ENS 53643: Difference between revisions
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StriderTol (talk | contribs) Created page by program invented by StriderTol |
StriderTol (talk | contribs) Created page by program invented by StriderTol |
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| Line 9: | Line 9: | ||
| unit = 1 | | unit = 1 | ||
| utype = W-4-LP, W-4-LP | | utype = W-4-LP, W-4-LP | ||
| cfr = 10 CFR 50.72(b)( | | cfr = 10 CFR 50.72(b)(3)(iv)(A) | ||
| emergency class = Non Emergency | | emergency class = Non Emergency | ||
| notification date = 10/04/2018 07:57 | | notification date = 10/04/2018 07:57 | ||
| Line 15: | Line 15: | ||
| NRC officer = Vince Klco | | NRC officer = Vince Klco | ||
| event date = 10/04/2018 00:00 EDT | | event date = 10/04/2018 00:00 EDT | ||
| last update date = 10/ | | last update date = 10/19/2018 | ||
| title = | | title = En Revision Imported Date 10/22/2018 | ||
| event text = At 0544 EDT on October 4, 2018, with Unit 1 in Mode 2 with reactor power in the intermediate range performing low power physics testing, the reactor was manually tripped due to a rod control urgent failure alarm. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam system. | | event text = EN Revision Text: MANUAL REACTOR TRIP DURING LOW POWER PHYSICS TESTING | ||
At 0544 EDT on October 4, 2018, with Unit 1 in Mode 2 with reactor power in the intermediate range performing low power physics testing, the reactor was manually tripped due to a rod control urgent failure alarm. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam system. | |||
Unit 2 was not affected. | Unit 2 was not affected. | ||
There was no impact to the health and safety of the public or plant personnel. | There was no impact to the health and safety of the public or plant personnel. | ||
The NRC Resident Inspectors have been notified. | The NRC Resident Inspectors have been notified. | ||
All control rods inserted as expected. The cause of the rod control urgent failure is being investigated." | All control rods inserted as expected. The cause of the rod control urgent failure is being investigated. | ||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2018/ | * * * UPDATE FROM KEVIN LOWE TO DONALD NORWOOD AT 1408 EDT ON 10/19/2018 * * * | ||
This Event Notification is being updated to clarify that the reactor was not critical when this event occurred. Therefore, the reporting requirement is changed from 10 CFR 50.72(b)(2)(iv)(B) to 10 CFR 50.72 (b)(3)(iv)(A). | |||
During Dynamic Rod Worth Measurement testing, Control Bank Charlie was inserted approximately 153 steps when the urgent failure occurred (CBC positioned at 75 steps out). Following the scram, additional analysis concluded that the reactor was subcritical when the Reactor Protection System was actuated." | |||
The licensee notified the NRC Resident Inspector. | |||
Notified the R2DO (McCoy). | |||
| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2018/20181022en.html#en53643 | |||
}}{{unit info | }}{{unit info | ||
| Unit = 1 | | Unit = 1 | ||
Latest revision as of 07:01, 22 October 2018
| Where | |
|---|---|
Vogtle  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+3.95 h0.165 days <br />0.0235 weeks <br />0.00541 months <br />) | |
| Opened: | Kevin Lowe 07:57 Oct 4, 2018 |
| NRC Officer: | Vince Klco |
| Last Updated: | Oct 19, 2018 |
| 53643 - NRC Website
| |