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Category:Letter
MONTHYEARML20211L6822020-08-25025 August 2020 Request for MRP-230 Revision 3 ML20142A3802020-06-10010 June 2020 Memo to ACRS - Transmittal of Safety Evaluation Revision 2 for EPRI Triso Topical Report ML20091L0912020-05-11011 May 2020 U.S. Nuclear Regulatory Commission Proprietary Determination Letter for MRP-189, Revision 3 and MRP-60, Revision 5 (EPID L- 2020-TOP-0007) ML20086M8272020-04-0707 April 2020 Letter to EPRI - Transmittal of Draft Safety Evaluation for EPRI Triso Topical Report ML20022A1732020-03-0202 March 2020 U.S. Nuclear Regulatory Commission Proprietary Determination Letter for Materials Reliability Program: Functionality Analysis for Flexible Operations of Westinghouse-Design Representative PWR Internals (MRP-230, Revision 2-Supplement 2) ML20006D1522020-02-19019 February 2020 U.S. Nuclear Regulatory Commission Verification Letter for Electric Power Research Institute Topical Report MRP 227, Revision 1, - Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline -(L-2 ML20017A3452020-02-10010 February 2020 Request for MRP-60 Rev 5 and MRP-189, Rev 3 ML19291A0062019-10-28028 October 2019 Request for Materials Reliability Program: MRP-230, Flexible Operations Technical Basis Report ML19232A2332019-09-0404 September 2019 Letter Requesting EPRI MRP 2019-002 ML19198A1792019-08-0606 August 2019 Request for Materials Reliability Program: MRP 2019-009, Interim Guidance Regarding MRP-227-A and MRP-227, Revision 1 PWR Core Barrel and Core Support Barrel Inspection Requirements ML19200A2002019-08-0505 August 2019 Electric Power Research Institute, Inc. - Acceptance of Uranium Oxycarbide (Uco) Tristructural Isotropic (Triso) Coated Particle Fuel Performance Topic Report ML19081A0012019-04-25025 April 2019 Final Safety Evaluation for Electric Power Research Institute Topical Report MRP-227, Revision 1, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline ML18275A0692019-02-28028 February 2019 MRP-227 Rev 1 Draft SE Transmittal Letter ML19028A0132019-02-0707 February 2019 Request for Materials Reliability Program: Inspection Standard for Pressurized Water Reactor Internals - 2018 Update (MRP-228, Rev. 3) ML19002A0982019-01-23023 January 2019 Request for Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191, Revision 2) ML18176A1882018-07-12012 July 2018 Operating Experience Request for Additional Information for Electric Power Research Institute Topical Report MRP-227, Revision 1 (CAC No. MF7223; EPID L-2016-TOP-0001) ML18072A1342018-03-23023 March 2018 Request for Materials Reliability Program: Evaluation of Carbon Macrosegregation in Class 1 Reactor Coolant System Forgings (MRP-428) ML18016A0082018-01-29029 January 2018 Final Safety Evaluation of Action Items 1 and 7 from Topical Report MRP-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline ML16238A1332018-01-0303 January 2018 Letter on Draft SE for MRP-227 Action Items 1 and 7 2020-08-25
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 10, 2020 MEMORANDUM TO: Scott W. Moore, Executive Director Advisory Committee on Reactor Safeguards FROM: John D. Monninger, Director /RA/
Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
SUBJECT:
ELECTRIC POWER RESEARCH INSTITUTE - DRAFT SAFETY EVALUATION, REVISION 2 FOR TOPICAL REPORT, URANIUM OXYCARBIDE (UCO) TRISTRUCTURAL ISOTROPIC (TRISO)
COATED PARTICLE FUEL PERFORMANCE: TOPICAL REPORT EPRI-AR-1(NP)
By letter dated May 31, 2019, Electric Power Research Institute (EPRI) submitted topical report (TR) Uranium Oxycarbide (UCO) Tristructural Isotropic (TRISO) Coated Particle Fuel Performance: Topical Report EPRI-AR-1(NP), to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. This TR consolidates the technical bases for the functional performance of UCO-based TRISO-coated particles so these particles can be used by a variety of high temperature reactor (HTR) developers in their designs. EPRIs letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML19155A173. The NRC staff discussed a preliminary set of questions with EPRI during a public meeting on December 9, 2019 (ADAMS Accession No. ML20029E871), and subsequently issued requests for additional information (RAIs) on January 2, 2020 (ADAMS Accession No. ML20009E065). By letters dated February 26, 2020 and March 9, 2020, EPRI submitted responses to the RAIs (ADAMS Accession Nos. ML20058A040 and ML20071D143, respectively).
The NRC staffs draft Safety Evaluation (SE), Revision 2 for TR EPRI-AR-1(NP), can be found at ADAMS Accession No. ML20142A381. Note that in the draft SE, Confirmatory Item refers to planned revisions to the TR submitted in docketed RAI responses that have not yet been formally incorporated into a revision to the TR. The SE, Revision 2, was revised as a result of comments discussed at the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee meeting on May 6, 2020, and will support a future meeting of the ACRS Full Committee.
Docket No.: 99902021 CONTACT: Jordan Hoellman, NRR/DANU 301-415-5481
ML20142A365 Package *via e-mail NRR-106 OFFICE NRR/DANU/UARP/PM
- NAME JHoellman JSegala MHayes DATE 6/11/2020 6/10/2020 5/20/2020 OFFICE OGC/NLO
- NAME OMikula JMonninger (BSmith for)
DATE 5/26/2020 6/10/2020