1 for St. Lucie Unit 1, Regarding Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load
Person / Time
ML19274B733
Site:	Saint Lucie
Issue date:	10/01/2019
From:	Deboer D Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2019-181 LER 2019-001-1
Download: ML19274B733 (4)
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LER-2019-001, 1 for St. Lucie Unit 1, Regarding Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load

Event date:
Report date:
3352019001R01 - NRC Website
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Licensee Event Report

Saint Lucie

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		Reporting criterion
05000335/LER-2019-001-01, 1 for St. Lucie Unit 1, Regarding Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load	1 for St. Lucie Unit 1, Regarding Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load
05000335/LER-2019-001, Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load	Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000335/LER-2019-002, Reactor Coolant Pump Motor Ground Results in Reactor Coolant Pump Trip and Subsequent Automatic Reactor Trip	Reactor Coolant Pump Motor Ground Results in Reactor Coolant Pump Trip and Subsequent Automatic Reactor Trip	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A)
05000335/LER-2019-003, Inoperability of Emergency Diesel Generator Due to Cracked Crankshaft	Inoperability of Emergency Diesel Generator Due to Cracked Crankshaft	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

05000335/LER-2019-001-01, 1 for St. Lucie Unit 1, Regarding Automatic Reactor Trip Caused by Main Generator Ground Resulting in Generator Lockout/Loss of Load

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