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Category:Acceptance Review Letter
MONTHYEARML20049H7052020-02-0707 February 2020
Acceptance for Review of BAW-10227P, Revision 2 (Email)
ML19240A9562019-09-12012 September 2019
Verification Letter for Topical Report EMF-93-177, Revision 1, Supplement 2P-A, Revision 1
ML19232A0832019-09-0505 September 2019
Verification Letter of the Approval Version of Framatome Inc. Topical Report Baw 10227, Revision 1, Supplement 1P-A, Revision 0 Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel (CAC MF9716/EPID L-2017-TOP-003
ML19183A0102019-07-25025 July 2019
Verification Review Letter for Topical Report ANP-10332P-A, Revision 0, AURORA-B: an Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios
ML18345A1592018-12-18018 December 2018
Acceptance Letter for Review of Topical Report ANP-10339P, Arita -AREMIS/RELAP Integrated Transient Analysis Methodology
ML18325A1932018-12-0606 December 2018
Acceptance for Review of Framatome Inc. Topical Report ANP-10337, Revision 0, Supplement 1P, Revision 0, Deformable Spacer Grid Element
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
ML18284A2572018-11-0707 November 2018
Acceptance for Review of Framatome Inc. Topical Report EMF 93-177, Revision 1, Supplement 2P, Revision 1, Mechanical Design for BWR Fuel Channels: Z4B Material
ML18254A2452018-09-24024 September 2018
Verification of the Approval Version of Topical Report BAW-10247P-A, Supplement 2P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical Methods
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)
ML18059A9542018-03-13013 March 2018
Acceptance Review Letter for Framatome Topical Report ANP-10346P, Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA
2020-02-07
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Category:E-Mail
MONTHYEARML20105A4382020-04-14014 April 2020
Transmittal Email of Requests for Additional Information Regarding Topical Report ANP-10339P, Revision 0 (Arita) (Round 2)
ML20049H7052020-02-0707 February 2020
Acceptance for Review of BAW-10227P, Revision 2 (Email)
ML19347C1932019-12-10010 December 2019
Email Transmittal of Request for Additional Information Questions Regarding Topical Report ANP-10339P, Revision 0, Arita - Artemis/Relap Integrated Transient Analysis Methodology
ML19347C2432019-12-0909 December 2019
Email Documentation of Acceptance for Review of Topical Report ANP-10344P, Revision 0, Best-Estimate Enhanced Option III Methodology
ML19137A0882019-05-15015 May 2019
Email Transmitting Request for Additional Information for ANP-10337P, Revision 0, Supplement 1P, Revision 0, Deformable Spacer Grid Element
2020-04-14
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Text
From: Rowley, Jonathan To: "PETERS Gary (Framatome)"
Cc: ELLIOTT Gayle (Framatome); "HOLM Jerald (Framatome)"; Morey, Dennis
Subject:
Acceptance for Review of BAW-10227P, Revision 2 Date: Friday, February 07, 2020 2:40:00 PM Mr. Peters By letter dated December 31, 2019 (Agencywide Documents Access and Management System Accession No. ML20003E146), Framatome Inc. (Framatome) submitted for U.S.
Nuclear Regulatory Commission (NRC) staff review Topical Report (TR) BAW-10227P, Revision 2, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel." The NRC staff has performed an acceptance review of TR BAW10227P, Revision
- 2. We have found that the material presented is sufficient to begin our review.
In the submittal letter, Framatome requested approval by December 2020 with the use of the Limited Safety Evaluation process proposed for Revision 8 of LIC-500. The NRC staff does not agree the incoming TR should be considered limited in scope per the new definitions proposed for LIC-500, Revision 8. While the NRC staff does recognize that the TR itself has been previously approved, the NRC staff cannot determine with reasonable certainty that the expansion of models to higher burn-ups constitutes a limited scope review. In short, due to the NRC staffs uncertainty about the review required in ensuring the credibility of models at higher burn-ups, the NRC staff is not able to confirm that this TR should be considered of limited scope. However, the NRC staff can support the requested December 2020 review timeline provided that review of TR ANP-10323P, Revision 1, GALILEO Fuel Rod Thermal-Mechanical Methodology for Pressurized Water Reactors,"
and accompanying draft safety evaluation (SE) has been sufficiently completed.
The NRC staff expects to issue its requests for additional information by July 10, 2020, and issue its draft SE by December 27, 2020. This schedule information takes in consideration the NRCs current review priorities and available technical resources and may be subject to change. If modifications to these dates are deemed necessary, we will provide appropriate updates to this information. The NRC staff estimates that the review will require approximately 470 staff hours including project management time.
Jonathan Rowley, Project Manager U.S. Nuclear Regulatory Commission (NRC)
Office of Nuclear Reactor Regulation (NRR)
Division of Operating Reactor Licensing (DORL)
Licensing Projects Branch (LLPB)
Phone: 301-415-4053 Email: jonathan.rowley@nrc.gov