ENS 52129
ENS Event | |
|---|---|
09:41 Jul 28, 2016 | |
| Title | Source Range Instruments Reading Improperly During a Reactor Startup |
| Event Description | This four and eight hour notification is being made to report that at 0541 [EDT] on 7/28/16, Salem Unit 1 initiated a shutdown to comply with Technical Specifications due to the inoperability of both source range nuclear instruments. During a reactor startup, with Unit 1 in Mode 2, both source range instruments were reading approximately one decade lower than expected compared to intermediate range and Gamma-Metric instruments and due to the proximity to the estimated critical condition. The condition could also have prevented the fulfilment of the source range instruments safety function to trip the reactor when required.
Salem Unit 1 is currently stable in Mode 3. Reactor Coolant system pressure is 2235 psig and reactor coolant system temperature is 547 F with decay heat removal via the main steam dump and auxiliary feedwater systems. Unit 1 has one active shutdown tech spec action statement in effect due to the inoperability of the containment radiation monitor 1R11A. The inoperability of this radiation monitor had no effect on the event. All control rods were manually inserted to place Unit 1 in Hot Standby (Mode 3). No ECCS [emergency core cooling system] or ESF [emergency safety features] systems were required to function during this event. No major secondary equipment was tagged for maintenance prior to this event. No personnel were injured during this event. The reactor was manually shut down and a shutdown margin calculation verified sufficient margin. The licensee notified the NRC Resident Inspector and the local township.
The purpose of this notification is to retract event report number 52129 made on 7/28/2016 at 0925 (EDT). Previously PSEG reported that Salem Unit 1 initiated a shutdown to comply with Technical Specifications (TS) due to the inoperability of both source range nuclear instruments. Additionally PSEG reported that the condition could have prevented the fulfillment of the safety function needed to, 'Shut down the reactor and maintain it in a safe shutdown condition.' Subsequent review identified that the condition did not meet either reporting criteria. Maintenance and Engineering evaluation of the source range nuclear instruments determined that the instruments were fully operable at the time of the event. TS 3.3.1.1, Reactor Trip Instrumentation remained met, no TS shutdown was required and the instruments were capable of performing their required function. Therefore PSEG is retracting the notifications made under 10 CFR 50.72(b)(2)(i) and 10 CFR 50.72(b)(3)(v)(A). The NRC Resident Inspector was notified of this retraction by the licensee. Notified the R1DO (Cook). |
| 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)(v)(A), Loss of Safety Function - Shutdown the Reactor | |
| Time - Person (Reporting Time:+-0.27 h-0.0113 days <br />-0.00161 weeks <br />-3.69846e-4 months <br />) | |
| Opened: | Eric Powell 09:25 Jul 28, 2016 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Sep 26, 2016 |
| 52129 - NRC Website
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Salem with 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 | |
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 475172011-12-11T17:58:00011 December 2011 17:58:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Intermediate Range Nuclear Instrument High Flux Trip Set Points Set Incorrectly 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 430382006-12-07T22:28:0007 December 2006 22:28:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Loss of Safe Shutdown Capability 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 413592005-01-26T20:50:00026 January 2005 20:50:00 Other Unspec Reqmnt, 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Potential for Carbon Dioxide Migration Into 4160/460 Volt Switchgear Rooms ENS 409042004-07-29T01:00:00029 July 2004 01:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Unidentified Reactor Coolant System (Rcs) Leak 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 | |