05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)
| ML24184C067 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/02/2024 |
| From: | Mclaughlin R Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LR-N24-0048 LER 2024-001-00 | |
| Download: ML24184C067 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
| 3542024001R00 - NRC Website | |
text
Robert D. Mclaughlin Plant Manager, Hope Creek Generating Station, PSEG Nuclear LLC PO Box236 o PSEG I NUCLEAR Hancocks Bridge, New Jersey 08038-0221 LR-N24-0048 July 2, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354 10 CFR 50.73 Subject: Licensee Event Report 2024-001-00, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)
PSEG Nuclear LLC submits licensee event report (LER) per 1 O CFR
- 50. 73(a)(2)(ii)(A).
There are no regulatory commitments contained in this letter.
Please contact Ms. Tammy Morin at (856) 339 - 2286 if you have questions.
Sincerely, Robert D. McLaughlin Plant Manager, Hope Creek Generating Station Attachment: Licensee Event Report cc:
USNRC Regional Administrator - Region 1 USN RC NRR Project Manager - Hope Creek USN RC Senior Resident Inspector - Hope Creek NJ Department of Environmental Protection, Bureau of Nuclear Engineering
Abstract
On May 3, 2024, during a refueling outage, Hope Creek Generating Station (HCGS) performed Primary Containment Integrated Leak Rate Testing (ILRT) Type A test as required by Technical Specification 4.6.1.2.
The as-found test was not completed successfully because the stabilization criteria was not met. The as-left test was completed successfully prior to plant start-up.
This event was reported to the NRC as an eight-hour, non-emergency per 10 CFR 50.72(b)(3)(ii)(A) in Event Notification 57103 on May 3, 2024. This event is reportable per 10 CFR 50.73(a)(2)(ii)(A). Page of
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor (BWR/4)
System - Primary Containment IDENTIFICATION OF OCCURRENCE Discovery Date: May 3, 2024 CONDITIONS PRIOR TO OCCURRENCE OPCON 4, Cold Shutdown. No other structures, systems, or components that could have contributed to the event were inoperable.
DESCRIPTION OF OCCURRENCE On May 2, 2024, at 10:00 am, the Primary Containment Integrated Leak Test (ILRT) commenced. At 1:08 pm, the stabilization period started. At 6:30 pm there was evidence of leakage and walkdowns were initiated to determine the location of any leaks. At 8:30 pm a leak was found at the drywell airlock hatch to primary containment flange. At 11:00 pm, in accordance with procedures, an attempt to quantify the leak was made.
On May 3, 2024, at 3:05 am, a second attempt to quantify the leak was made and at 4:11 am, it was determined that a step change in the leakage rate had invalidated the as-found test.
On May 4, 2024, at 10:00 am, the Type A as-left ILRT was completed with satisfactory results.
CAUSE OF EVENT
The cause of the event has not been determined at the time of this LER. A Root Cause Evaluation is in progress. A supplement to this LER will be submitted.
SAFETY CONSEQUENCES AND IMPLICATIONS
The event occurred when HCGS was in OPCON 4, Cold Shutdown. The test was performed in an operating mode where the safety function of the primary containment was not required, and the as-left test was performed successfully prior to entering a mode when the primary containment is required. This is reportable as a degraded condition of a principal safety barrier because the stabilization criteria was not met.
PREVIOUS EVENTS There have been no previous events at HCGS in the last three years related to Primary Containment ILRT.
CORRECTIVE ACTIONS
A satisfactory Type-A as-left ILRT was performed to verify Primary Containment integrity exists. Additional corrective actions are being determined in the Root Cause Evaluation.
COMMITMENTS
There are no regulatory commitments in this LER.
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