ENS 52801
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ENS Event | |
---|---|
13:11 Jun 11, 2017 | |
Title | Excessive Bonnet Leakage from Chemical Volume Control System Valve |
Event Description | At Indian Point Energy Center [IPEC], Unit 3 normal letdown was isolated due to a significant body/bonnet leak on the inlet valve to Reactor Coolant Filter. Shift team took action to isolate letdown and stop the leak. The Abnormal Operating Procedure (AOP) was entered, normal letdown was isolated per procedure, and excess letdown was placed in service to balance inventory at 61 percent Pressurizer Level. This was above the Technical Specification [3.4.9] level of 54.3 percent which was exceeded at 0911 [EDT], putting the unit in a 6-hour shutdown action statement. The valve body/bonnet was torqued, successfully eliminating the leakage. Pressurizer Level was restored to the normal control band and the AOP was exited at 1136. The SM [Shift Manager] estimated the leakage at 18 gallons per minute when leak was active. No EAL [Emergency Action Level] thresholds were exceeded. This occurrence is considered a safety system functional failure per 10 CFR 50.72(b)(3)(v)(A), requiring an 8-hour NRC report. Both IPEC units are stable at full power."
The licensee has notified the NRC Resident Inspector and the New York State Public Service Commission. |
Where | |
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Indian Point New York (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor | |
LER: | 05000286/LER-2017-002 |
Time - Person (Reporting Time:+1.4 h0.0583 days <br />0.00833 weeks <br />0.00192 months <br />) | |
Opened: | Clifton Gates 14:35 Jun 11, 2017 |
NRC Officer: | Jeff Rotton |
Last Updated: | Jun 11, 2017 |
52801 - NRC Website
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Unit 3 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
WEEKMONTHYEARENS 528012017-06-11T13:11:00011 June 2017 13:11:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Excessive Bonnet Leakage from Chemical Volume Control System Valve ENS 467822011-04-25T13:50:00025 April 2011 13:50:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Single Train Charging Pump Declared Inoperable ENS 463922010-11-04T05:23:0004 November 2010 05:23:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Charging Pump '23' Declared Inoperable During Surveillance Testing ENS 462222010-09-01T20:00:0001 September 2010 20:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Loss of Temperature Instrumentation ENS 454322009-10-14T19:00:00014 October 2009 19:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Safety System Functional Failure - Alternate Safe Shutdown Source Range Neutron Monitor Inoperable ENS 451522009-06-23T22:23:00023 June 2009 22:23:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Potentially Degraded Inventory Control During Shutdown ENS 442362008-05-23T07:30:00023 May 2008 07:30:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Charging Pump Declared Inoperable Due to Relief Valve Lifting Below Setpoint 2017-06-11T13:11:00 | |
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