Letter Sequence Approval |
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MONTHYEARML16238A1332018-01-0303 January 2018
Letter on Draft SE for MRP-227 Action Items 1 and 7
Project stage: Draft Approval
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
Project stage: Approval
ML18142A2292018-04-24024 April 2018, 27 April 2018, 17 May 2018
Electric Power Research Institute Transmittal of Supplemental Information Regarding Technical Report MRP-227, Revision 7, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines.
Project stage: Request
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)
Project stage: RAI
ML18275A0692019-02-28028 February 2019
MRP-227 Rev 1 Draft SE Transmittal Letter
Project stage: Draft Approval
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
Project stage: Approval
2018-04-24
[Table View] |
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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
[Table view]
Category:Safety Evaluation
MONTHYEARML19081A0012019-04-25025 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
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
2019-04-25
[Table view] |
Text
/RA/
Code of Federal Regulation
Additional Guidance Used or Referenced in Subsequent License Renewal Applications Aging Management of Pressurized Water Reactor Vessel Internals (Applicable to Subsequent License Renewal Periods Only),"
3.1.3.1 Babcock and Wilcox Primary Components - Table 4-1
3.1.3.2 B&W expansion components
3.1.3.3 B&W Plants Examination and Acceptance Criteria
3.1.3.4 Combustion Engineering Primary Components
CE Expansion Components
3.1.3.6 CE Plants Examination and Acceptance Criteria 3.1.3.7 Westinghouse Primary Components
3.1.3.8 Westinghouse Expansion Components 3.1.3.9 Westinghouse/CE Primary Components
3.1.3.10 CE & Westinghouse Existing Programs Components
Projections Projections
Projections Projections