Body):
((
))
NEDC-33824P Appendix D Figures 4-1 to 4-13:
((
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))
(( ))
The on-dryer pressure loads comparisons are the more appropriate comparisons ((
))
The FIV analysis is performed by mapping the steam dryer acoustic nodal pressure (a total of
(( )) nodes) on the structural FE model. The stress analysis is directly related to the on-dryer pressure loads, ((
)).
NEDC-33824P Figure 4.1-53 presented a summary comparison of BFN ((
)).
To reflect the degree of local differences, additional comparison plots are included in the present RAI response.
((
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))
Appendices A-1 to A-4 present additional comparison ((
))
MSL Dead-Legs (( )):
MSL Measurement:
From the MSL pressure measurements (NEDC-33824P Figure 4.1-51 and NEDC-33824P Appendix D Figures 4-1 to 4-13), ((
)).
Calculated (( )) Dryer Pressure Loads:
From the calculated (( )) pressure loads (NEDC-33824P Figure 4.1-53), and present RAI response (Appendices A-1 to A-4), ((
))
((
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))
Changes to NEDC-33824P Revision 0 - BFN Steam Dryer Analysis Report (SDAR):
((
))
((
))
((
))
Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 9 of 138 GEH Additional Response to EMCB-RAI-25 Use of the (( ))
((
))
Discussion of the BWR/4 versus BFN (( ))
The BFN RSD pressure loads used in the RSD design analyses were reviewed ((
))
The main cause of the difference ((
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))
With the above being stated, the predicted steam dryer loads are ((
))
Comparisons of the ((
))
In summary, the main cause of the differences ((
))
In order to conservatively address the concerns ((
))
During the investigation ((
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))
Figure 25-1
))
((
))
Figure 25-1 (( ))
Updated ASR Based on Effect (( ))
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GEH Letter No. 175528-021 Page 12of 138 A (( )) bias te1m was ((
)).
Table 25-1 (( ))
((
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((
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((
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((
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((
))
Power Ascension Test Plan Contingencies for Loss of Instrumentation There are (( ))
instilllllentation for the lead unit:
- 1) ((
))
If th e ((
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))
The (( )) table below (Table 25-2) has been updated (( )).
Table 25-2 (( ))
((
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((
))
(( ))
As discussed in the response to EMCB-RAI-39(c), ((
))
The methods described in NEDC 33824P Appendix E are maintained ((
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))
Changes to NEDC-33824P Revision 0 - BFN Steam Dryer Analysis Report (SDAR)
- 1. Updated (( )).
- 2. Updated (( )) based on the final SDAR stress analysis results as revised by the RAI responses. ((
))
- 3. Updated ((
)).
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GEH Letter No. 175528-021 Page 20 of 138 Appendix A for GEH Additional Response to EMCB-RAI (( ))
((
))
Figure A ((
))
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((
))
Figure A ((
))
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((
))
Figure A ((
))
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((
))
Figure A ((
))
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GEH Letter No. 175528-021 Page 24 of 138 EMCB-RAI-38 The limits in Table 5.3.1 (time) and Appendix E-1 (frequency) appear to be nonconservative compared to strains observed in other instrumented dryers.
- a. Compare the simulated on-dryer strains for the BFN dryer to those measured on the benchmark BWR/4 dryer.
- b. Provide cumulative strain plots for sensors (( )) to complement the computing root mean square (RMS) values provided in Table 5.3-1.
- c. SGs 6 and 9 have very high potential strains - up to (( )). SGs have a finite life, particularly at high amplitude. Provide information on which frequency(s) contribute most strongly to the strain at these gage locations. Describe the survivability (expected life or number of cycles) of the dryer SGs at these potential strain amplitudes.
- d. Provide alternative procedures for RMS limits and frequency-dependent limit curves for on-dryer SGs based on new data acquired on the lead BFN dryer just prior to power ascension to CLTP. Note that since these methods would be based on data measured on the BFN dryer,
(( )). The current simulations of on-dryer strains may be used to demonstrate the procedure, but not used as actual limits during power ascension.
GEH Response Revision 1 NOTE: This response is revised with an additional response for part (a) appended to the end of the original response to part (a) below, and as indicated with a revision bar in the right margin.
For completeness, the entire response, all parts, is provided here.
- a. For comparison, the analysis scenario of the Browns Ferry Nuclear Plant (BFN) dryer Finite Element Analysis (FEA) model applied with the ((
)) was run, which is referred to as BFN, CR Load later in the presented plots. In this particular analysis, ((
))
The rationale for using the analysis ((
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))
((
))
Figure 38a-1. (( ))
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((
))
Figure 38a-1. (( ))
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((
))
Figure 38a-2. ((
))
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((
))
Figure 38a-3. ((
))
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((
))
Figure 38a-4. ((
))
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((
))
Figure 38a-5. ((
))
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((
))
Figure 38a-6. ((
))
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((
))
Figure 38a-7. ((
))
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((
))
Figure 38a-8. ((
))
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((
))
Figure 38a-9. ((
))
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((
))
Figure 38a-10. ((
))
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((
))
Figure 38a-11. ((
))
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((
))
Figure 38a-12. ((
))
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((
))
Figure 38a-13. ((
))
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((
))
Figure 38a-14. ((
))
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((
))
Figure 38a-15. ((
))
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((
))
Figure 38a-16. ((
))
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((
))
Figure 38a-17. ((
))
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((
))
Figure 38a-18. ((
))
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((
))
Figure 38a-19. ((
))
GEH Additional Response to EMCB-RAI-38, Part (a)
Figures 38a-1S through 38a-18S provide the additional ((
)) comparisons between the BFN replacement dryer with the ((
)) and the BWR/4 prototype dryer with ((
)). These two sets of ((
)). The comparisons are provided at the ((
)). Note in these plots, only the low frequency range
(<135 Hz) is plotted, therefore the (( )).
Specifically, in the plots below, the legend is now detailed:
))
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((
)) as shown in NEDC33824P R0 Table 4.1-25. ((
)) are shown in Figure 38a-1. The sensor locations are also shown in NEDC33824P Appendix C Figures C1 to C3.
The results for the (( )) can be summarized as follows:
- 1. ((
))
- 2. Design improvements have been implemented in the BFN RSD design, which are described in Section 3.2.2.2 of NEDC-33824P R0. These design improvements will
((
))
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((
))
Figure 38a-1S (( ))
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((
))
Figure 38a-2S (( ))
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((
))
Figure 38a-3S (( ))
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((
))
Figure 38a-4S (( ))
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((
))
Figure 38a-5S (( ))
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((
))
Figure 38a-6S (( ))
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((
))
Figure 38a-7S (( ))
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((
))
Figure 38a-8S (( ))
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((
))
Figure 38a-9S (( ))
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((
))
Figure 38a-10S (( ))
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((
))
Figure 38a-11S (( ))
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((
))
Figure 38a-12S ((
))
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((
))
Figure 38a-13S ((
))
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((
))
Figure 38a-14S (( ))
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((
))
Figure 38a-15S ((
))
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((
))
Figure 38a-16S ((
))
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((
))
Figure 38a-17S ((
))
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((
))
Figure 38a-18S ((
))
- b. To complement ((
))
It is necessary to stress that ((
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As described in Section 5.4 of NEDC-33824P Appendix E, ((
))
((
))
Figure 38b-1. ((
))
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((
))
Figure 38b-2. ((
))
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((
))
Figure 38b-3. ((
))
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((
))
Figure 38b-4. ((
))
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((
))
Figure 38b-5. ((
))
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((
))
Figure 38b-6. ((
))
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((
))
Figure 38b-7. ((
))
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((
))
Figure 38b-8. ((
))
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((
))
Figure 38b-9. ((
))
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((
))
Figure 38b-10. ((
))
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((
))
Figure 38b-11. ((
))
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((
))
Figure 38b-12. ((
))
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GEH Letter No. 175528-021 Page 76of138 Table 38b-1. ((
))
((
))
- c. ((
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Table 38c-1: ((
))
((
))
The use of the Ni-Cr-Fe fatigue Curve C (Figure 38c-1) from the American Society of Mechanical Engineers (ASME)Section III (Division 1, Appendix I, 1995) for the fatigue evaluation on the strain gage product (with the wire made of Ni-CrV) is considered conservative.
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\"- ........
26
\ '"'"~
-- Curve A 24 vi
.. 22
~ ~ ...
0 20
.l j ~~
18
~~
- Curve B I
16
........ I r--..
14 """'- Curve C 12 106 NOTE . Number of cyclei, N E = 28 3 X 106 PSI Figure 38c-1 (Figure I-9.2.2) Design Feature Curves for Austenitic Steels, Nickel-Chromium-Iron Alloy, Nickel-Iron-Chromium Alloy, and Nickel-Copper Alloy for S a ~ 28.2 ksi, for Temperatures Not Exceeding 800°F (For Sa>28.2 ksi, use Figure I-9.2.1)
The strain gage product specification and some supplementaiy test data from the manufacturer can be used to address the survivability of the strain gages. The strain gages of Model 'KHC-10-120 ' supplied by Kyowa Electronic Instnnnents Co., Ltd (Kyowa) has been and continue to be used in the BWR/4 and BWR/6 diyer EPU instnnnentation process. In the product specification, the fatigue life at room temperature is identified as 4x 105
(+/- l OOOµm/m), (i.e. , 4x105 cycles with strain level +/-1000 µs (micro-strain)). The extra supplementa1y test data. were provided by Kyowa and sUilllllai*ized in Table 38c-2. The test results were available in a paper (Reference 38-1) published in conjunction with the Japan Atomic Energy Research Institute (JAERI) in November 1983.
Table 38c-2: Comparison of KYOWA Fatigue Test Data with (( ))
Strain Fatigue Strain Gage Operation Level Life Integrity Temperature (au:) (cycles) Hold/Not?
KHC 75.2°F No info1mation Product +/-1000 4xl05 (24° C) provided Specification Strain gage is not KHC Test 1 +/-300 l x107 repo1ied broken Strain gage is KHC Test 2 +/-1000 2x106 932°F r eported broken (500° c) Strain gage is not KHC Test 3 +/-500 5x106 repo1ied broken Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 79 of 138
((
)) the time duration required for the power ascension test to complete, which is (( )).
- d. The procedure for the Root Mean Square (RMS) limits and frequency-dependent limit curves for on-dryer Strain Gages (SGs) based on new data acquired on the lead BFN dryer is
(( ))
Appendix E presented the power ascension test plan and limit curves (on-dryer and Main Steam Line (MSL) based) for the Browns Ferry Nuclear Plant (BFN) replacement steam dryers. Section 5.0 of Appendix E discussed the (( ))
limit curves for on-dryer strain gages based on the Flow-Induced Vibration (FIV) analysis results developed from ((
))
Lead unit power ascension process was presented in Appendix E, Figure 3.2-1. ((
))
It is noted that for BFN dryer limit curve updates with the BFN on-dryer measurements,
((
))
The methodology for maximum stress calculation and acceptance limit updates with on-dryer strain measurement is consistent ((
))
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GEH Letter No. 175528-021 Page 80 of 138
((
))
Figure 38d-1. (( ))
As presented in the (( )) Figure 3.2-1 ((
))
Measured Data:
(( ))
Predicted Data:
((
))
Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 81 of 138 Reference 38-1. Evaluation Test of Stability for High Temperature Strain Gages (in Japanese), ,
No. 309, November 1983.
Changes to NEDC-33824P Revision 0 - BFN Steam Dryer Analysis Report (SDAR):
Appendix E: Power Ascension Test Plan Limit Curves (On-Dryer & MSL Based)
((
))
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GEH Letter No. 175528-021 Page 82 of 138
((
))
((
))
((
))
(continued on next page)
Figure 3.2-1: Browns Ferry (( ))
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GEH Letter No. 175528-021 Page 83 of 138
((
))
((
))
Figure 3.2-1: Browns Ferry (( )) (continued)
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GEH Letter No. 175528-021 Page 84 of 138 EMCB-RAI-39 GEH computes ((
)). The final alternating stress ratios (ASRs) at EPU shown in Table 4.4-1 on pages 4-152 and 4-153 (Reference 6) are above 2.0, and additional details of the five most highly stressed dryer regions are provided in Section 6 of Appendix D (Reference 10) of Attachment 40 (Ref. 6). However, not enough peak stress locations were addressed in the plots provided. Provide the following additional information.
- a. Table 8.1-4 of Appendix-A (p. A-88 of Reference 8) states that a ((
)). Provide the numerical value of the (( )) used in the static analysis. Also, provide a justification for the magnitude of the (( )) value.
- b. The instrument mast on BFN unit 3 RSD used for on-dryer instrumentation may influence the dryer stresses in the vicinity of the mast. Please clarify the following:
- i. Are the ASRs shown in Table 4.4-1 (pages 4-152 and 4-153 of Reference 6) based on a structural finite element model of the RSD with the instrumentation mast, without the instrumentation mast or an envelope of with and without the mast?
ii. If the ASRs in Table 4.4-1 are based on a dryer model without the mast, provide ASRs for a model that includes the mast.
- c. Based on Section 5.1 (page 5-1), and Section 4.1 (p. A-16) of Appendix-A (Reference 8) it appears that the ASRs shown in Table 4.4-1 are ((
)). This issue is being discussed in the ASME Code committees, and has not been resolved. Therefore, provide adjusted Table 4.4-1 ASRs applying the ((
))
- d. Provide spectra and stress accumulation plots for the five most highly stressed upper dryer and for the five most highly stressed lower dryer locations. Highlight the relative contributions to total stress of the (( )), the SRV resonance peak(s), and the VPF peak.
GEH Response Revision 1 NOTE: This response is revised for part (c) only, as indicated with a revision bar in the right margin. For completeness, the entire response, all parts, is provided here.
- a. The acoustic load on the face of the steam dryer hood during a Main Steam Line Break (MSLB) event consists of ((
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GEH Letter No. 175528-021 Page 85 of 138
))
Figure 39-1 shows an example of the typical (( ))
time histories for several points on the dryer hood. The ((
)) at each location on the dryer hood can be obtained from the corresponding
(( )) time history as shown in Figure 39-1. The acoustic loads applied on the steam dryer outer hood for the MSLB are obtained by applying the ((
)). To account for the dynamic effect from the MSLB transient event ((
)). This factor is defined ((
)).
Because deflection, spring forces, and stresses in the linear elastic structure analysis are all proportional, the ((
)). In Reference 39-1 the responses for one-degree elastic systems (un-damped) subjected to symmetrical triangular load pulse are calculated.
Figure 39-2 (Figure 2.6(c) in Reference 39-1) shows the typical responses for this type of forcing function which start at zero and reach a maximum F1 at one-half the total force duration td, with T as the natural period of the system. The maximum response as a function of td/T is given by Figure 39-3 (Figure 2.8(a) in Reference 39-1). ((
)) As shown in Figure 39-1, the time histories of MSLB acoustic loads ((
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GEH Letter No. 175528-021 Page 86 of 138
))
((
))
Figure 39-1. Typical Local Normalized Pressure vs Time and Peak Normalized Pressure Loads on the Hood Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 87 of 138 Figure 39-2. Typical Responses of One-Degree Elastic Systems (Un-damped) Subjected to Symmetrical Triangular Load Pulse (T is the natural period of the system)
Figure 39-3. Maximum Response of One-Degree Elastic Systems (Un-damped)
Subjected to Symmetrical Triangular Load Pulse (T is the natural period of the system)
- b. ((
))
Although the dryer Finite Element Model (FEM) used to generate Flow-Induced Vibration (FIV) ASR values ((
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GEH Letter No. 175528-021 Page 88 of 138
))
To evaluate the global impact of the instrumentation mast ((
)) the RSD with and without the instrumentation mast was performed up to frequency of (( )), which covered the ((
)). Resulting ((
)) by inclusion of the instrumentation mast in the model. Additionally, a selected (( )) was performed to evaluate the ((
))
Figure 39-4 shows the structural finite element model of the RSD with the instrumentation mast model, (( )). Table 39-1 is the
((
)) are shown in Figures 39-5, 39-6, and 39-7, which are mainly the (( )).
Global steam dryer ((
)). From Figures 39-8 and 39-9, the ((
)).
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GEH Letter No. 175528-021 Page 89 of 138
((
))
Figure 39-4. (( ))
Table 39-1: (( ))
((
))
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GEH Letter No. 175528-021 Page 90 of 138
((
))
Figure 39-5. (( ))
((
))
Figure 39-6. (( ))
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GEH Letter No. 175528-021 Page 91 of 138
((
))
Figure 39-7. (( ))
((
))
Figure 39-8. Steam Dryer Modes at (( ))
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GEH Letter No. 175528-021 Page 92 of 138
((
))
Figure 39-9. Steam Dryer Modes at (( ))
To evaluate the (( )), the FIV stress analysis is performed to the ((
)). The stress intensity contour plot of the component of ((
)) is shown in Figure 39-10. The maximum stress intensity is at ((
)) is shown in Figure 39-11. The instrumentation mast is ((
)) in Figure 39-11. ((
)) When excluding the stress at these (( ))
as shown in the close look of the (( )) at the bottom left of Figure 39-12, which is ((
)) as shown in Figure 39-12. ((
)) as shown in Figure 39-13, ((
))
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GEH Letter No. 175528-021 Page 93 of 138
((
))
Figure 39-10. ((
))
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GEH Letter No. 175528-021 Page 94 of 138
((
))
Figure 39-11. (( ))
((
))
Figure 39-12. ((
))
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GEH Letter No. 175528-021 Page 95 of 138
((
))
Figure 39-13. ((
))
In addition, all the mast structure components have been analyzed for ((
))
- c. ASRs shown in Table 4.4-1 are (( )). For components with stresses calculated directly from the FEM, ((
)) from NEDC-33824P would result in some component ((
))
Section NG-3222.4(e) of the ASME Boiler and Pressure Vessel (B&PV) Code requires correction of fatigue calculations for the Youngs modulus ratio. However, as noted in Section 4.3 of NEDC-33824P the steam dryer is a non-safety related item and is classified as an Internal Structure as defined in the ASME B&PV Code,Section III. While the steam dryer is not a component governed by the ASME B&PV Code, the design complies with stress and fatigue criteria for core support structures, ASME B&PV Code Section III, Subsection NG-3000. NEDC-33824P Section 4.3 does, however, ((
)) is discussed below.
The data used to generate the fatigue curve in ASME B&PV Code,Section III, Appendix I, Table I-9.2 includes correction of the fatigue data for the effect of mean stress using the Goodman approach and strength properties at room temperature. GEH review of technical literature on the Goodman approach showed no specific limitation related to temperature. In Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 96 of 138 fact, Reference 39.3 demonstrated an application of the Goodman diagram for 600°F stainless steel data.
When the mean stress correction (MSC) is performed considering strength values at the reactor operating temperature and EC is also applied, the resulting endurance limit of the austenitic stainless steel increases significantly, see Table 39-1a.
Table39-1a Revised Fatigue Limit as a Function of Temperature for Austenitic Stainless Steel - Includes EC and MSC Temperature (°F) 70 200 300 400 500 550 600 Revised Fatigue Limit 13.6 15.1 15.8 15.5 15.2 15.0 14.8 (ksi)
Applying the revised fatigue endurance limit to NEDC-33824P Table 4.4-1 stress values would (( )). Therefore, the NEDC-33824P Table 4.4-1 ((
)). The ASR values documented in NEDC-33824P Table 4.4-1 are ((
)).
In addition to the conservatism in the design fatigue limit of 13.6 ksi when considering the
((
)), there are several additional conservatisms in the BFN replacement dryer fatigue analysis.
These conservatisms were introduced in the development of the final stress adjustment terms listed in Table 4.2-7 of NEDC-33824P and are discussed below:
SRV Acoustic Resonance EPU Scale Factor: As described in the response to BFN EPU-EMCB-RAI-15, the scale model testing performed for BFN showed that the maximum measured SRV acoustic resonance pressure load at EPU was 3.5 times the SRV resonance pressure load at CLTP. ((
)).
Mesh Convergence Factor: ((
)). The mesh convergence studies where the ((
)) was developed are described in Section 4.2.2. ((
))
Recirculation Pump Vane Passing Frequency Loads: The recirculation pump vane passing frequency (VPF) loading is discussed in NEDC-33824P Section 4.1.5.4. There are Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 97 of 138 several conservatisms associated with the way the dryer response to the VPF loads has been addressed in the BFN RSD analysis. ((
))
Core Flow Effect: ((
)) This core flow effect is described in Section 4.1.5.3. ((
))
An additional conservatism was introduced into the BFN RSD stress results by the
((
)). These concerns are described in the supplemental Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 98 of 138 response to BFN EPU-EMCB-RAI-25. To address the concerns, ((
)). Investigation into the root causes for the ((
)). A minor error was identified in the inputs used in the development of the ((
)). Estimates correcting for this error
(( )). While this error correction may not resolve all the concerns expressed in the RAI, it does indicate that most of the difference in the dryer loads in the ((
)).
In conclusion, the fatigue acceptance criterion of 13.6 ksi used in the BFN RSD analysis is conservative when considering the temperature effects on both the Youngs modulus ratio and on the maximum retained mean stress. Therefore, a separate temperature correction for the Youngs modulus ratio alone is not necessary.
- d. In the ((
))
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GEH Letter No. 175528-021 Page 99 of 138 Table 39-2: ((
))
Time Shift Time LF HF Combined Alternating Component Name Ad.justed Ad.justed Adjusted Load Case Interval Stress Ratio Stress Stress Stress
((
))
Note:
- 1. ((
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))
((
))
Figure 39-14a Non-Proprietary Information - Class I (Public)
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))
Figure 39-14b Non-Proprietary Information - Class I (Public)
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))
Figure 39-14c Non-Proprietary Information - Class I (Public)
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))
Figure 39-15a Non-Proprietary Information - Class I (Public)
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))
Figure 39-15b Non-Proprietary Information - Class I (Public)
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))
Figure 39-15c Non-Proprietary Information - Class I (Public)
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))
Figure 39-16a Non-Proprietary Information - Class I (Public)
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))
Figure 39-16b Non-Proprietary Information - Class I (Public)
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))
Figure 39-16c Non-Proprietary Information - Class I (Public)
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))
Figure 39-17a Non-Proprietary Information - Class I (Public)
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))
Figure 39-17b Non-Proprietary Information - Class I (Public)
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))
Figure 39-17c Non-Proprietary Information - Class I (Public)
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))
Figure 39-18a Non-Proprietary Information - Class I (Public)
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))
Figure 39-18b Non-Proprietary Information - Class I (Public)
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))
Figure 39-18c Non-Proprietary Information - Class I (Public)
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))
Figure 39-19a Non-Proprietary Information - Class I (Public)
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))
Figure 39-19b Non-Proprietary Information - Class I (Public)
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))
Figure 39-19c Non-Proprietary Information - Class I (Public)
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))
Figure 39-20a Non-Proprietary Information - Class I (Public)
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))
Figure 39-20b Non-Proprietary Information - Class I (Public)
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))
Figure 39-20c Non-Proprietary Information - Class I (Public)
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))
Figure 39-21a Non-Proprietary Information - Class I (Public)
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))
Figure 39-21b Non-Proprietary Information - Class I (Public)
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))
Figure 39-21c Non-Proprietary Information - Class I (Public)
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))
Figure 39-22a Non-Proprietary Information - Class I (Public)
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))
Figure 39-22b Non-Proprietary Information - Class I (Public)
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))
Figure 39-22c Non-Proprietary Information - Class I (Public)
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))
Figure 39-23a Non-Proprietary Information - Class I (Public)
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))
Figure 39-23b Non-Proprietary Information - Class I (Public)
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))
Figure 39-23c Non-Proprietary Information - Class I (Public)
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))
Figure 39-24a Non-Proprietary Information - Class I (Public)
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((
))
Figure 39-24b Non-Proprietary Information - Class I (Public)
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((
))
Figure 39-24c
References:
39-1. John M. Biggs, Introduction to Structural Dynamics, McGraw-Hill Book Companies, 1964.
39.2 An Examination of the Role of the Assumed Young's Modulus Value at the High Cycle End of ASME Code Fatigue Curve for Stainless Steels. Ranganath, Sampath and Mehta, Hardayal, S. Boston: Pressure Vessels & Piping Conference, 2015.
39.3 MJ Manjoine and RE Tome, Proposed Design Criteria for High Cycle Fatigue of Stainless Steels, International Conference on Advances in Life Prediction Methods, ASME, 1983, pp. 51-57.
Changes to NEDC-33824P Revision 0 - BFN Steam Dryer Analysis Report (SDAR):
None Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 133 of 138 EMCB-RAI-43 Provide a quantitative justification that ANSYS shell elements used to model the steam dryer in the finite element structural analysis of the steam dryer adequately capture peak stresses.
GEH Response Revision 1 In ANSYS Version 14.0 (Reference 43-1), SHELL181 is the recommended four-node structural shell element for modeling thin to moderately-thick shell structures. The SHELL181 element formulation assumes the transverse shear is a parabolic distribution through the thickness (i.e. zero transverse shear stress at the top and bottom fibers and maximum at middle fiber). The ANSYS SHELL63 element type is a legacy element type in Version 14.0. It is formulated for analyzing relatively thin shell structures where transverse shear stiffness is negligible with respect to the in-plane stiffness. The ANSYS SHELL43 element type is also a legacy element type in Version 14.0. The SHELL43 element formulation assumes a uniform transverse shear distribution through the plate thickness and is well-suited for modeling thin to moderately thick structures. Both SHELL43 and SHELL63 element types are undocumented; however, these elements are (( )). The replacement steam dryer (RSD) finite element model (FEM) ((
)). The reason for this choice is ((
))
To determine the consequence of the transverse shear assumption in the ANSYS element formulation for the three element types, SHELL181, SHELL63, and SHELL43, a simplified study using the ANSYS verification manual test case VM39 (Reference 43-1) was performed.
This test case uses a 10° sector of a circular plate with a center hole to study the differences between the three element types (see Figure 43-1). The plate thickness for the study is 0.25 inches and the inner (b) and outer (a) radii are 10 inches and 30 inches, respectively. For the material, the elastic modulus is 30 MSI and Poissons ratio is 0.3. Symmetric boundary condition configurations are applied along the two radial edges with the inner diameter constrained in all six degrees of freedom. In order to test the transverse shear effect, the loading is modified as a total 4 lb. vertical force applied evenly at outer edge two nodes (Nodes 7 and 17) of the 10° sector as shown in Figure 43-1. This simplified test case configuration is similar to the (( )).
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GEH Letter No. 175528-021 Page 134 of 138 Figure 43-1 Finite Element Model Description for Test Case VM39 with Vertical Force Applied Table 43-1 shows comparisons of the outer edge deflection and the average element component stress SX in X (~ radial) direction for the inner diameter (Element 1) and outer diameter (Element 6) elements, as well as the peak component stress SX (maximum element node stress) for the inner diameter (Element 1), using the SHELL181 (ANSYS recommended element type) results as a base reference. The comparisons show the differences to be insignificant. However, the SHELL43 results are virtually identical to the SHELL181 results for the case analyzed.
To further illustrate the ANSYS transverse shear stress assumption for the three element types, Figures 43-2 to 43-4 provide the component stress listing at each node for Element 1 for the SHELL63, SHELL181 and SHELL43 element types, respectively. The results indicate that although there is no significant difference for the dominant in-plane stresses (SX and SY); the non-zero transverse shear stresses (SXZ and SYZ) are computed for SHELL181 and SHELL43 element types and not for the SHELL63 element type. Noting that the listed output contains three sets of data for the top, bottom, and middle fibers respectively, the SHELL181 top and bottom fibers assume a zero transverse shear stress with a maximum transverse shear stress in the middle fiber, while the SHELL43 element type assumes the transverse shear stress to be distributed uniformly throughout the thickness. Therefore, to adequately model locations where the transverse shear effect cannot be neglected, the SHELL181 or SHELL43 element types are recommended.
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GEH Letter No. 175528-021 Page 135 of 138 Table 43-1 Results Obtained from SHELL63, SHELL181 and SHELL43 Percent Percent SHELL181 SHELL63 SHELL43 Difference Difference (63-181)/181 (43-181)/181 Deflection at
-0.05755 -0.05850 -0.05757 1.6422% 0.0201%
Outer Edge (in)
Average SX Stress in 168.06 177.02 168.06 5.3263% -0.0001%
Element 6 (psi)
Average SX Stress in 2,449.00 2,424.04 2,449.01 -1.0194% 0.0002%
Element 1 (psi)
Peak SX Stress in Element 1 2,515.30 2,525.40 2,515.40 0.4015% 0.0040%
(psi)
PRINT S ELEMENT SOLUTION PER ELEMENT
- POST! ELEMENT NODAL STRESS LISTING *****
LOAD STEP= 1 SUBSTEP= 1 TIME= 1 . 0000 LOAD CASE= 0 SHELL REStn.TS FOR TOP /BOTTOM ALSO MID WHERE APPROPRIATE THE FOLLOWING X,Y, Z VALUES ARE IN GLOBAL COORDINATES ELEMENT= 1 SHELL63 NODE sx SY sz SXY SYZ sxz 1 2525 . 4 749.11 0. 0000 - 16. 783 0.0000 0. 0000 2 2373 . 1 1040.2 0. 0000 - 3. 6686 0.0000 0. 0000 12 234 1. 5 1086. 6 0.0000 233.04 0. 0000 0.0000 11 2456.2 803 . 78 0.0000 318.99 0. 0000 0.0000 1 -2525 . 4 -749.11 0. 0000 16 . 783 0.0000 0. 0000 2 - 2373 . 1 - 1040.2 0. 0000 3. 6686 0.0000 0. 0000 12 -234 1. 5 -1086 . 6 0.0000 -233.04 0. 0000 0.0000 11 -2456.2 -803 . 78 0.0000 -3 18.99 0. 0000 0.0000 1 0. 0000 0.0000 0. 0000 0. 0000 0.0000 0. 0000 2 0. 0000 0.0000 0. 0000 0. 0000 0.0000 0. 0000 12 0.0000 0. 0000 0.0000 0.0000 0. 0000 0.0000 11 0.0000 0. 0000 0.0000 0.0000 0. 0000 0.0000 Figure 43-2 Element Component Stresses (psi) for Element #1 Using SHELL63 Non-Proprietary Information - Class I (Public)
GEH Letter No. 175528-021 Page 136 of 138 Figure 43-3 Element Component Stresses (psi) for Element #1 Using SHELL181 Figure 43-4 Element Component Stresses (psi) for Element #1 Using SHELL43 During the RSD FEM development, two FIV full transient dynamic analysis test runs were performed using a ((
))
Although SHELL181 is the ANSYS recommended element type, the VM39 case study shows that the SHELL43 element type and SHELL181 element type calculate approximately the same result. Table 43-2 presents the comparison of the ((
)) as taken from Table 4.4-1 of NEDC-33824P Revision 0. ((
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GEH Letter No. 175528-021 Page 137of138
)); therefore, the results for these components are not applicable to this Request for Additional Info1mation (RAI) response. The results show that ((
))
The final version of the Browns Feny Nuclear Plant (BFN) RSD FEM is primarily comprised of ANSYS ((
))
Table 43-2
((
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GEH Letter No. 175528-021 Page 138 of 138
))
In addition, a comparison of peak stresses (maximum element node stresses SX) for SHELL43, SHELL63, and SHELL181 is provided in Table 43-1. The peak stress comparison shows that the conclusion provided in Revision 0 of the response to EMCB-RAI-43 is unchanged.
It should be noted that the model used to compare SHELL181, SHELL63 and SHELL43 for the EMCB-RAI-43 response includes a stress concentration. As shown in Figure 43-1 and described in the RAI response, the test case is a 10° sector of a circular plate with a center hole. The nodes along the inner diameter of the plate are constrained in all six degrees of freedom. The 4 lb.
vertical force is applied at the outer edge nodes. Similar to a cantilever beam, the higher stresses occur at the element closer to the fixed boundaries. In Table 43-1, the element component stress in X direction (SX) in Element #1 is much higher than the SX stress in Element #6, which clearly shows the stress concentration at the inner edge which is the discontinuity location. This test case configuration is similar to the base plate-to-mid support ring connection in the BFN replacement steam dryer FEM. Therefore, the results from this case study are considered to be adequate and there is no need to perform additional studies.
Reference 43-1. ANSYS Help Documentation Release 14.0 SAS IP, Inc.
Changes to NEDC-33824P Revision 0 - BFN Steam Dryer Analysis Report (SDAR)
None
ENCLOSURE 3 General Electric Hitachi Affidavit
GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, Peter M. Yandow, state as follows:
(1) I am Vice President, NPP/Services Licensing, Regulatory Affairs, GE-Hitachi Nuclear Energy Americas LLC (GEH), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Enclosure 1 of GEH letter 175528-021, GEH Revised Responses to RAIs 21, 25, 38a, 39c and 43 in Support of the Browns Ferry Steam Dryer Replacement, dated September 16, 2016. The GEH proprietary information in Enclosure 1, which is entitled GEH Revised Responses to EMCB RAIs 25, 38a, 39c and 43 in Support of TVA Browns Ferry Replacement Steam Dryer, is identified by a dotted underline inside double square brackets. ((This sentence is an example.{3})) Figures and large objects are identified with double square brackets before and after the object. In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 U.S.C. Sec. 552(b)(4), and the Trade Secrets Act, 18 U.S.C.
Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F.2d 871 (D.C. Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F.2d 1280 (D.C. Cir. 1983).
(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over other companies;
- b. Information that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, resulting in potential products to GEH; Affidavit for GEH Letter No. 175528-021 Page 1 of 3
GE-Hitachi Nuclear Energy Americas LLC
- d. Information that discloses trade secret or potentially patentable subject matter for which it may be desirable to obtain patent protection.
(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary or confidentiality agreements that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in the following paragraphs (6) and (7).
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary or confidentiality agreements.
(8) The information identified in paragraph (2), above, is classified as proprietary because it contains detailed GEH design information of the methodology used in the design and analysis of the steam dryers for the GEH Boiling Water Reactor (BWR). Development of these methods, techniques, and information and their application for the design, modification, and analyses methodologies and processes was achieved at a significant cost to GEH.
The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience and information databases that constitute a major GEH asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply Affidavit for GEH Letter No. 175528-021 Page 2 of 3
GE-Hitachi Nuclear Energy Americas LLC the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on this 16th day of September 2016.
Peter M. Yandow Vice President, NPP/Services Licensing Regulatory Affairs GE-Hitachi Nuclear Energy Americas LLC 3901 Castle Hayne Road Wilmington, NC 28401 Peter.Yandow@ge.com Affidavit for GEH Letter No. 175528-021 Page 3 of 3