ENS 52581
ENS Event | |
|---|---|
15:00 Feb 28, 2017 | |
| Title | Technical Specification Shutdown Due to Reactor Coolant System Pressure Boundary Leakage |
| Event Description | On February 28, 2017 at 0930 [EST], a containment visual inspection was performed to identify the source of elevated RCS [Reactor Coolant System] leakage. A leak was identified between 13RC6 and 13SS661, 13 RCS hot leg sample isolation valves at 1000 [EST]. These valves are manual isolation valves in the reactor coolant hot leg sample line. Leak isolation could not be initially verified and is considered RCS pressure boundary leakage. Salem Unit 1 entered Technical Specification 3.4.6.2a, RCS operational leakage, for the existence of pressure boundary leakage.
This event is being reported under the requirements of 10 CFR 50.72(b)(2)(i) for 'The initiation of a plant shutdown required by Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) or 'Any event of condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded.' The unit was placed in mode 3 at 1554 [EST] on 02/28/2017. This condition has no impact on public health and safety. Per Technical Specifications, the unit is proceeding to mode 5. The leak rate at the time of shutdown was 0.33 gpm. This event has no effect on Unit 2. The licensee has notified the NRC Resident Inspector. The licensee will be notifying the Lower Alloways Creek Township, the State of New Jersey and the State of Delaware.
The purpose of this notification is to retract event report number 52581 made on 2/28/2017 at 1624 (EST). Previously, PSEG notified the NRC that Salem Unit 1 initiated a shutdown required by Technical Specifications (TS) for Reactor Coolant System (RCS) Pressure Boundary Leakage. Subsequent to the initial report, PSEG has determined that the leak occurred in tubing downstream of the design specification break between Safety Related, Nuclear Class 1, Seismic Class1 and Non-Safety-Related, Nuclear Class 2, Seismic Class 2. Therefore, the observed leakage is not RCS pressure boundary leakage as defined in the Salem Unit 1 Technical Specifications and in the tubing design classification specification. At the time of the event, during initial entry into the containment, the volume of steam present and the height of the break above the floor made it difficult to ascertain the location of the steam source with certainty. The initial judgment of RCS Pressure Boundary Leakage was conservative under these circumstances. The plant was taken offline to minimize radiation exposure when personnel operated the isolation valves. Following the shutdown, the leak was isolated. Based on an observed reduction in RCS leak rate and visual verification of leakage isolation, the TS Limiting Condition for Operation (LCO) was exited and the unit remained in Mode 3, Hot Standby, to affect repairs. The condition did not meet the Technical Specification Pressure Boundary Leakage definition of leakage through a non-isolable fault in a RCS component body, pipe wall or vessel wall. The leakage did not impact the ability to shut down the unit and no TS limits were exceeded during this event. Therefore, the plant shutdown to investigate and correct leakage from flawed sample system tubing does not meet the reporting requirements of 10 CFR 50.72 and PSEG is retracting the notifications made under 10 CFR 50.72(b)(2)(i) and 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspector was notified of this retraction by the licensee. Notified R1DO (Jackson). |
| Where | |
|---|---|
Salem  New Jersey (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 | |
| Time - Person (Reporting Time:+1.4 h0.0583 days <br />0.00833 weeks <br />0.00192 months <br />) | |
| Opened: | John Osborne 16:24 Feb 28, 2017 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Apr 14, 2017 |
| 52581 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (28 %) |
| After | Hot Standby (0 %) |
Salem with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 525812017-02-28T15:00:00028 February 2017 15:00:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Shutdown Due to Reactor Coolant System Pressure Boundary Leakage ENS 521292016-07-28T09:41:00028 July 2016 09:41:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Source Range Instruments Reading Improperly During a Reactor Startup ENS 508962015-03-15T16:27:00015 March 2015 16:27:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Due to Failure to Restore Containment Fan Cooler Unit ENS 493002013-08-22T20:26:00022 August 2013 20:26:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unit 1 Commenced a Ts Required Shutdown Due to Unidentified Rcs Leakage > 1 Gpm ENS 478742012-04-30T14:18:00030 April 2012 14:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Unusual Event Due to a Potential Fire in Containment ENS 470522011-07-15T00:53:00015 July 2011 00:53:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Unusual Event Declared Based on Reactor Coolant Leak Greater than 10 Gpm ENS 442052008-05-12T19:00:00012 May 2008 19:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shut Down Initiated Due to Inoperable Steam Generator Flow Channels ENS 416702005-05-06T03:05:0006 May 2005 03:05:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specifications Required Plant Shutdown Began and Then Terminated ENS 416162005-04-20T01:52:00020 April 2005 01:52:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specificiation Required Shutdown Related to Pressure Boundary Leakage ENS 408232004-06-17T04:22:00017 June 2004 04:22:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Plant Shutdown Due to Emergency Core Cooling System Inoperable ENS 407872004-06-02T16:30:0002 June 2004 16:30:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Was Initiated to Comply with Tech Spec. 3.6.1.1. Primary Containment Integrity. ENS 407642004-05-21T17:15:00021 May 2004 17:15:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown ENS 402502003-10-15T20:03:00015 October 2003 20:03:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Feedwater Regulating Valve Issue Forces Initiation of Technical Specification Shutdown 2017-02-28T15:00:00 | |