ENS 53646: Difference between revisions
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| emergency class = Non Emergency | | emergency class = Non Emergency | ||
| notification date = 10/05/2018 09:52 | | notification date = 10/05/2018 09:52 | ||
| retracted = Yes | |||
| notification by = Terrell Higgins | | notification by = Terrell Higgins | ||
| NRC officer = Vince Klco | | NRC officer = Vince Klco | ||
| event date = 10/05/2018 00:00 CDT | | event date = 10/05/2018 00:00 CDT | ||
| last update date = 10/ | | last update date = 10/24/2018 | ||
| title = | | title = En Revision Imported Date 10/25/2018 | ||
| event text = At 0520 (CDT), on October 05, 2018, it was discovered that a Primary Containment local leak rate test performed on Main Steam Isolation Valves (MSIV) exceeded its acceptance criteria. | | event text = EN Revision Text: MAIN STEAM ISOLATION VALVES EXCEEDED PRIMARY CONTAINMENT LOCAL LEAK RATE ACCEPTANCE CRITERIA | ||
At 0520 (CDT), on October 05, 2018, it was discovered that a Primary Containment local leak rate test performed on Main Steam Isolation Valves (MSIV) exceeded its acceptance criteria. | |||
During Mode 1, 2, and 3, Surveillance Requirement 3.6.1.3.10 requires MSIV leakage for a single MSIV line to be less than or equal to 106 standard cubic feet per hour (scfh) when tested at 29 psig and Surveillance Requirement 3.6.1.3.12 requires the combined leakage rate for all MSIV leakage paths to be less than or equal to 212 scfh when tested at 29 psig. | During Mode 1, 2, and 3, Surveillance Requirement 3.6.1.3.10 requires MSIV leakage for a single MSIV line to be less than or equal to 106 standard cubic feet per hour (scfh) when tested at 29 psig and Surveillance Requirement 3.6.1.3.12 requires the combined leakage rate for all MSIV leakage paths to be less than or equal to 212 scfh when tested at 29 psig. | ||
As-found for the 'C' MSIV line leakage results were unquantifiable and gave a [minimum] path value greeter than 160 scfh. This leakage rate lead to Surveillance Requirement 3.6.1.3.10 and 3.6.1.3.12 limits to be exceeded. This event is being reported as a condition of the nuclear power plant, including its principal safety barriers, being seriously degraded per 10 CFR 50.72(b)(3)(ii)(A) since the Primary Containment Isolation Valves leakage limits for MSIVs were exceeded. | As-found for the 'C' MSIV line leakage results were unquantifiable and gave a [minimum] path value greeter than 160 scfh. This leakage rate lead to Surveillance Requirement 3.6.1.3.10 and 3.6.1.3.12 limits to be exceeded. This event is being reported as a condition of the nuclear power plant, including its principal safety barriers, being seriously degraded per 10 CFR 50.72(b)(3)(ii)(A) since the Primary Containment Isolation Valves leakage limits for MSIVs were exceeded. | ||
The NRC Resident Inspector has been notified. | The NRC Resident Inspector has been notified. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2018/ | * * * RETRACTION AT 2320 EDT ON 10/24/2018 FROM THOMAS FORLAND TO MARK ABRAMOVITZ * * * | ||
CNS [Cooper Nuclear Station] is retracting the 8-hour non-emergency notification made on October 5, 2018 at 0520 CDT (EN# 53646). Subsequent evaluation concluded that overall as-found 'C' MSIV leakage rate was not at a level that exceeded the surveillance requirement 3.6.1.3.10 and 3.6.1.3.12 limits and thus the Primary Containment Isolation Valve leakage rate limits for the MSIVs were not exceeded. | |||
The NRC Senior Resident Inspector has been notified. | |||
Notified the R4DO (Drake). | |||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2018/20181025en.html#en53646 | |||
}}{{unit info | }}{{unit info | ||
| Unit = 1 | | Unit = 1 |
Latest revision as of 07:30, 25 October 2018
Where | |
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Cooper ![]() Nebraska (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+4.87 h0.203 days <br />0.029 weeks <br />0.00667 months <br />) | |
Opened: | Terrell Higgins 09:52 Oct 5, 2018 |
NRC Officer: | Vince Klco |
Last Updated: | Oct 24, 2018 |
53646 - NRC Website
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