ENS 51809
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ENS Event | |
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01:54 Mar 21, 2016 | |
Title | Technical Specification (Ts) Required Shutdown Due To Pressure Boundary Leakage |
Event Description | During a planned Unit 1 shutdown for a refueling outage, a 0.5 gpm 'pressure boundary leak' was identified on a 1 inch pipe connected to the '1A' RHR-Shutdown Cooling return line by the drywell leak inspection team during a drywell inspection at approximately 15% power. The leak exceeded the TS 3.4.3.2 'Operational Leakage' LCO of no pressure boundary leakage. TS action 'a' was entered which requires to be in at least Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Cold Shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Therefore, the event is reportable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 10CFR50.72(b)(2)(i) due to the initiation of a plant shutdown required by the plant's TS.
The event is also reportable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per 10CFR50.72(b)(3)(ii) due to an event that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. TS 1.28 defines Pressure Boundary Leakage as leakage through a nonisolable fault in a reactor coolant system component body, pipe wall or vessel wall; therefore, the leak is a 'pressure boundary leak' as defined in TS. The licensee notified the NRC resident Inspector. |
Where | |
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Limerick Pennsylvania (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
LER: | 05000352/LER-2016-003 |
Time - Person (Reporting Time:+-2.05 h-0.0854 days <br />-0.0122 weeks <br />-0.00281 months <br />) | |
Opened: | John Harkins 23:51 Mar 20, 2016 |
NRC Officer: | Vince Klco |
Last Updated: | Mar 21, 2016 |
51809 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (15 %) |
After | Power Operation (15 %) |
Limerick with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 527382017-05-08T13:25:0008 May 2017 13:25:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Through-Wall Leakage Identified on Reactor Coolant System Pressure Boundary During Testing ENS 518092016-03-21T01:54:00021 March 2016 01:54:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification (Ts) Required Shutdown Due to Pressure Boundary Leakage ENS 500072014-04-08T10:18:0008 April 2014 10:18:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shutdown Action Initiated Because Hpci and Rcic Were Simultaneously Inoperable ENS 483722012-10-03T20:00:0003 October 2012 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Fire Safe Shutdown Analysis Failed to Identify Unprotected Cable ENS 483342012-09-21T20:00:00021 September 2012 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Isolation Valves Could Fail to Fully Close 2017-05-08T13:25:00 | |
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