ENS 56610: Difference between revisions
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| NRC officer = Karen Cotton-Gross | | NRC officer = Karen Cotton-Gross | ||
| event date = 07/06/2023 12:32 EDT | | event date = 07/06/2023 12:32 EDT | ||
| last update date = 07/ | | last update date = 07/10/2023 | ||
| title = Unanalyzed Condition | | title = Unanalyzed Condition | ||
| event text = The following information was provided by the licensee via email: | | event text = The following information was provided by the licensee via email: | ||
On July 6, 2023, at 1232 EDT, while operating in Mode 1 at 100 percent power, the supply check valve from the number 2 steam generator to the turbine driven auxiliary feedwater pump was determined during troubleshooting that it is not able to perform its isolation function. This failure would have resulted in the blowdown of both steam generators during a main steam line break in the number 2 steam generator main steam line upstream of the main steam isolation valves until the operators could isolate the faulted steam generator. Previous evaluation has determined that this condition constituted an unanalyzed condition that could impact containment pressure. | On July 6, 2023, at 1232 EDT, while operating in Mode 1 at 100 percent power, the supply check valve from the number 2 steam generator to the turbine driven auxiliary feedwater pump was determined during troubleshooting that it is not able to perform its isolation function. This failure would have resulted in the blowdown of both steam generators during a main steam line break in the number 2 steam generator main steam line upstream of the main steam isolation valves until the operators could isolate the faulted steam generator. Previous evaluation has determined that this condition constituted an unanalyzed condition that could impact containment pressure. | ||
There was no radioactive release to the environment. The steam line from the steam generator to the turbine driven auxiliary feedwater pump was isolated by use of a motor operated valve in the discharge line of the number 2 steam generator. There was no impact to Unit 3 which remains at 100 percent power. | There was no radioactive release to the environment. The steam line from the steam generator to the turbine driven auxiliary feedwater pump was isolated by use of a motor operated valve in the discharge line of the number 2 steam generator. There was no impact to Unit 3 which remains at 100 percent power. | ||
The Senior Resident was notified. | The NRC Senior Resident Inspector was notified. | ||
This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. | This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2023/ | | URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2023/20230711en.html#en56610 | ||
}}{{unit info | }}{{unit info | ||
| Unit = 2 | | Unit = 2 | ||
Latest revision as of 06:30, 11 July 2023
| Where | |
|---|---|
Millstone  Connecticut (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+0.27 h0.0113 days <br />0.00161 weeks <br />3.69846e-4 months <br />) | |
| Opened: | Jason Paris 16:48 Jul 6, 2023 |
| NRC Officer: | Karen Cotton-Gross |
| Last Updated: | Jul 10, 2023 |
| 56610 - NRC Website
| |