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ENS 56685
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Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release +, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown +, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded +, 10 CFR 50.72#b2i +, 10 CFR 50.72#b2xi +  and 10 CFR 50.72#b3iiA +
Current power
0  +
Current reactor mode
Hot Shutdown +
Description
The following information was provided by … The following information was provided by the licensee via email:</br>On 8/20/2023 at 1600 EDT, during plant walkdowns in the drywell while in mode 3 to identify a cause of increasing unidentified leakage rate, reactor coolant system pressure boundary leakage (approximately 2 gpm) was identified on the reactor recirculation sample line between the reactor recirculation sample line inboard isolation valve (B3100F019) and where the sample line taps off the B reactor recirculation jet pump riser. This requires entry into technical specification 3.4.4 condition C, identification of pressure boundary leakage with a required action to be in mode 3 in 12 hours and mode 4 in 36 hours. At 1630 EDT, a technical specification required shutdown to mode 4, cold shutdown, was initiated. </br>A press release by DTE is anticipated. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i), a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(xi), and an eight-hour, non-emergency notification 10 CFR 50.72(b)(3)(ii)(A) for the degraded condition of the pressure boundary. </br>Investigation into the cause of the reactor coolant system pressure boundary leakage is still ongoing. </br>There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified. NRC resident inspector has been notified.  +
Discovered date
20:00:00, 20 August 2023  +
ENS id number
56,685  +
Emergency class
Non Emergency +
Entered date
18:30:00, 20 August 2023  +
Event date
20:00:00, 20 August 2023  +
Event description
The following information was provided by … The following information was provided by the licensee via email:</br>On 8/20/2023 at 1600 EDT, during plant walkdowns in the drywell while in mode 3 to identify a cause of increasing unidentified leakage rate, reactor coolant system pressure boundary leakage (approximately 2 gpm) was identified on the reactor recirculation sample line between the reactor recirculation sample line inboard isolation valve (B3100F019) and where the sample line taps off the B reactor recirculation jet pump riser. This requires entry into technical specification 3.4.4 condition C, identification of pressure boundary leakage with a required action to be in mode 3 in 12 hours and mode 4 in 36 hours. At 1630 EDT, a technical specification required shutdown to mode 4, cold shutdown, was initiated. </br>A press release by DTE is anticipated. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i), a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(xi), and an eight-hour, non-emergency notification 10 CFR 50.72(b)(3)(ii)(A) for the degraded condition of the pressure boundary. </br>Investigation into the cause of the reactor coolant system pressure boundary leakage is still ongoing. </br>There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified. NRC resident inspector has been notified.  +
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ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +, ENS 56685 +  and ENS 56685 +
Hours
1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +
Initial power
0  +
Initial reactor mode
Hot Shutdown +
LER
05000341/LER-2023-003, Reactor Pressure Boundary Leakage at Socket Weld on Reactor Recirculation Sample Line Caused by Fatigue Failure +  and Reactor Pressure Boundary Leakage at Socket Weld on Reactor Recirculation Sample Line Caused by Fatigue Failure +
Last update date
00:00:00, 20 August 2023  +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
19:57:23, 4 January 2024  +
NRC officer
Dan Livermore +
Notification date
18:30:00, 20 August 2023  +
Originated by
Richard Beck +
Reactor critical
false  +
Reactor scram
false  +
Reactor type
GE-4 +
Region
NRC Region 3 +
Reporting criterion
10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release +, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown +  and 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded +
Reporting time
-0.0625 d (-1.5 hours, -0.00893 weeks, -0.00205 months)  +
Site
Fermi +
Start date
20:00:00, 20 August 2023  +
State
Michigan +
System
Reactor Coolant System +
TS
TS-3.4.4 +
Title
Technical Specification Required Shutdown  +
Topic
Pressure Boundary Leakage +  and Unidentified leakage +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2023/20230822en.html#en56685  +
Unit
2  +
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