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ENS 56673
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Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +, 10 CFR 50.72(b)(3)(iv)(A), System Actuation +, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge +, 10 CFR 50.72#b2ivB +, 10 CFR 50.72#b3ivA +  and 10 CFR 50.72#b2ivA +
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>At 0039 (EDT) on 8/10/23, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped during a reactor protection system (RPS) bus shift. All systems responding normally post-trip. There was no equipment inoperable at the time of the trip. Operations responded and stabilized the plant. Reactor water level being maintained via feedwater. Decay heat is being removed by cycling safety relief valves.</br>An actuation of high-pressure core spray, division 3 diesel generator, and reactor core isolation cooling occurred during the scram and main steam line isolation closure. The reason for the auto-start was reaching Level 2 (130 inches in the reactor pressure vessel) during the transient. The systems automatically started as designed and injected to the reactor vessel when the Level 2 signal was received.</br>The RPS actuation is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The emergency core cooling system (ECCS) injection is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). The ECCS actuation is being reported as a eight-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(A). </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
04:39:00, 10 August 2023  +
ENS id number
56,673  +
Emergency class
Non Emergency +
Entered date
04:03:00, 10 August 2023  +
Equipment trip
Reactor Trip +
Event date
04:39:00, 10 August 2023  +
Event description
The following information was provided by … The following information was provided by the licensee via email:</br>At 0039 (EDT) on 8/10/23, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped during a reactor protection system (RPS) bus shift. All systems responding normally post-trip. There was no equipment inoperable at the time of the trip. Operations responded and stabilized the plant. Reactor water level being maintained via feedwater. Decay heat is being removed by cycling safety relief valves.</br>An actuation of high-pressure core spray, division 3 diesel generator, and reactor core isolation cooling occurred during the scram and main steam line isolation closure. The reason for the auto-start was reaching Level 2 (130 inches in the reactor pressure vessel) during the transient. The systems automatically started as designed and injected to the reactor vessel when the Level 2 signal was received.</br>The RPS actuation is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The emergency core cooling system (ECCS) injection is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). The ECCS actuation is being reported as a eight-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(A). </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.  +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +, ENS 56673 +  and ENS 56673 +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 10 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>.
19:57:27, 4 January 2024  +
NRC officer
Ernest West +
Notification date
04:03:00, 10 August 2023  +
Originated by
Terry Ginn +
Reactor critical
true  +
Reactor type
GE-6 +
Region
NRC Region 3 +
Reporting criterion
10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation +, 10 CFR 50.72(b)(3)(iv)(A), System Actuation +  and 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge +
Reporting time
-0.025 d (-0.6 hours, -0.00357 weeks, -8.2188e-4 months)  +
Site
Perry +
Start date
04:39:00, 10 August 2023  +
State
Ohio +
System
Feedwater +, Reactor Protection System +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Core Spray +, Emergency Core Cooling System +, Main Steam Line +  and Safety Relief Valve +
Title
Automatic Reactor Trip  +
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/2023/20230814en.html#en56673  +
Unit
1  +
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