ML19149A489

Transmittal of Final Safety Evaluation for Topical Report EMF-93-177, Revision 1, Supplement 2P, Revision 1, Mechanical Design for BWR Fuel Channels: Z4B Material

ML19149A489
Person / Time
Site:	PROJ0728, 99902041
Issue date:	06/24/2019
From:	Dennis Morey NRC/NRR/DLP/PLPB
To:	Peters G Framatome
Rowley J, NRR/DLP, 415-4053
Shared Package
ML19149A479 -Pkg.	List: ML19149A486 ML19149A488 ML19149A489
References
EPID L-2018-TOP-0029 EMF-93-177
Download: ML19149A489 (3)

Text

June 24, 2019 Mr. Gary Peters, Director Licensing and Regulatory Affairs Framatome Inc.

3315 Old Forest Road Lynchburg, VA 24501

SUBJECT:

FINAL SAFETY EVALUATION FOR FRAMATOME INC. TOPICAL REPORT EMF-93-177, REVISION 1, SUPPLEMENT 2P, REVISION 1, MECHANICAL DESIGN FOR BWR FUEL CHANNELS: Z4B MATERIAL (EPID: L-2018-TOP-0029)

Dear Mr. Peters:

By letter dated July 25, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18211A307), Framatome, Inc. (Framatome) submitted Topical Report (TR) EMF-93-177, Revision 1, Supplement 2P, Revision 1, Mechanical Design for BWR

[boiling water reactor] Fuel Channels: Z4B Material, to the U.S. Nuclear Regulatory Commission (NRC) staff for review and approval. By letter dated April 23, 2019 (ADAMS Accession No. ML19101A419), an NRC draft safety evaluation (SE) regarding our approval of TR EMF-93-177, Revision 1, Supplement 2P, Revision 1, was provided for your review and comment. By letter dated May 20, 2019 (ADAMS Accession No. ML19142A094), Framatome provided comments on the draft SE. The NRC staffs disposition of the Framatome comments on the draft SE are discussed in the attachment (ADAMS Accession No. ML19149A488) to the final SE enclosed with this letter.

The NRC staff has found that TR EMF-93-177, Revision 1, Supplement 2P, Revision 1, is acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR.

Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the acceptable material described in the TR. When the TR appears as a reference in licensing action requests, our review will ensure that the material presented applies to the specific plant involved. Requests for licensing actions that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards.

G. Peters In accordance with the guidance provided on the NRC website, we request that Framatome publish approved proprietary and non-proprietary versions of TR EMF-93-177, Revision 1, Supplement 2P, Revision 1, within 3 months of receipt of this letter. The approved versions shall incorporate this letter and the enclosed final SE after the title page. Also, they must contain historical review information, including NRC requests for additional information and your responses. The approved versions shall include an -A (designating approved) following the TR identification symbol.

As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and if the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:

1. The RAIs and RAI responses can be included as an Appendix to the accepted version.

2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.

If future changes to the NRCs regulatory requirements affect the acceptability of this TR, Framatome will be expected to revise the TR appropriately or justify its continued applicability for subsequent referencing. Licensees referencing this TR would be expected to justify its continued applicability or evaluate their plant using the revised TR.

Sincerely,

/RA/

Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Project No. 728 Docket No. 99902041

Enclosure:

Final Safety Evaluation

ML19149A489 -Letter; ML19149A486 -Safety Evluation; ML19149A479 Package; ML19149A488 -Attachment *concurrence via email NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DSS/SNPB NRR/DLP/PLPB/BC NAME JRowley DHarrison RLukes DMorey DATE 06/1/19 06/11/19 06/18/19 06/24/19