Letter Sequence Other |
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MONTHYEARML18355A9802019-01-15015 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
Project stage: Other
ML18355A9772019-01-15015 January 2019
Audit Plan for January 30-31, 2019, Audit Supporting Review of Framatome Inc. Topical Report BAW-10227, Revision 1, Supplement 1P, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel
Project stage: Request
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
Project stage: Approval
ML19043A8422019-04-0808 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 (Non-
Project stage: Approval
ML19043A8312019-04-0808 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 PWR Reactor Fuel
Project stage: Request
ML19141A3682019-06-0303 June 2019
Resolution of Framatome Comments on Draft Safety Evaluation for Topical Report BAW-10227,Revision 1, Supplement 1P, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel
Project stage: Draft Approval
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
Project stage: Approval
ML19141A1862019-06-0303 June 2019
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
Project stage: Approval
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
Project stage: Other
ML19232A0242019-09-0606 September 2019
Request for Withholding Information from Public Disclosure in August 6, 2019, Publication of BAW-10227, Revision 1, Supplement 1P-A, Revision 0, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel
Project stage: Withholding Request Acceptance
2019-06-03
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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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Text
September 5, 2019 Mr. Gary Peters, Director Licensing and Regulatory Affairs Framatome Inc.
3315 Old Forest Road Lynchburg, VA 24501
SUBJECT:
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-0031)
Dear Mr. Peters:
By letter dated August 6, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19220A070), Framatome Inc. (Framatome) submitted an approval (-A) version of Topical Report (TR) BAW-10227, Revision 1, Supplement 1P-A, Revision 0, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR [Pressurized Water Reactor] Reactor Fuel," to the U.S. Nuclear Regulatory Commission (NRC) staff.
Framatome has done so in accordance with our request to publish approval proprietary and non-proprietary versions of this TR, as detailed in the transmittal letter dated June 3, 2019, of the NRC staffs final safety evaluation (ADAMS Accession No. ML19141A191) for the original TR.
The NRC staff has completed its review of the approval version of the TR. The NRC staff verified that Framatome has met the requirements and determined that the submitted -A versions are acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the accepted versions of the TR. TR BAW-10227, Revision 1, Supplement 1P-A, Revision 0, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel," is now approved for use in future licensing actions.
Please contact Jonathan G. Rowley of my staff at (301) 415-4053 if you have on questions on this subject.
Sincerely,
/RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902041
ML19232A083 *concurrence via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DSS/SNPB NRR/DLP/PLPB/BC NAME JRowley DHarrison RLukes DMorey DATE 08/20/2019 08/29/2019 09/3/2019 09/5/2019