Letter Sequence Request |
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TAC:ME3145, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- 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, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
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MONTHYEARML0907106832008-02-17017 February 2008 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1 Project stage: Other ML13064A4352008-03-20020 March 2008 CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4 Project stage: Other ML0914101242008-08-11011 August 2008 Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU Project stage: Other L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008 Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis. Project stage: Other ML0832301122008-10-31031 October 2008 NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate. Project stage: Request ML0832301112008-11-0505 November 2008 Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate Project stage: Other ML0832301142008-11-0505 November 2008 Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation. Project stage: Request ML0834003662008-12-0202 December 2008 Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues Project stage: Acceptance Review ML0834004022008-12-0505 December 2008 Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area Project stage: Other ML0835000992008-12-11011 December 2008 Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis Project stage: Supplement ML0835303022008-12-16016 December 2008 Draft Request for Additional Information, Environmental Issues of EPU Application Project stage: Draft RAI ML0936200242008-12-18018 December 2008 Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate. Project stage: Other ML0835005752008-12-18018 December 2008 Letter Finding 11/5/08 Application for Amendment Acceptable for Review Project stage: Other ML0835309982008-12-18018 December 2008 EPU Application - Additional RAI Question Regarding an Environmental Issue Project stage: RAI ML0835310022008-12-18018 December 2008 Proposed Eou Amendment - Revised RAI Re. Containment Analysis Project stage: RAI ML0914101222008-12-18018 December 2008 Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint Project stage: Other ML0914101212008-12-19019 December 2008 Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint Project stage: Other ML0835901272009-01-14014 January 2009 Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure Project stage: Other ML0835706102009-01-26026 January 2009 Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure Project stage: Other L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009 Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008 Project stage: Other L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009 Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate Project stage: Request L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009 Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008 Project stage: Other ML0904204852009-02-11011 February 2009 Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907106792009-02-17017 February 2009 Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008 Project stage: Request ML0907106802009-02-17017 February 2009 Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424 Project stage: Other L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538 Project stage: Other ML0907106842009-02-17017 February 2009 Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008 Project stage: Other L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009 Project stage: Request ML0907100912009-03-11011 March 2009 Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907200572009-03-12012 March 2009 Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800062009-03-18018 March 2009 Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800042009-03-18018 March 2009 Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment Project stage: Draft RAI ML0907809032009-03-19019 March 2009 Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907809092009-03-19019 March 2009 RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment Project stage: RAI L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009 Project stage: Request ML0908200312009-03-20020 March 2009 Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908200992009-03-23023 March 2009 Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate Project stage: Draft RAI ML0908800022009-03-28028 March 2009 Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908800032009-03-28028 March 2009 Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello Project stage: Draft RAI ML0908800012009-03-29029 March 2009 Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello Project stage: Draft RAI ML0910300212009-04-0606 April 2009 Draft RAI Question from Instrumentation and Controls Branch Re. Proposed EPU Amendment Project stage: Draft RAI ML0910300172009-04-0606 April 2009 Conveys an Additional EPU Draft RAI Question from Instrumentation and Controls Branch Project stage: Draft RAI L-MT-09-025, Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 20092009-04-22022 April 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 2009 Project stage: Request ML0911205782009-04-22022 April 2009 Request for Audit of Implementation of Long-Term Stability Solution Project stage: Other ML0911902092009-04-29029 April 2009 Transmit Revised Draft RAI from the Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0914101232009-05-0606 May 2009 Monticello - Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass Project stage: Other ML0911404702009-05-0707 May 2009 Determination That Submitted Information Can Be Withheld from Public Disclosure Project stage: Other ML0914101202009-05-13013 May 2009 Monticello - Extended Power Uprate: Response to NRC Instrumentation & Controls Branch Request for Additional Information Dated March 11, 2009, and April 6, 2009, and Fire Protection Branch RAIs Dated March 12, 2009 Project stage: Request L-MT-09-045, Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 20092009-05-26026 May 2009 Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 2009 Project stage: Request L-MT-09-029, Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 20092009-05-29029 May 2009 Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 2009 Project stage: Request 2009-02-24
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Category:Letter type:L
MONTHYEARL-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024 Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP) L-MT-24-002, Submittal of Revision 41 to the Updated Safety Analysis Report2024-04-17017 April 2024 Submittal of Revision 41 to the Updated Safety Analysis Report L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022 Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022 Changes to the Emergency Plan L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022 Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency 2024-07-09
[Table view] Category:Legal-Affidavit
MONTHYEARL-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 ML21211A5962021-06-30030 June 2021 Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit L-MT-21-034, Affidavit for Cycle 31 Core Operating Limits Report - NAD-MN-047P2021-05-13013 May 2021 Affidavit for Cycle 31 Core Operating Limits Report - NAD-MN-047P L-MT-16-028, Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information2016-05-18018 May 2016 Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information ML15289A0732015-10-12012 October 2015 Submittal of Power Ascension Testing Results for Replacement Steam Dryer L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015 Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits ML15348A2202015-08-26026 August 2015 Enclosure 9, Areva Affidavits ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow L-MT-14-060, Extended Power Uprate: Replacement Steam Dryer - Response to NRC Requests for Additional Information, Revised Limit Curves and Supporting Information2014-07-22022 July 2014 Extended Power Uprate: Replacement Steam Dryer - Response to NRC Requests for Additional Information, Revised Limit Curves and Supporting Information L-MT-14-016, Calculation 11042-0204, Revision 2, Structural and Allowable Flaw Size Evaluation of the Spent Fuel Storage Canisters with Nonconforming Closure Welds at Monticello Nuclear Generating Plant2014-07-0707 July 2014 Calculation 11042-0204, Revision 2, Structural and Allowable Flaw Size Evaluation of the Spent Fuel Storage Canisters with Nonconforming Closure Welds at Monticello Nuclear Generating Plant ML15348A2152014-07-0707 July 2014 Enclosure 4, General Electric Hitachi (GEH)- Affidavit L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013 Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit ML13282A1412013-10-0404 October 2013 Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses L-MT-13-070, Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses2013-07-31031 July 2013 Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses L-MT-13-059, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Response to Request for Additional Information Reactor Systems Branch and Vessel & Internals Integrity Branch and Supplemental Informati2013-06-26026 June 2013 Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Response to Request for Additional Information Reactor Systems Branch and Vessel & Internals Integrity Branch and Supplemental Information L-MT-13-033, Extended Power Uprate: Secy 11-0014 Use of Containment Accident Pressure - Responses to Requests for Additional Information2013-03-21021 March 2013 Extended Power Uprate: Secy 11-0014 Use of Containment Accident Pressure - Responses to Requests for Additional Information ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML0923903232009-08-10010 August 2009 Enclosure 2 - Continuum Dynamics Affidavit ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference ML0413101222004-04-30030 April 2004 Request for Closed Meeting with USNRC to Discuss NMC Refueling Plans 2023-07-04
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ENCLOSURE 1 CONTAINS PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.390
@ XcelEnergy Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 July 31, 2013 L-MT-13-070 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No. DPR-22
Subject:
Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses (TAC ME3145)
References:
- 1) Letter from T J O'Connor (NSPM), to Document Control Desk (NRC),
"License Amendment Request: Maximum Extended Load Line Limit Analysis Plus," L-MT-10-003, dated January 21, 2010. (ADAMS Accession No. ML100280558)
- 2) Email from T Beltz (NRC) to J Fields (NSPM), "Monticello -
MELLLA+ Review - Draft Requests for Additional Information (TAC No. ME3145).docx," dated April 9, 2013.
In Reference 1, Northern States Power Company, a Minnesota corporation (NSPM),
doing business as Xcel Energy, requested approval of an amendment to the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License (OL) and Technical Specifications (TS). The proposed change would allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain.
In Reference 2 the NRC provided a Request for Additional Information (RAI) pertaining to the quench front velocity in the TRACG model. provides a report from General Electric - Hitachi (GEH) letter, GE-MNGP-AEP-3296R2, "GEH Response to RAI-3 Parts a-g and i." Enclosure 1 contains proprietary information.
Document Control Desk Page 2 provides a non-proprietary copy of the Enclosure 1 RAI responses. The non-proprietary copy of the RAI responses is being provided based on the NRC's expectation that the submitter of the proprietary information should provide, if possible, a non-proprietary version of the document with brackets showing where the proprietary information has been deleted. contains an affidavit executed to support withholding Enclosure 1 from public disclosure. Information in Enclosure 1 contains proprietary information as defined by 10 CFR 2.390. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in 10 CFR 2.390(b)(4). Accordingly, NSPM respectfully requests that the proprietary information in Enclosure 1 be withheld from public disclosure in accordance with 10 CFR 2.390(a)4, as authorized by 10 CFR 9.17(a)4.
Correspondence with respect to the copyright or proprietary aspects of GEH information or the supporting GEH affidavit in Enclosure 3 should be addressed to James F Harrison, Vice President, Regulatory Affairs, GE-Hitachi Nuclear Energy Americas LLC, 3901 Castle Hayne Road, Wilmington, NC 28401.
The supplemental information provided herein does not change the conclusions of the No Significant Hazards Consideration and the Environmental Consideration evaluations provided in Reference 1 for the MELLLA+ license amendment request.
In accordance with 10 CFR 50.91(b), a copy of this application supplement, without enclosures is being provided to the designated Minnesota Official.
Summary of Commitments This letter makes no new commitments or revisions to existing commitments.
Document Control Desk Page 3 I declare under penalty of perjury that the foregoing is true and correct.
Executed on: July ;9, 2013 Mark A. Schimmel Site Vice-President Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosures (3) cc: Regional Administrator, Region Ill, USNRC (w/o enclosures)
Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC (w/o enclosures)
Minnesota Department of Commerce (w/o enclosures)
L-MT-1 3-070 ENCLOSURE 2 GE-MNGP-AEP-3296R2, ENCLOSURE 2 GEH RESPONSE TO RAI-3 PARTS A-G AND I NON-PROPRIETARY 9 pages follow
ENCLOSURE 2 GE-MNGP-AEP-3296R2 GEH Response to RAI-3 Parts a-g and i Non-proprietary Information - Class I (Public)
NON-PROPRIETARY NOTICE This is a non-proprietary version of the Enclosure 1 of GE-MNGP-AEP-3296R2 which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( I].
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)
Page 2 of 9
RAI-3
DetailedCode Questions
- a. Please explain how TRACG differentiates between the quenchfront and the bulk liquid phase in any given node duringA TIWS-I conditionswhen heat is transferredfrom a hot rod to the liquid downstream of the quench front.
Response
TRACG employs a one-dimensional two-fluid model in each fuel channel. Therefore there is one void fraction and one liquid temperature for each node. Heat transfer to the bulk liquid does vary between individual surfaces in the node, such as the surfaces for individual fuel rods, water rods and channel box. Heat transfer to the bulk liquid is calculated according to the heat transfer selection logic described in Section 6.6.2 of the TRACG Model Description LTR [3-1]. The sum of the heat transfer to the liquid from all the surfaces in the node is the net heat transfer to the bulk liquid. If a surface in a node contains a quench front, the quench front heat transfer is calculated as described in Section 6.6.13 of the TRACG Model LTR [3-1] and discussed in the response to RAI 2 in Reference 3-2. The quench front heat transfer is applied to the conduction solution for the surface containing the quench front, where it becomes an energy loss, and added as a source term to the net heat transfer to the bulk liquid in the node.
- b. In the response to RAI 2, the first term of Equation 2-2 describes heat transferaccording tofihn boiling.
Please explain how Equation 2-2 accountsfor only part of a node being in filn boiling.
Response
((
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)
Page 3 of 9
- c. The response to RAI 2 states that "Forconditions where the energy generation in the fuel is high, the net heat removal given by the difference between Equation 2-2 and the energy generationrate is reduced andthe quenching is similarly slowed down."
Please describe by what mechanism is the quenchfront "slowed downi" in TRA CG?
Response
RAI 2 of Reference 3-2 contains the statement: ((
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)
Page 4 of 9
- d. In the response to RAI 2, there is a discussion of Equation 2-3 that notes it is usedfor "conditionswhere the energy generationin the fiuel rod is small."
Please explain how this expression changes if the energy generation is large, as may be the case duringA TWS conditions.
Response
Please see the response to RAI 3c above for conditions where the energy generation is large.
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)
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- e. 1) Equation 2-5 relates the quench front heat transfer coefficient to reflood velocity which, according to the response to RAI 2, is derivedfiom upstream liquid velocity.
However,for non-LOCA scenariossuch as A TWS-I, the cladding hot spot may be in a low void invertedannularflin boiling (IAFB) regime with oscillatoryflow conditions.
Please explain how Equation 2-5 is applied to scenarios such as A TWS-I where upstream liquid velocity may be reversed.
Response
The quench front models in TRACG were developed for LOCA application.
For top down quenching, it is assumed that the quenching is by a falling film. The heat transfer coefficient used in the quench front model for top down quenching is
(( )) as described in Section 6.6.13 of Reference 3-1.
For bottom reflood quenching the heat transfer coefficient used in the quench front model is the maximum of the above value and Equation 2-5 from Reference 3-2. Equation 2-5 from Reference 3-2 has been retained from TRAC-PIA [3-3] and TRAC-BD1 [3-4] and is based on based on Yu, Farmer and Coney [3-5].
For conditions with low void fractions and downward velocities, Equation 2-5 from Reference 3-2 is not applied and the falling film quench front model is conservatively applied.
- 2) Additionally, the quenchfiont propagationwould be well correlatedwith reflood velocity for oscillatoryflow conditions where low void inverted annularflow can develop.
Pleaseprovide the basisfor Equation2-5 as applied to this type of situation.
Response
The basis for the application of Equation 2-5 from Reference 3-2 is described above and is given in Reference 3-5.
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)
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- 3) In the "Monticello Audit slides "presented to the staffduring the audit (ADAMS Accession No. ML123400521), the GEH model was compared to oscillatory results from the Stern Lab tests. However, TRA CG appearedto reduce the clad temperature and quench much faster than the data in the Stern Lab oscillatoiy dryout tests.
Pleaseprovide a descriptionabout why the reduction in clad temperatureand quench occurfaster in TRACG than in the Stern data occurs.
Response
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)
Page 7 of 9 f Equation 6.6-158 in the TRACG Model Description Topical Report is an expression that provides the heat transfer coefficientfor bottom reflood It is reportedly "basedon an empirical correlationdevelopedfor TRAC-P1A based on FLECHTreflood data." The FLECHT data is referenced as:
J.0. Cermak, et al., P WR Full Length Emergency CoolingHeat Transfer (FLECHT)Group I Test Report, WCAP- 7435, Westinghouse Electric Company, January 1970.
Pleaseprovide clarificationas to whether this statement is a carryover of the documentationfor TRA C-P1A?
Is the TRACG source code for this equation based on the Yu, Farmer,and Coney data?
Response
Please see the response to RAI 3.e. Reference 116 in the TRACG Model LTR [3-1] is incorrect; it should be Reference 3-5. This will be corrected in the next revision of Reference 3-1.
- g. A discussion about Equation 2-5 is included in the response to RAI 2. It is stated that the quench front heat transfercoefficient "is consistent with the observations in Reference 2-9." Reference 2-9 notes that in the evaluationof the Harwell data, the heat transfer coefficient in the vicinity of the advancing quenchfront was 10O Btu/hr-f!t-F [5.6 x 1Is W/m 2-K]. When a reflood velocity of 0.5 in/sec is applied to Equation 2-5, the result is a heat transfercoefficient of]. 6x10 7 W/m 2-K Please explain the inconsistencies between this result and the observation in Reference 2-9.
Response
There really is no inconsistency. Reference 2-9 (Thompson) of Reference 3-2 is for falling film rewetting. It shows heat transfer coefficients just behind the quench front on the order of I05 Btu/ft2-hr-F, which in SI units is 6x10 5 W/m 2-K. TRACG uses a heat transfer coefficient of (( )) for the falling film quenching. ((
For bottom reflood TRACG uses the model from References 3-4 and 3-5. The model is implemented as described in the TRAC-BDI Model Description [3-4]:
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)
Page 8 of 9 h= F 13-5)
ATq = TO - T, is the difference between the Leidenfrost temperature and the liquid temperature. In the above expression:
Fq = aF( 3-6) 4 1 F =4.24.1 0 V. 13-7)
(1 + VAT)0.13 for (1+ vAT2) < 40 (3-8) 0.4839(1 + vATq)20.346 for (1 + vAT2) > 40 v, is the liquid velocity.
In the latter expression for a as described in Reference 3-4 and implemented within TRACG ATq = T0 -Te is used. An examination of the original paper by Yu, Farmer and Coney [3-5] has revealed that u. should be calculated as:
=(+ VeAT2) for (1+ veAT2)
- 40 a= , .. (3-9) for (1+ v AT 2) > 40 where AT, = Tsat - Te is the amount of liquid subcooling.
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)
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- i. The response to RAI 2 provides Equation 2-2 to describe total heat removalfrom the fuel.
Please describe the distributionof heat transferredto the two phases in TRA CG.
Response
Please see the response to RAI 3b.
References:
3-1 GE Nuclear Energy, "TRACG Model Description," NEDE 32176P, Revision 4, January 2008.
3-2 Response to Monticello Nuclear Generating Plant - Draft Request for Additional information re: MELLLA+ License Amendment Request Review (TAC No. ME3145) -
Revision 1, GE-MNGP-AEP-3223, December 14, 2012.
3-3 USNRC, "TRAC-P IA: An Advanced Best-Estimate Computer Program for PWR LOCA Analysis," NUREG/CR-0665, Los Alamos Scientific Laboratory, May 1979.
3-4 USNRC, "TRAC-BDI: An Advanced Best-Estimate Computer Program for Boiling Reactor Loss-of-Coolant Accident Analysis," NUREG/CR-2178, October 1981.
3-5 S. K. W. Yu, P. R. Farmer and M. W. Coney, "Methods and Correlations for the Prediction of Quenching Rates on Hot Surfaces," International Journal of Multiphase Flow, 3, 1977, pp. 415-443.
3-6 Presentations from the NRC Audit of Monticello MELLLA+ ATWS/I, October 240"and 2 5 th, GE-MNGP-AEP-321 1, October 30, 2012.
3-7 T. S. Thompson, "On the Process of Rewetting a Hot Surface by a Falling Liquid Film,"
Nuclear Engineering and Design Volume 31, Issue 2, January 1975, pp 234-245.
L-MT-13-070 ENCLOSURE 3 GENERAL ELECTRIC - HITACHI AFFIDAVIT FOR WITHHOLDING PROPRIETARY INFORMATION 3 pages follow
GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, James F. Harrison, state as follows:
(1) I am the Vice President Fuel Licensing of 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, GE-MNGP-AEP-3296R2, "GEH Response to MELLLA Plus Requests for Additional Information," dated July 19, 2013. The GEH proprietary information in Enclosure 1, which is entitled "GEH Response to RAI-3 Parts a-g and i," is identified by a dark red dotted underline inside double square brackets. ((This sentence is an.e.x.ample 3 )). In each case, the superscript notation (3)refers to Paragraph (3) of this affidavit that 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 Proiect v. Nuclear Regulatory Commission, 975 F.2.d 871 (D.C. Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F.2.d 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 GEH or 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, that may include potential products of GEH.
- d. Information that discloses trade secret or potentially patentable subject matter for which it may be desirable to obtain patent protection.
Affidavit for GE-MNGP-AEP-3296R2 Page I of 3
GE-Hitachi Nuclear Energy Americas LLC (5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to the 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. Access to such documents within GEH is limited to a "need to know" basis.
(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 results of an analysis performed by GEH to support the Monticello Maximum Extended Load Line Limit Analysis Plus (MELLLA+) license application. This analysis is part of the GEH MELLLA+ methodology. Development of the MELLLA+ methodology and the supporting analysis techniques and information, and their application to the design, modification, and processes were achieved at a significant cost to GEH.
The development of the evaluation methodology along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes 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 the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
Affidavit for GE-MNGP-AEP-3296R2 Page 2 of 3
GE-Hitachi Nuclear Energy Americas LLC 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 affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed on this 19th day of July, 2013.
James F. Harrison Vice President Fuel Licensing GE-Hitachi Nuclear Energy Americas LLC 3901 Castle Hayne Rd Wilmington, NC 28401 james.harrison@ge.com Affidavit for GE-MNGP-AEP-3296R2 Page 3 of 3