05000354/LER-2023-001, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable: Difference between revisions
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{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 10 CFR 50.73 LR-N23-0039 June 20, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354 Subject: | {{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 10 CFR 50.73 LR-N23-0039 June 20, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354 | ||
==Subject:== | |||
Licensee Event Report 2023-001-00, Technical Specification Required Shutdown due to Declaring the Suppression Chamber and Primary Containment Inoperable In accordance with 10 CFR 50.73(a)(2)(i)(A) and 50.73(a)(2)(v)(D), PSEG Nuclear LLC submits Licensee Event Report (LER) 2023-001-00. | Licensee Event Report 2023-001-00, Technical Specification Required Shutdown due to Declaring the Suppression Chamber and Primary Containment Inoperable In accordance with 10 CFR 50.73(a)(2)(i)(A) and 50.73(a)(2)(v)(D), PSEG Nuclear LLC submits Licensee Event Report (LER) 2023-001-00. | ||
There are no regulatory commitments contained in this letter. | There are no regulatory commitments contained in this letter. | ||
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: 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO. | : 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO. | ||
052 050 CAUSE OF EVENT HCGS will supplement this LER when the RCE is complete. | 052 050 | ||
SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences because of this event. An engineering analysis determined that primary containment and the suppression chamber (torus) were capable of performing their intended safety functions. Therefore, per NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, this will not be counted as a safety system functional failure. | |||
PREVIOUS EVENTS No similar LER or corrective action occurrences were found following a review of station LERs and the corrective action program for the past three years. | ==CAUSE OF EVENT== | ||
CORRECTIVE ACTIONS HCGS identified bypass leakage through one torus-to-drywell vacuum breaker, completed repairs, satisfactorily performed SR 4.6.2.1.f, and returned to power operation on May 6, 2023. | HCGS will supplement this LER when the RCE is complete. | ||
HCGS will supplement this LER when the RCE is complete. | |||
COMMITMENTS There are no regulatory commitments in this LER. | ==SAFETY CONSEQUENCES AND IMPLICATIONS== | ||
There were no safety consequences because of this event. An engineering analysis determined that primary containment and the suppression chamber (torus) were capable of performing their intended safety functions. Therefore, per NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, this will not be counted as a safety system functional failure. | |||
PREVIOUS EVENTS No similar LER or corrective action occurrences were found following a review of station LERs and the corrective action program for the past three years. | |||
==CORRECTIVE ACTIONS== | |||
HCGS identified bypass leakage through one torus-to-drywell vacuum breaker, completed repairs, satisfactorily performed SR 4.6.2.1.f, and returned to power operation on May 6, 2023. | |||
HCGS will supplement this LER when the RCE is complete. | |||
==COMMITMENTS== | |||
There are no regulatory commitments in this LER. | |||
3 3 | 3 3 | ||
Hope Creek Generating Station 354 2023 001 00 | Hope Creek Generating Station 354 2023 001 00 | ||
Latest revision as of 17:48, 2 January 2025
| ML23173A087 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/20/2023 |
| From: | Agster T Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LR-N23-0039 LER 2023-001-00 | |
| Download: ML23173A087 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3542023001R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 10 CFR 50.73 LR-N23-0039 June 20, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354
Subject:
Licensee Event Report 2023-001-00, Technical Specification Required Shutdown due to Declaring the Suppression Chamber and Primary Containment Inoperable In accordance with 10 CFR 50.73(a)(2)(i)(A) and 50.73(a)(2)(v)(D), PSEG Nuclear LLC submits Licensee Event Report (LER) 2023-001-00.
There are no regulatory commitments contained in this letter.
Please contact Mr. Harry Balian at (856) 339 - 2173 if you have questions.
Sincerely, Thomas R. Agster Plant Manager, Hope Creek Generating Station Attachment: Licensee Event Report 2023-001-00
- Agster, Thomas R.
Digitally signed by Agster, Thomas R.
Date: 2023.06.20 20:00:41 -04'00' 0 PSEG Nuclear ILG
Page 2 LR-N23-0039 cc:
USNRC Regional Administrator í Region 1 USNRC NRR Project Manager - Hope Creek USNRC Senior Resident Inspector - Hope Creek NJ Department of Environmental Protection, Bureau of Nuclear Engineering President & Chief Nuclear Officer, PSEG Nuclear Senior Vice President, PSEG Nuclear Operations Site Vice President, Hope Creek Plant Manager, Hope Creek Vice President, PSEG Nuclear Engineering Executive Director Regulatory Affairs & Nuclear Oversight Director Site Regulatory Compliance, Regulatory Affairs Manager, Nuclear Oversight Corporate Commitment Coordinator, PSEG Nuclear, LLC Records Management (Record Type 3E.111)
Abstract
On April 30, 2023, Hope Creek Generating Station (HCGS) completed a technical specification (TS) required shutdown because limiting condition for operation (LCO) 3.6.1.1, Primary Containment Integrity, was declared inoperable. LCO 3.6.1.1 was declared inoperable because drywell-to-torus differential pressure could not be established to perform surveillance requirement (SR) 4.6.2.1.f, and LCO 3.6.2.1, SUPPRESSION CHAMBER, could not be met. HCGS demonstrated containment Operability and returned to power operation.
HCGS will supplement this licensee event report (LER) when a root cause evaluation (RCE) is complete.
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- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050
CAUSE OF EVENT
HCGS will supplement this LER when the RCE is complete.
SAFETY CONSEQUENCES AND IMPLICATIONS
There were no safety consequences because of this event. An engineering analysis determined that primary containment and the suppression chamber (torus) were capable of performing their intended safety functions. Therefore, per NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, this will not be counted as a safety system functional failure.
PREVIOUS EVENTS No similar LER or corrective action occurrences were found following a review of station LERs and the corrective action program for the past three years.
CORRECTIVE ACTIONS
HCGS identified bypass leakage through one torus-to-drywell vacuum breaker, completed repairs, satisfactorily performed SR 4.6.2.1.f, and returned to power operation on May 6, 2023.
HCGS will supplement this LER when the RCE is complete.
COMMITMENTS
There are no regulatory commitments in this LER.
3 3
Hope Creek Generating Station 354 2023 001 00
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