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Category:Letter
MONTHYEARML20141L3142020-06-0909 June 2020
MRP-227, Rev 1-A Supplemental Information Final SE Transmittal Email
ML19253A0602020-02-24024 February 2020
Proprietary Determination of EPRI Presentation Material for 9/11/19, Closed Mtg to Discuss Plans for Submittal of BWRVIP-315: Vessel and Internals Project, Reactor Internals Aging Management Evaluation for Extended Operations
ML19296A0092020-01-15015 January 2020
U.S. Nuclear Regulatory Commission Verification Letter and Proprietary Determination for - BWRVIP-241-A: BWR Vessel and Internals Project, Probabilistic Fracture Mechanics Evaluation for the Boiling Water Reactor Nozzle-To-Vessel
ML19296A0102020-01-15015 January 2020
U.S. Nuclear Regulatory Commission Verification Letter and Proprietary Determination for - BWRVIP-108-A: BWR Vessel and Internals Project, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor
ML19296A0112020-01-15015 January 2020
U.S. Nuclear Regulatory Commission Verification Letter and Proprietary Determination for - BWRVIP-41, Revision 4-A: BWR Vessel and Internals Project, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines
ML19240A0262019-10-0707 October 2019
Acceptance Review and Proprietary Determination of Electric Power Research Institute Topical Report BWRVIP-329, BWR (Boiling Water Reactor) Vessel and Internals Project, Updated Probalistic Fracture Mechanics Analyses for BWR RPV
ML19175A1532019-09-0505 September 2019
Proprietary Determination of Electric Power Research Institute Revised Response to Requests for Additional Information Eseb RAI-1 on BWRVIP-25, Revision 1, Boiling Water Reactor Vessel and Internals Project, BWR Core Plate Inspection and Fl
ML19198A0102019-07-23023 July 2019
Approval of Change in the BWRVIP Integrated Surveillance Program Capsule Test Schedule to Accommodate Early Closure
ML19171A0022019-07-22022 July 2019
U.S. Nuclear Regulatory Commission Verification Letter and Proprietary Determination for BWRVIP-62-A (2018 Update): BWR Vessel and Internals Project, Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection,
ML19196A1072019-07-11011 July 2019
EPRI - Request for Permission to Dispose of Reconstituted Surveillance Specimens from the Columbia Generating Station Reactor Vessel
ML19100A0022019-04-25025 April 2019
Acceptance Review for Electric Power Research Institute Topical Report BWRVIP-321: BWR Vessel and Internals Project, Plan for Extension of the Bwr Integrated Surveillance Program (ISP) Through the Second License Renewal (Slr).
ML19091A2592019-04-23023 April 2019
Proprietary Determination of Electric Power Research Institute Topical Report BWRVIP-321: BWR Vessel and Internals Project, Plan for Extension of the BWR Integrated Surveillance Program (ISP) Through the Second License Renewal (Slr). (EPID:
ML18288A1902018-11-14014 November 2018
Proprietary Determination of Electric Power Research Institute Responses for RAI on BWRVIP-25, Rev. 1, Boiling Water Reactor Vessel and Internals Project, BWR Core Plate Inspection and Flaw Evaluation Guidelines (CAC No. MF8863; EPID L-2016
ML18270A0902018-11-0505 November 2018
Proprietary Determination of Electric Power Research Institute Information for September 26, 2018, Meeting on Subsequent License Renewal
ML18269A1192018-09-24024 September 2018
Docket No. 99902016 - September 26, 2018 Meeting with NRC to Discuss Second License Renewal Activities for BWRs
ML18243A4832018-08-29029 August 2018
Electric Power Research Institute - Submittal of BWRVIP-319NP: BWR Vessel and Internals Project, Testing and Evaluation of the Hatch Unit 2 120 Degrees Surveillance Capsule
ML18142A0192018-07-0606 July 2018
Final SE Related to BWRVIP-62-A, Boiling Water Reactor Vessel and Internals Project, Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection, Use of Online Noble Metal Chemistry in Boiling Water Reactors
ML18130A0242018-07-0202 July 2018
Final Nonproprietary Safety Evaluation for BWRVIP-41, Revision 4, BWRVIP Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (NRC-2018-0123;EPID L-2014-TOP-0008)
ML18130A0502018-06-26026 June 2018
Transmittal Letter Regarding Final Proprietary Safety Evaluation for Electric Power Research Institute Topical Report BWRVIP-41, Revision 4, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (CAC No. MF4887; EPID L-2014-TOP-00
ML18107A6072018-05-15015 May 2018
Transmittal Letter Regarding Supplemental SE Related to BWRVIP-62-A, BWRVIP, Technical Basis for Inspection Relief for BWR Internal; Components with Hydrogen Injection Use of Online Noble Metal Chemistry in Boiling Water Reactors
ML18095A0122018-05-0101 May 2018
U.S. Nuclear Regulatory Commission Approval and Proprietary Determination Letter for BWRVIP-139, Revision 1-A: BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines
ML17171A3172018-04-20020 April 2018
Transmittal Letter for Draft Safety Evaluation for BWRVIP-41, Revision 4, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines
ML17004A2562018-04-16016 April 2018
U.S. Nuclear Regulatory Commission Approval and Proprietary Determination Letter for Electric Power Research Institute BWRVIP-42, Revision 1-A
ML18043A0902018-04-0909 April 2018
U.S. Nuclear Regulatory Commission Approval and Proprietary Determination Letter for BWRVIP-234-A: BWR Vessel and Internals Project, Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steels for BWR Internals
ML18023A4382018-04-0202 April 2018
U.S. Nuclear Regulatory Commission Approval and Proprietary Determination Letter for BWRVIP-183-A Report, BWR Vessel and Internals Project - Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines
ML18029A0022018-02-13013 February 2018
Proprietary Determination of Electric Power Research Institute Topical Reports MRP-175 and MRP-211
ML18031A0112018-02-13013 February 2018
Proprietary Determination of Electric Power Research Institute Topical Reports Submitted Via October 5, 2017 Letter
2020-06-09
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Kyle, By letter dated December 3, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19339G364), the Electric Power Research Institute (EPRI) submitted Submittal of MRP-227 Revision 1-A, Final Published Version Electric Power Research Institute Topical Report, entitled Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluations Guideline, for NRC [US Nuclear Regulatory Commission] Acceptance (CAC NO. MF7740) (ADAMS Accession No. ML19339G348).
The NRC staff provided a draft safety evaluation (SE) to EPRI for comment via email dated May 14, 2020 (ADAMS Accession No. ML201227H669). By letter dated May 22, 2020 (ADAMS Accession No. ML20146A002), EPRI informed the NRC staff that there was no proprietary information in the draft SE and had no comments on its accuracy or clarity.
The NRC staff has found that the supplemental information provided, is acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the submittal and in the enclosed final SE. The final SE defines the basis for our acceptance of the supplemental information. A copy of the final SE is attached to this email.
Our acceptance applies only to material provided in the supplemental information. We do not intend to repeat our review of the acceptable material described in the supplemental information. When the supplemental information appears as a reference in license applications, our review will ensure that the material presented applies to the specific plant involved. License amendment requests that deviate from the supplemental information will be subject to a plant specific review in accordance with applicable review standards.
In accordance with the guidance provided on the NRC website, we request that EPRI publish an accepted version of the MRP-227, Rev 1-A within three months of receipt of this email. The accepted versions shall incorporate the final SE after the title page. Once the -A version of MRP-227, Rev 1-A has been verified by the NRC staff, licensees may then reference the supplemental information.
If you have any questions or require any additional information, please feel free to contact me at (301) 415 7297 or joseph.holonich@nrc.gov.
This email and the attached SE have been placed in ADAMS and made public.
Joe Holonich, Senior Project Manager Office of Nuclear Reactor Regulation