ML24088A204
| ML24088A204 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/28/2024 |
| From: | David Gudger Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML24088A204 (1) | |
Text
200 Exelon Way Kennett Square, PA 19348 www.constellation.com 10 CFR 50.55a March 28, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 R. E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244
Subject:
Response to NRC Request for Additional Information Regarding Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump References
- 1. Letter from D. Gudger (Constellation Energy Generation, LLC (CEG)) to the U.S. Nuclear Regulatory Commission, R. E. Ginna Nuclear Power Plant - Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump, Dated January 26, 2024 (ADAMS Accession No ML24026A011)
- 2. Electronic mail from V. Sreenivas (U.S. Nuclear Regulatory Commission) to M. Henry (Constellation Energy Generation, LLC (CEG)), Request for Additional Information Regarding Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump dated March 13, 2024 (ADAMS Accession No. ML24073A360)
By letter dated January 26, 2024 (Reference 1), Constellation Energy Generation, LLC (CEG) requested Nuclear Regulatory Commission (NRC) approval of a proposed alternative for R.E.
Ginna Nuclear Power Plant (Ginna). Specifically, the proposed alternative is associated with the performance of the B Auxiliary Feedwater Pump Inservice Testing.
By electronic mail dated March 13, 2024 (Reference 2), the U.S. Nuclear Regulatory Commission (NRC) identified that additional information is necessary to complete the review. The attachment to this letter contains the NRC's request for additional information immediately followed by CEGs response.
This letter and its attachment contain no regulatory commitments.
Response to RAI Regarding Relief Request associated with Inservice Testing of B Auxiliary Feedwater Pump March 28, 2024 Page 2 Should you have any questions concerning this supplement, please contact Mr. Michael Henry at Michael.Henry@constellation.com or at (267) 533-5382.
Respectfully, David T. Gudger Sr. Manager - Licensing Constellation Energy Generation, LLC
Attachment:
Request for Additional Information and CEG Response cc:
USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, R.E. Ginna Nuclear Power Plant USNRC Project Manager, NRR - R.E. Ginna Nuclear Power Plant
ATTACHMENT Request for Additional Information and CEG Response R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244 RAI No. 1 The licensee is requested to indicate whether the Condensate Heater 4B Outlet Check Valve is within the scope of the IST Program at Ginna, and to discuss the evaluation of the check valve failure and whether any changes to IST Program activities related to check valves were necessary based on the extent of condition review of the check valve failure.
CEG RESPONSE:
The Condensate Heater 4B Outlet Check Valve (3968) is not in the IST program as it does not meet the scoping criteria of the ASME OM Code. The condensate system is not safety related. This valve does not meet any of the three scoping requirements in ASME OM (2012 ed.) section ISTA-1100:
(a) pumps and valves that are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident (b) pressure relief devices that protect systems or portions of systems that perform one or more of the three functions identified in subpara. ISTA-1100(a)
(c) dynamic restraints (snubbers) used in systems that perform one or more of the three functions identified in subpara. ISTA-1100(a), or to ensure the integrity of the reactor coolant pressure boundary.
The immediate extent of condition included the sister component, Condensate Heater 4A Outlet Check Valve (3969) which is also not within the IST Program. The 3968 valve is a 12-inch Crane Swing Check Valve in continuous service (i.e., open). There are no valves within the IST program that are of the same size, make, model and service conditions that would warrant changes to IST Program activities based on extent of condition. Further analysis will be performed when the 3968 valve internals are inspected and repaired during the 2024 refueling outage. Inspection and repair actions are being tracked in the Corrective Action Program.