ML24215A171

LLC, Response to SDAA Audit Question Number A-16.3.4-1

ML24215A171
Person / Time
Site:	05200050
Issue date:	08/02/2024
From:	NuScale
To:	Office of Nuclear Reactor Regulation
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Download: ML24215A171 (1)

Text

Response to SDAA Audit Question Question Number: A-16.3.4-1 Receipt Date: 07/17/2023 Question:

The References section of GTS Bases Subsection B 3.4.5, RCS Operational LEAKAGE, includes a reference to Revision 4 of the Electric Power Research Institute (EPRI) Pressurized Water Reactor Primary-to-Secondary Leak Guidelines. The NRC staff notes that Revision 5 of this EPRI guidance document was issued in December 2020. Similarly, the References section of GTS Bases Subsection B 3.4.9, SG Tube Integrity, includes a reference to Revision 4 of the EPRI Steam Generator Examination Guidelines. The NRC staff notes that Revision 8 of this EPRI guidance document was issued in June 2016.

The revision number in each of these references is bracketed (i.e., [4]), which indicates that a COL applicant referencing the US460 approved standard design should provide the number of its desired revision. However, referencing the current revision of each EPRI guideline document in GTS Bases would provide the most up-to-date information available.

Please explain the reason for using Revision 4 for these guideline documents rather than Revision 5 and Revision 8, respectively.

Response

The bracketed reference to Revision 4 of the EPRI Pressurized Water Reactor Primary-to-Secondary Leak Guidelines reflects the latest revision of that document that NuScale is authorized to use.

NuScale revises Reference 7 of Technical Specification Bases B 3.4.9 to bracketed Revision 7.

Revision 7 is the latest version of the EPRI Pressurized Water Reactor Steam Generator Examination Guidelines that NuScale is authorized to use.

Markups of the affected changes, as described in the response, are provided below:

NuScale Nonproprietary NuScale Nonproprietary

SG Tube Integrity B 3.4.9 NuScale US460 B 3.4.9-7 Draft Revision 1 BASES SURVEILLANCE REQUIREMENTS (continued)

The Frequency of prior to entering MODE 3 following a SG inspection ensures that the Surveillance has been completedis complete and all tubes meeting the plugging criteria are plugged prior to subjecting the SG tubes to significant primary to secondary pressure differential.

REFERENCES

1. NEI 97-06, Rev. [3].

2.

10 CFR 50, Appendix A, GDC 19.

3.

FSAR, Section 3.1.

4.

10 CFR 50.34a.

5.

ASME, Boiler and Pressure Vessel Code,Section III, Subsection NB,

[2017 edition].

6.

Draft Regulatory Guide 1.121, August 1976.

7.

EPRI, Pressurized Water Reactor Steam Generator Examination Guidelines, Rev. [74].