ML24144A225
| ML24144A225 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 05/28/2024 |
| From: | Gerond George Licensing Processes Branch |
| To: | Zozula C Westinghouse |
| References | |
| EPID L-2023-TOP-0054, WCAP-18904-P, Rev 0, WCAP-18904-NP, Rev 0 | |
| Download: ML24144A225 (1) | |
Text
May 28, 2024 Camille Zozula Manager, Infrastructure & Facilities Licensing Westinghouse Electric Company 1000 Westinghouse Drive, Building 1 Cranberry Township PA 16066
SUBJECT:
REGULATORY AUDIT PLAN FOR THE U.S. NUCLEAR REGULATORY COMMISSION REGULATORY AUDIT ON JUNE 10-14, 2024, FOR THE REVIEW OF WESTINGHOUSE ELECTRIC COMPANY TOPICAL REPORT WCAP-18904-P/NP, REVISION 0, CRITICAL POWER EXPERIMENTS AND D6 CPR CORRELATION FOR TRITON11 FUEL (EPID L-2023-TOP-0054)
Dear Camille Zozula:
By the letter dated November 3, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23307A183), Westinghouse Electric Company (Westinghouse) submitted Topical Report (TR) WCAP-18904-P/NP, Revision 0, Critical Power Experiments and D6 CPR Correlation for TRITON11 Fuel (ADAMS Package Accession No. ML23180A303), to the U.S. Nuclear Regulatory Commission (NRC) for review and approval.
The NRC staff technical review of this TR is ongoing. The NRC staff determined that a regulatory audit is needed to facilitate the review. The NRC staff will perform a hybrid (in-person and virtual) regulatory closed audit June 10 through 14, 2024. Enclosed for your information is the audit plan the NRC staff will follow during the audit. Nathaniel Mackereth, Westinghouse, confirmed via email dated May 23, 2024, that the enclosed audit plan does not contain any proprietary information.
If you have any questions, please contact Ekaterina Lenning via phone at 301-415-3151 or via email at Ekaterina.Lenning@nrc.gov.
Sincerely,
/RA/
Gerond A. George, Chief Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 99902038
Enclosure:
Audit Plan
Enclosure U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION AUDIT PLAN FOR WESTINGHOUSE ELECTRIC COMPANY TOPICAL REPORT WCAP-18904-P/NP, REVISION 0, CRITICAL POWER EXPERIMENTS AND D6 CPR CORRELATION FOR TRITON11 FUEL DOCKET NO. 99902038 EPID L-2023-TOP-0054
1.0 BACKGROUND
By letter dated November 3, 2023 (Ref. 1), Westinghouse Electric Company (Westinghouse) submitted to the U.S. Nuclear Regulatory Commission (NRC) a request for review and approval of Topical Report (TR) WCAP-18904-P/NP, Revision 0, Critical Power Experiments and D6 CPR Correlation for TRITON11 Fuel (Ref. 2). This TR describes the critical power correlation for TRITON11 fuel. The proposed TR would allow Westinghouse to use the D6 critical power ratio (CPR) correlation on TRITON11 fuel. The NRC staff has proposed to conduct a joint regulatory audit at this point in the review process to increase efficiency in the review and the development of the staffs safety evaluation. The scope of this audit will be ensuring understanding of the material presented within the TR and discussing draft open items.
2.0 REGULATORY AUDIT BASES The regulations at Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A provide general design criteria (GDC) for nuclear power reactors. GDC 10 requires:
The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits (SAFDLs) are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
The regulatory guidance provided in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (SRP), Section 4.4, Thermal Hydraulic Design, provides one method commonly used to demonstrate adherence to GDC 10. SRP 4.4 defines the CPR as the SAFDL and states:
The limiting (minimum) value of DNBR (departure from nucleate boiling ratio),
CHFR (critical heat flux ratio), or CPR correlations is to be established such that at least 99.9 percent of the fuel rods in the core will not experience a DNB (departure from nucleate boiling) or boiling transition during normal operation or AOOs (anticipated operational occurrence).
In summary, 10 CFR Part 50, Appendix A, GDC 10 requires that SAFDLs are used to protect the fuel, and one SAFDL commonly used in boiling water reactors is CPR which demonstrates that 99.9 percent of the fuel rods in the core will not experience a dryout during normal operation or AOOs.
The regulatory audit will be held in accordance with the NRC procedures as described in LIC-111, Regulatory Audits.
3.0 REGULATORY AUDIT SCOPE The NRC staff will conduct a five-day hybrid (in-person and virtual) audit. This five-day audit will include technical discussion pertaining to potential request for additional information questions as well as comprehension questions on the TR itself.
4.0 INFORMATION NEEDS The NRC staff would like Westinghouse to make available the appropriate engineer(s) with the knowledge of WCAP-18904-P/NP, Revision 0, to address any comprehension questions by the NRC staff as well as any appropriate references.
5.0 TEAM AND REVIEW ASSIGNMENTS Kevin Heller, DSS/SFNB - Lead technical reviewer for WCAP-18904-P (Audit team leader)
Joshua Kaizer, DSS/SFNB - Technical review support for WCAP-18904-P Jack Vande Polder, DSS/SFNB - Technical reviewer Kate Lenning, DORL/LLPB - Project Manager 6.0 LOGISTICS Audit Dates: Monday, June 10, 2024, through Friday, June 14, 2024 Time: 8:30 am - 4:30 pm Eastern Standard Time The regulatory audit will be held at Westinghouses Cranberry, PA, facility, and some NRC staff may participate virtually as needed. Westinghouse should provide a conference room for discussions.
7.0 DELIVERABLES A regulatory audit summary will be provided within 90 days of the completion of the audit.
8.0 REFERENCES
- 1. Letter from Zachary S. Harper (Westinghouse) to U.S. NRC, Submittal of Westinghouse Topical Report WCAP-18904-P, Revision 0, Critical Power Experiments and D6 CPR Correlation for TRITON11 Fuel, LTR-NRC-23-30 dated November 3, 2023 (ADAMS Accession No. ML23307A183).
- 2. WCAP-18904-P/NP, Revision 0, Critical Power Experiments and D6 CPR Correlation for TRITON11 Fuel, dated November 2023 (ADAMS Accession Nos.
ML23307A184/ML23307A185 (Non-Publicly Available/Publicly Available).
- 3. NRC, NUREG-0800, Section 4.4, Thermal and Hydraulic Design, Revision 2 dated March 2007 (ADAMS Accession No. ML070550060).
ML24144A225, Cover letter with Enclosed Audit Plan OFFICE NRR/DORL/LLPB/PM NRR/DORL/LLPB/LA NRR/DSS/SFNB/BC NRR/DORL/LLPB/BC NAME ELenning DHarrison SKrepel GGeorge DATE 5/23/2024 5/24/2024 5/28/2024 5/28/2024