Letter Sequence Draft Approval |
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MONTHYEARML23045A2642023-02-24024 February 2023 E-Mail - NRC Withholding Determination Form 897 for the Slides for Closed Meeting with Electric Power Research Institute on BWRVIP-100, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shroud Project stage: Meeting ML23045A2652023-02-24024 February 2023 NRC Withholding Determination Form 897 for the Slides for Closed Meeting with Electric Power Research Institute on BWRVIP-100, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shroud (EPID Project stage: Meeting ML23214A0532023-09-14014 September 2023 E-mail - NRC Completion Determination Form 898 and Proprietary Determination Form 898 for BWRVIP-100, Revision 2, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel Project stage: Other ML23214A0692023-09-14014 September 2023 BWRVIP-100, Rev 2, Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds - NRC 898,Topical Report Completeness Determination Project stage: Other ML23214A0722023-09-14014 September 2023 BWRVIP-100, Rev 2, Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds - NRC 897, Topical Report Withholding Determination Project stage: Other ML23011A3422023-10-30030 October 2023 February 27, 2023, Meeting Summary: Pre-application Meeting for Submittal of a Revision to BWRVIP-100, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (EPID L-2023-TOP-0018) - Memo Project stage: Meeting ML23060A0972023-10-30030 October 2023 February 27, 2023, Meeting Summary: Pre-application Meeting for Submittal of a Revision to BWRVIP-100, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (EPID L-2023-TOP-0018) - Enclosure 3 - at Project stage: Meeting ML24036A0052024-02-12012 February 2024 E-Mail - Final Request for Additional Information - BWRVIP-100, Revision 2, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for Boiling Water Reactor (BWR) Internal Components Project stage: RAI ML24036A0072024-02-12012 February 2024 Redacted - Enclosure 2 - Final Request for Additional Information - BWRVIP-100, Revision 2, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for Boiling Water Reactor (BWR) Internal Components (EPID L-2023-NTR-0005 Project stage: RAI ML24219A0532024-09-12012 September 2024 Summary of August 2024 Meetings Responses to RAIs for Technical Report BWRVIP 100, Rev 2: Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internals Components Project stage: RAI ML24219A0802024-09-12012 September 2024 Attendees List for August 2024 Meetings Responses to RAIs for Technical Report BWRVIP 100, Rev 2: Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internals Components Project stage: RAI ML24219A0762024-09-12012 September 2024 August 2024 Summary of Meetings Responses to RAIs for Technical Report BWRVIP 100, Rev 2: Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internals Components Project stage: RAI ML24255A0022024-09-23023 September 2024 Change in Estimated Review Schedule for BWRVIP-100, Revision 2, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components Project stage: Other ML25023A0922025-03-21021 March 2025 E-mail - Draft Safety Evaluation Associated with EPRI Technical Report BWRVIP-100, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components, Revision 2 Project stage: Draft Approval 2024-02-12
[Table View] |
E-mail - Draft Safety Evaluation Associated with EPRI Technical Report BWRVIP-100, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components, Revision 2| ML25023A092 |
| Person / Time |
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| Site: |
99902016 |
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| Issue date: |
03/21/2025 |
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| From: |
Lois James Licensing Processes Branch |
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| To: |
Bonifanti M, Palm N Electric Power Research Institute |
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| Shared Package |
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| ML25023A090 |
List: |
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| References |
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| BWRVIP-100, BWRVIP-100, Rev 2, BWRVIP-100, Revision 2, EPID L-2023-TOP-0018 (pre-fee), EPID L-2023-NTR-0005 (post-fee) |
| Download: ML25023A092 (1) |
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Text
1 Lois James From:
Lois James Sent:
Friday, March 21, 2025 8:24 AM To:
martin.bonifanti@constellation.com; npalm@epri.com Cc:
RidsNrrOd Resource; RidsNrrDnrl Resource; RidsNrrLADHarrison Resource; RidsNrrDorl Resource; RidsNrrDorlLlpb Resource; RidsACRS_MailCTR Resource; Lois James; Jennie Rankin; Angie Buford; Scott Krepel; David Rudland; Michael Benson; John Tsao; Steven Levitus; Joseph Messina; Christopher Brown; wmcgruder@epri.com; npalm@epri.com; bcarter@epri.com
Subject:
Draft Safety Evaluation Associated with EPRI Technical Report BWRVIP-100, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components, Revision 2 (EPID L-2023-NTR-0005)
Martin Bonifanti, Constellation, BWRVIP Chairman Nathan Palm, EPRI, BWRVIP Program Manager Electric Power Research Institute 1300 West W.T. Harris Blvd Charlotte, NC 28262-8550
Dear Martin Bonifanti and Nathan Palm:
By letter dated July 11, 2023 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML23198A333), Electric Power Research Institute (EPRI) submitted BWRVIP-100, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Internal Components, Revision 2, to the U.S. Nuclear Regulatory Commission (NRC) for review and approval. Revision 2 of BWRVIP-100 incorporates newly acquired test data from harvested reactor internals materials which may indicate a potential non-conservatism in BWRVIP-100, Revision 1-A, and reassess the relationship between fracture toughness and fluence. The NRC staff reviewed and accepted the technical report on September 14, 2023 (ADAMS Accession No. ML23214A047).
A copy of the draft safety evaluation (SE) has been placed in the box.com folder. Nathan Palm and Wynter McGruder has been given access to the folder. The draft SE is being provided for a proprietary information review. If EPRI provides comments on other areas, the NRC staff will exercise its discretion on whether to address those comments.
Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR), we have determined that the draft SE may contain proprietary information. If you believe that any information in the draft SE is proprietary, please identify such information line-by-line and define the basis pursuant to the criteria of 10 CFR 2.390. Use double brackets and yellow highlight to identify any
(( proprietary information )). Your response is due back to the NRC no later than 90 days from the date of this email.
Your response must be via a letter from an authorized individual. In addition, please provide an electronic redline/strikeout Word version of the SE either via email or the box.com folder. It helps expedite the NRC staff response to comments if EPRI provides in the formal transmittal and in a separate Word file, a table with the following columns: Comment No., Page No., and Line No.,
Comment Type (if comments other than proprietary information are provided (i.e., clarity, accuracy)),
ML25023A090 (nonpublic - pkg); ML25023A092 (public - email);
ML25023A096 (nonpublic - draft SE)
^via eConcurrence *via email NRR-106 OFFICE DORL/LLPB/PM DORL/LLPB/LA DNRL/NVIB/BC DSS/SFNB/BC NAME LJames^
DHarrison^
ABuford^
SKrepel*
DATE 02/04/2025 03/04/2025 03/06/2025 02/03/2025 OFFICE OGC (NLO)
DORL/LLPB/BC DORL/LLPB/PM NAME MCarpentier JRankin (A)
LJames DATE 03/20/2025 03/21/2025 03/21/2025