LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1
| ML23212A170 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/31/2023 |
| From: | Agster T Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LR-N23-0052 | |
| Download: ML23212A170 (1) | |
Text
LR-N23-0052 July 31, 2023 PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear LLC Technical Specification 4.6.2.1.f U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1.f
References:
- 1. PSEG Event Notification 56495, Technical Specification Required Shutdown.
Event Date: 4/30/2023.
- 2. PSEG Licensee Event Report 2023-001-00, Technical Specification Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable. Report Date: 6/20/2023, Accession Number: ML23173A087.
On April 30, 2023, Hope Creek Generating Station (HCGS) attempted to perform Surveillance Requirement (SR) 4.6.2.1.f but could not establish the initial test conditions (drywell-to-torus differential pressure). HCGS then declared Suppression Chamber and Primary Containment Integrity inoperable and completed a plant shutdown in accordance with Technical Specifications (TS). Event Notification 56495 (Reference 1) and Licensee Event Report 2023-001-00 (Reference 2) document the event.
Per TS Surveillance Requirement (SR) 4.6.2.1.f, if any Drywell-to-Suppression Chamber bypass leak test fails to meet the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission. An internal Technical Evaluation was performed to assess the test schedule for subsequent Drywell-to-Suppression Chamber bypass leak tests.
July 31, 2023 Page 2 LR-N23-0052 Technical Specification 4.6.2.1.f Based on the results of the Technical Evaluation, PSEG believes that it is appropriate for HCGS to continue to perform SR 4.6.2.1.f on an eighteen month interval. The inability to establish initial test conditions in the April 2023 event was directly caused by prior inadequate maintenance on the vacuum breakers without an appropriate retest. The event was not attributed to equipment degradation. Additional technical details will be provided in a forthcoming supplement to Reference 2. A review of past performances of this surveillance from 2000-2022 did not reveal any test failures or trends of concern. Prior to start-up from the May 2023 forced outage, SR 4.6.2.1.f was successfully performed to verify rework of the vacuum breakers.
Based on these factors, no degradation mechanism is present that would warrant an increased test frequency for SR 4.6.2.1.f. HCGS will perform SR 4.6.2.1.f again immediately prior to the spring 2024 refueling outage, after which the eighteen month surveillance interval will be re established.
This proposed test schedule is being submitted for your review and approval as required by Surveillance Requirement 4.6.2.1.f. If you have any questions or comments on this transmittal, please contact Bernadette Cizin at (856) 339 - 2206.
Sincerely, Thomas Agster Plant Manager, Hope Creek
July 31, 2023 Page 3 LR-N23-0052 cc:
USN RC Administrator - Region I USN RC Project Manager - Hope Creek USN RC Senior Resident Inspector - Hope Creek Technical Specification 4.6.2.1.f NJ Department of Environmental Protection, Bureau of Nuclear Engineering Corporate Tracking Coordinator