Letter Sequence Approval |
|---|
|
|
MONTHYEARML18038B3162018-03-15015 March 2018
Transmittal of Final Safety Evaluation for Topical Report ANP-10333P, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (Crda).
Project stage: Approval
ML18128A0022018-05-0808 May 2018, 10 May 2018
Final Safety Evaluation for Topical Report ANP-10333P, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA) (non-proprietary Version)
Project stage: Request
ML18128A0082018-05-10010 May 2018
Transmittal of Non-Proprietary Version of Final Safety Evaluation for Topical Report ANP-10333P, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA)
Project stage: Approval
ML18249A3942018-09-24024 September 2018
Verification of Topical Report ANP-10333P-A, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA)
Project stage: Other
2018-05-10
[Table View] |
|
|---|
Category:Letter
MONTHYEARML23117A0432023-04-20020 April 2023
Framatome, Inc., Part 21 Notification of Existence of a Defect
ML20230A0382020-08-24024 August 2020
Draft Safety Evaluation for Framatome Inc. Topical Report ANP-10323P, Revision 1, Galileo Fuel Rod Thermal Mechanical Methodology for Pressurized Water Reactor
ML20211L7302020-08-0404 August 2020
August 18-20, 2020 Regulatory Audit Plan Letter for Errata to Framatome Inc. Topical Report BAW-10241PA, Revision 1, Bhtp DNB Correlation Applied with Lynxt Topical Report
ML20203M3382020-07-24024 July 2020
Regulatory Audit Plan Letter for August 3-6, 2020, Audit for Framatome Inc. Topical Report Baw 10227, Revision 2, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel
ML20154J9592020-06-0505 June 2020
Draft Safety Evaluation for Framatome Inc. Topical Report ANP-10337, Revision 0, Supplement 1P, Revision 0, Deformable Spacer Grid Element
ML20045C1902020-03-0202 March 2020
Verification Letter of the Approval Version of Framatome Inc. Topical Report ANP-10346P-A, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA
ML19322C9462019-12-31031 December 2019
Verification Letter of the Approval Version of Framatome Inc. Topical Report Anp 10342P-A, Revision 0, Gaia Fuel Assembly Mechanical Design (CAC: MF9078/EPID: L-2016-TOP-0016)
ML19337D5292019-12-30030 December 2019
Permission Granted to Framatome to Receive Data and Data Reports for Rocom Testing Conducted as Part of the PKL2 Project
ML19276E5772019-10-30030 October 2019
Transmittal of Final Safety Evaluation for Framatome Inc. Topical Report ANP-10346, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA (Non-Proprietary Version)
ML19281A7832019-10-22022 October 2019
Request for Withholding Information from Public Disclosure in September 27, 2019, Fourth Response to Request for Additional Information Regarding ANP-10323P, Revision 0
ML19204A0592019-09-24024 September 2019
Transmittal of Final Safety Evaluation for Topical Report ANP-10342P, Revision 0, Gaia Fuel Assembly Mechanical Design
ML19240A9562019-09-12012 September 2019
Verification Letter for Topical Report EMF-93-177, Revision 1, Supplement 2P-A, Revision 1
ML19239A1812019-09-12012 September 2019
Proprietary Determination for August 7, 2019, Publication of EMF-93-177, Revision 1, Supplement 2P-A, Revision 1, Mechanical Design for BWR Fuel Channels: Z4B Material
ML19149A4892019-06-24024 June 2019
Transmittal of Final Safety Evaluation for Topical Report EMF-93-177, Revision 1, Supplement 2P, Revision 1, Mechanical Design for BWR Fuel Channels: Z4B Material
ML19141A1912019-06-0303 June 2019
Transmittal of Final Safety Evaluation for Framatome Inc. Topical Report BAW-10227, Revision 1, Supplement 1P, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel
ML19078A0762019-04-25025 April 2019
Audit Report for the June 11 - 13, 2018, Audit in Support of the Review of ANP-10346P, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA
ML19101A4192019-04-23023 April 2019
Transmittal of Draft Safety Evaluation for Topical Report EMF-93-177, Revision 1, Supplement 2P, Revision 1, Mechanical Design for BWR Fuel Channels: Z4B Material.
ML19043A8682019-04-0808 April 2019
Audit Report for the January 30 - 31, 2019, Audit in Support of the Review of Topical Report BAW-10227P, Revision 1, Supplement 1P, Evaluation of Advanced Cladding and Structural Material (M5) in Pressurized Water Reactor Reactor Fuel
ML18360A2302019-02-0707 February 2019
Request for Withholding Information from Public Disclosure in December 19, 2018, Additional Information Regarding Anp 10342P;Gaia Fuel Assembly Mechanical Design (CAC No. MF9078; EPID L-2016-TOP-0016)
ML18362A3222019-02-0707 February 2019
Request for Withholding Information from Public Disclosure in December 20, 2018, Response to Request for Additional Information Regarding ANP-10323P, Revision 0
ML18355A9802019-01-15015 January 2019
Regulatory Audit Plan for January 30-31, 2019, Audit for Framatome Inc. Topical Report BAW-10227, Revision 1, Supplement 1P,Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel
ML18323A5592018-12-18018 December 2018
Request for Withholding Information from Public Disclosure in October 31, 2018, Revised Response to Request for Additional Information Regarding Topical Report ANP-10332P, Revision 0
ML18257A1912018-11-0707 November 2018
Proprietary Determination Letter for Request for Review and Approval of ANP-10339P, Arita - Artemis/Relap Integrated Transient Analysis Methodology
ML18298A1312018-11-0707 November 2018
Request for Withholding Information from Public Disclosure in October 5, 2018, Publication of ANP-10341P-A, Revision 0, the ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations
ML18285A4242018-11-0707 November 2018
Verification Letter of the Approval Version of Framatome Inc. Topical Report ANP-10297, Revision 0, Supplement 1P-A, Revision 0, the Arcadia Reactor Analysis System for PWRs Methodology Description and Benchmarking Results
ML18299A2842018-11-0707 November 2018
Verification Letter for ANP-10341P-A, Revision 0, the ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations
ML18276A1722018-11-0707 November 2018
Request for Withholding Information from Public Disclosure in September 25, 2018, Publication of Anp 10297, Revision 0, Supplement 1P-A, Revision 0, the Arcadia Reactor Analysis System for PWRs Methodology Description and Benchmarking Resul
ML18250A2172018-11-0707 November 2018
Request for Withholding Information from Public Disclosure in August 31, 2018, Publication of BAW-10247P-A, Supplement 2P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical M
ML18250A1982018-11-0707 November 2018
Request for Withholding Information from Public Disclosure in August 17, 2018, Additional Information Regarding ANP-10341P, the ORFEO-GAIA and ORFEO-NMGRI Critical Heat Flux Correlations
ML18236A4092018-09-24024 September 2018
Transmittal of Final Safety Evaluation for Topical Report ANP-10341P, the ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations
ML18171A2762018-09-24024 September 2018
Request for Withholding Information from Public Disclosure in March 28, 2018, Additional Information Regarding ANO-10340P, Incorporation of Chromia-Doped Fuel Proprieties in Areva Approved Methods (CAC No. MF7707; EPID L-2016-TOP-0004)
ML18170A3002018-09-21021 September 2018
Proprietary Determination Letter for Response to Request for Comment on Draft Safety Evaluation for ANP-10341P, the ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations.
ML18228A8222018-09-21021 September 2018
Transmittal of Request for Additional Information Regarding Topical Report ANP-10346P, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA
ML18234A1002018-09-13013 September 2018
Verification of Approval Version of Framatome Inc., Topical Report ANP-10335P-A, Revision 0, Ace/Atrium 11 Critical Power Correlation
ML18213A1882018-08-22022 August 2018
Verification Letter of the Approval Version of Topical Report ANP-10300P-A, Revision 1, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios (CAC No. ME2979; EPID L-2009-TOP-0004)
ML18179A3522018-08-17017 August 2018
Verification Letter of the Approval Version of Framatome Inc. Topical Report ANP-10340P-A, Revision 0, Incorporation of Chromia-Doped Fuel Properties in Areva Approved Methods
ML18178A6092018-08-0303 August 2018
Transmittal of Final Safety Evaluation for ANP-10297P-A, Revision 0, Supplement 1, the Arcadia Reactor Analysis System for PWRs Methodology Description and Benchmarking Results
ML18193A9862018-07-30030 July 2018
Transmittal of Regulatory Audit Plan for June 11-13, 2018, Audit for Topical Report ANP-10346P, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA
ML18227A1382018-07-27027 July 2018
Framatome, Inc., Response to Confirmatory Order, EA-16-016 - Independent Consultant Review
ML18171A3082018-07-17017 July 2018
Request for Withholding Information from Public Disclosure in April 30, 2018, Response to Request for Additional Information Regarding Topical Report ANP-10332P, Revision 0 (CAC No. MF3829; EPID L-2014-TOP-0004)
ML18173A1612018-07-17017 July 2018
Request for Withholding Information from Public Disclosure in May 31, 2018, Response to Request for Comment on Draft Safety Evaluation for ANP-10297P-A, Revision 0, Supplement 1 (CAC No. MF6469; EPID L-2015-TOP-0005)
ML18179A1272018-07-17017 July 2018
Request for Withholding Information from Public Disclosure in April 23, 2018, Response for Comment on Draft Safety Evaluation for ANP-10335P, Revision 0
ML18155A5172018-06-11011 June 2018
Verification Letter of the Approval Version of Framatome Inc. Topical Report ANP-10337P-A, Revision 0, PWR Fuel Assembly Structural Response to Externally Applied Dynamic Excitations
ML18155A3402018-05-31031 May 2018
Framatome, Inc., Response to Request for Comment on Draft Safety Evaluation for ANP-10297P-A Revision 0, Supplement 1, the Arcadia Reactor Analysis System for PWRs Methodology Description and Benchmarking Results.
ML18120A3572018-05-25025 May 2018
Transmittal of Final Safety Evaluation for Topical Report ANP-10335P, Revision 0, Ace/Atrium 11 Critical Power Correlation.
ML18129A0292018-05-23023 May 2018
Transmittal Letter for Final Safety Evaluation for Topical Report ANP-10340P, Revision 0, Incorporation of Chromia-Doped Fuel Properties in Areva Approved Methods (CAC No. MF7707; EPID L-2016-TOP-0004)
ML18128A2762018-05-10010 May 2018
Transmittal of Final Safety Evaluation for Topical Report ANP-10337P, Revision 0, PWR Fuel Assembly Structural Response to Externally Applied Dynamic Excitations (Non-Proprietary Version)
ML18128A0082018-05-10010 May 2018
Transmittal of Non-Proprietary Version of Final Safety Evaluation for Topical Report ANP-10333P, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA)
ML18089A5772018-05-10010 May 2018
Transmittal of Draft Safety Evaluation for Framatome Inc. Topical Report ANP-10341P, the ORFEO-GAIA and ORFEO-NMGRID Critical Heat Flux Correlations
ML18124A2412018-05-0808 May 2018
Transmittal of Final Safety Evaluation for Areva Inc. Topical Report ANP-10300P, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios (Non-Proprietary Version)
2023-04-20
[Table view] |
Text
May 10, 2018 Mr. Gary Peters, Director Licensing and Regulatory Affairs Framatome Inc.
3315 Old Forest Road Lynchburg, VA 24501
SUBJECT:
FINAL SAFETY EVALUATION FOR TOPICAL REPORT ANP-10333P, REVISION 0, AURORA-B: AN EVALUATION MODEL FOR BOILING WATER REACTORS; APPLICATION TO CONTROL ROD DROP ACCIDENT (CRDA)
(CAC NO. MF3889/EPID: L-2014-TOP-0005)
Dear Mr. Peters:
By letter dated March 31, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14098A331), Framatome Inc. (Framatome) (formerly AREVA Inc.)
submitted Topical Report (TR) ANP-10333P, Revision 0, " AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA)," to the U.S.
Nuclear Regulatory Commission (NRC) staff for review and approval. By letter dated October 25, 2017 (ADAMS Accession No. ML17240A268), an NRC draft safety evaluation (SE) regarding our approval of TR ANP-10333P, Revision 0, was provided for your review and comment. By letter dated December 15, 2017 (ADAMS Accession No. ML17353A223),
Framatome provided comments on the draft SE. The NRC staffs disposition of the Framatome comments on the draft SE are discussed in the attachment (ADAMS Accession No. ML18128A004) to the final SE enclosed with this letter.
The NRC staff has found that TR ANP-10333P, Revision 0, is acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR.
Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the acceptable material described in the TR. When the TR appears as a reference in licensing action requests, our review will ensure that the material presented applies to the specific plant involved. Requests for licensing actions that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards.
G. Peters In accordance with the guidance provided on the NRC website, we request that Framatome publish approved proprietary and non-proprietary versions of TR ANP-10333P, Revision 0, within 3 months of receipt of this letter. The approved versions shall incorporate this letter and the enclosed final SE after the title page. Also, they must contain historical review information, including NRC requests for additional information and your responses. The approved versions shall include an -A (designating approved) following the TR identification symbol.
As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and if the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:
- 1. The RAIs and RAI responses can be included as an Appendix to the accepted version.
- 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.
If future changes to the NRCs regulatory requirements affect the acceptability of this TR, Framatome will be expected to revise the TR appropriately or justify its continued applicability for subsequent referencing. Licensees referencing this TR would be expected to justify its continued applicability or evaluate their plant using the revised TR.
Sincerely,
/RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Project No. 728 Docket No. 99902041
Enclosure:
Final Safety Evaluation (Non-Proprietary)
ML18128A002 (Ltr.); ML18128A003 (SE); ML18128A002 (Pkg.);
ML18128A004 (Attachment); *concurrence via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/BC NAME JRowley, Jr. DMorey DATE 05/8/18 05/10/18 May 10, 2018 Mr. Gary Peters, Director Licensing and Regulatory Affairs Framatome Inc.
3315 Old Forest Road Lynchburg, VA 24501
SUBJECT:
FINAL SAFETY EVALUATION FOR TOPICAL REPORT ANP-10333P, REVISION 0, AURORA-B: AN EVALUATION MODEL FOR BOILING WATER REACTORS; APPLICATION TO CONTROL ROD DROP ACCIDENT (CRDA)
(CAC NO. MF3889/EPID: L-2014-TOP-0005)
Dear Mr. Peters:
By letter dated March 31, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14098A331), Framatome Inc. (Framatome) (formerly AREVA Inc.)
submitted Topical Report (TR) ANP-10333P, Revision 0, " AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA)," to the U.S.
Nuclear Regulatory Commission (NRC) staff for review and approval. By letter dated October 25, 2017 (ADAMS Accession No. ML17240A268), an NRC draft safety evaluation (SE) regarding our approval of TR ANP-10333P, Revision 0, was provided for your review and comment. By letter dated December 15, 2017 (ADAMS Accession No. ML17353A223),
Framatome provided comments on the draft SE. The NRC staffs disposition of the Framatome comments on the draft SE are discussed in the attachment (ADAMS Accession No. ML18128A004) to the final SE enclosed with this letter.
The NRC staff has found that TR ANP-10333P, Revision 0, is acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR.
Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the acceptable material described in the TR. When the TR appears as a reference in licensing action requests, our review will ensure that the material presented applies to the specific plant involved. Requests for licensing actions that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards.
G. Peters In accordance with the guidance provided on the NRC website, we request that Framatome publish approved proprietary and non-proprietary versions of TR ANP-10333P, Revision 0, within 3 months of receipt of this letter. The approved versions shall incorporate this letter and the enclosed final SE after the title page. Also, they must contain historical review information, including NRC requests for additional information and your responses. The approved versions shall include an -A (designating approved) following the TR identification symbol.
As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and if the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:
- 1. The RAIs and RAI responses can be included as an Appendix to the accepted version.
- 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.
If future changes to the NRCs regulatory requirements affect the acceptability of this TR, Framatome will be expected to revise the TR appropriately or justify its continued applicability for subsequent referencing. Licensees referencing this TR would be expected to justify its continued applicability or evaluate their plant using the revised TR.
Sincerely,
/RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Project No. 728 Docket No. 99902041
Enclosure:
Final Safety Evaluation (Non-Proprietary)
ML18128A002 (Ltr.); ML18128A003 (SE); ML18128A002 (Pkg.);
ML18128A004 (Attachment); *concurrence via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/BC NAME JRowley, Jr. DMorey DATE 05/8/18 05/10/18