Letter Sequence Draft Approval |
---|
|
|
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] |
|
---|
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] |
Text
OFFICIAL USE ONLY - PROPRIETARY INFORMATION January 3, 2018 Brian Burgos MRP Program Manager Electric Power Research Institute 3420 Hillview Avenue Palo Alto, CA 94304
SUBJECT:
DRAFT 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 (CAC NO. MF7223 EPID: L-2016-TOP-0001)
Dear Ms. Demma:
By letter dated January 12, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090160204), the Electric Power Research Institute (EPRI) submitted for U.S. Nuclear Regulatory Commission (NRC) staff review, TR [Topical Report]
Materials Reliability Program (MRP) Report 1016596 (MRP-227), Revision 0, Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines. By letter dated December 16, 2011, the NRC staff issued its safety evaluation (SE) on MRP-227, Revision 0. A copy of the NRC staff transmittal letter and SE can be found in ADAMS Accession No. ML11308A770.
The SEs on MRP-227 contained a number of applicant/licensee action items (A/LAIs). Two of these, A/LAI 1 and A/LAI 7, have been under staff review to determine if they can be closed on a generic basis instead of in plant-specific evaluations. Based on its review of the information submitted by EPRI, the NRC staff finds the information submitted to address A/LAI 1 and A/LA 7 on a generic-basis acceptable subject to the limitations specified in the EPRI submissions and in the NRC staff SE. Enclosed for EPRI review and comment is the NRC staff draft SE.
Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR 2.390), 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. Twenty working days are provided for EPRI to comment on any proprietary information, factual errors, or clarity concerns contained in the draft SE.
NOTICE: Enclosure transmitted herewith contains SUNSI. When separated from Enclosure, this transmittal document is decontrolled.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
OFFICIAL USE ONLY - PROPRIETARY INFORMATION B. Burgos 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.
If you have any questions, please contact the Project Manager for the review, Joseph J. Holonich at 301-415-7297 or Joseph.Holonich@nrc.gov.
Sincerely,
/RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902021
Enclosure:
Draft SE OFFICIAL USE ONLY - PROPRIETARY INFORMATION
ML16238A128 (Package); ML16238A133 (Letter/Public);
ML16238A134 (Draft SE/Non-Public); *concurrence via e-mail NRR-106 OFFICE DLP/PLPB/PM DLP/PLPB/LA* DE/DMLR/MVIB* DLP/PLPB/BC NAME JHolonich DHarrison SRuffin DMorey DATE 11/8/2017 12/14/2017 12/14/2017 1/3/2018