Letter Sequence Draft 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
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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
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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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Text
OFFICIAL USE ONLY - PROPRIETARY INFORMATION February 28, 2019 Brian Burgos MRP Program Manager Electric Power Research Institute 3420 Hillview Avenue Palo Alto, CA 94304
SUBJECT:
DRAFT SAFETY EVALUATION FOR ELECTRIC POWER RESEARCH INSTITUTE TOPICAL REPORT MRP-227, REVISION 1, MATERIALS RELIABILITY PROGRAM: PRESSURIZED WATER REACTOR INTERNALS INSPECTION AND EVALUATIONS GUIDELINE (CAC NO.MF7223; EPID L-2016-TOP-0001)
Dear Mr. Burgos:
By letter dated December 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15358A046), the Electric Power Research Institute (EPRI) submitted for U.S. Nuclear Regulatory Commission (NRC) staff review topical report MRP-227, Revision 1, Materials Reliability Program: Pressurized Water Reactor Internals Inspection And Evaluations Guideline. Enclosed for EPRI review and comment is the NRC staff draft safety evaluation (SE) for the TR.
Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR), we have determined that the enclosed draft SE may contain proprietary information. If you believe that any information in the enclosure is proprietary, please identify such information line-by-line and define the basis pursuant to the criteria of 10 CFR 2.390. After 10 working days, the draft SE will be made publicly available, as appropriate, and an additional 10 working days are provided for you to comment on any factual errors or clarity concerns contained in the draft SE.
The final SE will be issued after making any necessary changes and will be made publicly available. The NRC staff disposition of your comments on the draft SE will be discussed in the final SE.
To facilitate the NRC staff's review of your comments, please provide a marked-up copy of the draft SE showing proposed changes and provide a summary table of the proposed changes.
NOTICE: Enclosure transmitted herewith contains SUNSI. When separated from the Enclosure, this transmittal document is decontrolled.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
B. Burgos If you have any questions, please contact the Project Manager for the review, Joseph J. Holonich at 301-415-7297 or via electronic mail at Joseph.Holonich@nrc.gov.
Sincerely,
/RA/
Dennis Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902021
Enclosure:
Draft SE
ML18275A069 (Letter); ML18275A071 (Draft SE);
ML18275A074 (Package) *concurred via email NRR-106 OFFICE NRR/DLR/PLPB* NRR/DLR/PLPB* DMLR/MPHB/BC* NRR/DLR/PLPB NAME JHolonich DHarrison DAlley DMorey DATE 01/26 /2019 02/19/2019 01/26 /2019 02/28/2019