L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
| ML23269A150 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/26/2023 |
| From: | Strand D Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-2023-136 | |
| Download: ML23269A150 (1) | |
Text
September 26, 2023 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTN: Document Control Desk
SUBJECT:
DOCKET NO:
St. Lucie Units 1 and 2 50-335 and 50-389 L-2023-136 10 CFR 50.90 10 CFR 50.69 Supplement to License Amendment Request to Adopt 1 O CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors"
References:
- 1. Florida Power & Light Company letter L-2022-175, Application to Adopt 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors," December 2, 2022 (ML22336A071)
- 2. Florida Power & Light Company letter L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors," September 11, 2023 (ML23255A041)
In Reference 1, Florida Power & Light Company (FPL) submitted a license amendment request to modify the licensing basis by the addition of a license condition to allow for the implementation of the provisions of Title 1 O of the Code of Federal Regulations (1 O CFR),
Part 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors," to the licenses for St. Lucie Unit 1 and Unit 2.
Reference 2 provided a response to requested information that the NRC staff determined to be necessary to complete its review.
The enclosure to this letter provides information that supplements information provided in References 1 and 2 without altering the conclusions in Reference 1 that the proposed change does not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the change.
This letter contains no new or revised regulatory commitments.
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 L-2023-136 Page 2 of 2 If you should have any questions regarding this submittal, please contact Kenneth Mack, Licensing Manager, at (561) 904-3635.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 2."°"' day of September 2023.
Sincerely, Dianne Strand General Manager Regulatory Affairs Florida Power & Light Company Enclosure cc:
USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant, Units 1 and 2 USNRC Senior Resident Inspector, St. Lucie Nuclear Plant, Units 1 and 2 Mr. John Williamson, Florida Department of Health
ENCLOSURE
LIST OF ATTACHMENTS : List of Categorization Prerequisites : Proposed License Condition : Drawing 2998-G-839 Sheet 1, St. Lucie Unit 2 Flood Control Stop Logs
- List of Categorization Prerequisites
- 1. Any FLEX equipment credited in the future will apply NRC accepted data sources and HRA methodologies as a prerequisite to implementing the 10 CFR 50.69 categorization processes.
- 2. As a prerequisite to implementing the 10 CFR 50.69 categorization processes, FPL will update failure probabilities for the portable pump modeled in its PRA and apply NRC accepted data sources.
- 3. As a prerequisite to implementing the 10 CFR 50.69 categorization processes, FPL will update the operator action for the portable pump by utilizing NRC accepted HRA methodologies and perform a FSPR of this update followed by any necessary F&O closure items by an Independent Assessment Team IAT per NEI 05-04/07-12/12-06 Appendix X: "Close-Out of Facts and Observations (F&Os)."
- 4. The key uncertainty involving Human-Induced errors in support system initiating event models has the potential to affect categorization of SSCs and the support system initiating event fault tree structure will be revised to include any applicable human failure events contributing to the support system initiating event and thereby remove this key source of uncertainty.
- 5. Since F&O findings CS-B1-01 and CS-A3-01 have not been formally closed using an NRC approved F&O closure process, F&O CS-B1 -01 along with CS-A3-01 will be closed using an NRC approved F&O Closure process as a prerequisite to implementing the 10 CFR 50.69 categorization processes.
- 6. To clarify the status of open F&Os and to implement a closure review team assessment of F&Os not formally closed, a review of open F&Os and closure of these F&Os will be implemented. FPL will generate an F&O disposition matrix with reference to the closure review that closes each F&O and references the NRC approved F&O Closure process used to close the F&O. Closure of all F&Os will be performed as a prerequisite to implementing the 10 CFR 50.69 categorization processes.
- 7. FQ-C1-01 will have a Focused Scope Peer Review of the Fire PRA followed by any necessary F&O closure items by an Independent Assessment Team per NEI 05-04/07-
12/12-06 Appendix X: "Close-Out of Facts and Observations (F&Os)," as a prerequisite to implementing the 1 0CFR 50.69 categorization processes.
- Proposed License Condition FPL proposes the addition of the following condition to the renewed operating licenses of St.
Lucie Nuclear Plant (PSL), Units 1 and 2 to document the NRC's approval of the use 10 CFR 50.69.
FPL is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using: Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, internal flooding, and internal fire; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2 and Class 3 and non-Class SSCs and their associated supports; the results of the non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009 for other external hazards except seismic; and the alternative seismic approach as described in FPL's original submittal letter dated December 2, 2022, and all its subsequent associated supplements; as specified in License Amendment No. [XXX] dated [DATE].
Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above.
FPL shall complete the numbered items listed in Attachment 1, List of Categorization Prerequisites, of FPL letter [ML Number], dated September 26, 2023, prior to implementation. All issues identified in the attachment will be addressed and any associated changes will be made, focused scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2), and any findings will be resolved and reflected in the PRA of record prior to implementation of the 10 CFR 50.69 categorization process.
- Drawing 2998-G-839 Sheet 1, St. Lucie Unit 2 Flood Control Stop Logs Please note that this drawing is not proprietary information even though the stamp immediately above the title block states, "This document is the property of Ebasco Services Incorporated. Its use is expressly restricted by the terms of the contract, dated as of 9-1-7 S between Ebasco Services Incorporated and Florida Power & Light Company." When construction was completed on St. Lucie Unit 2 such that the contract between Ebasco Se1vices Incorporated and Florida Power & Light Company was fulfilled, Ebasco Se1vices Incorporated turned over all St. Lucie Unit 2 drawings to FPL who assumed ownership of all St. Lucie Unit 2 drawings.
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