ENS 43038
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ENS Event | |
|---|---|
22:28 Dec 7, 2006 | |
| Title | Loss of Safe Shutdown Capability |
| Event Description | The Unit 2 Spray Additive System was isolated due to an identified crack on a weld at a 'tee' section of pipe upstream of a sample point. The crack was identified during a system release for an unrelated maintenance activity. Isolation of the crack for repairs requires isolation of the Containment Spray Additive system from both Containment Spray headers. This isolation was also completed to comply with ASME (Technical Specification Action Statement) 3.4.11.1. Therefore the Containment Spray Additive system is unable to perform its safety function. Salem Unit 2 remains in TS A/S 3.6.2.2 until repairs are complete.
TS A/S 3.6.2.2 is a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO (entered at 0503 on 12/07/06) and requires the plant to be in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of the expiration of the LCO. The licensee will inform the Lower Alloways Creek Township and has informed the NRC Resident Inspector.
On December 7, 2006, PSEG made a non-emergency report in accordance with the 10 CFR 50.72(b)(3)(v)(A) and 10 CFR 50.72(b)(3)(v)(D) (event report 43038) regarding the Salem Unit 2 Spray Additive System. Upon further investigation, PSEG determined that the identified crack on a weld which resulted in a one drop per minute leak would not have caused a loss of system function. Therefore, based upon the guidance provided in NUREG 1022 that there is reasonable assurance that the weld would have remained intact and would have satisfactorily performed its intended function in the event of a CS system actuation (i.e., there was no loss of system safety function) this event report is being retracted. The NRC Resident Inspector was notified of this retraction. R1DO (Cook) notified. |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 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 | |
| Time - Person (Reporting Time:+-0.62 h-0.0258 days <br />-0.00369 weeks <br />-8.49276e-4 months <br />) | |
| Opened: | Kenneth Faber 21:51 Dec 7, 2006 |
| NRC Officer: | Jason Kozal |
| Last Updated: | Feb 5, 2007 |
| 43038 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Salem with 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 | |
WEEKMONTHYEARENS 534382018-06-01T04:00:0001 June 2018 04:00:00
[Table view]10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Tornado Missile Vulnerabilities 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 515632015-11-24T02:48:00024 November 2015 02:48:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to Reactor Coolant System Leakage ENS 515042015-10-28T10:28:00028 October 2015 10:28:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Both Trains of Control Room Emergency Air Conditioning System Inoperable ENS 511702015-06-22T18:06:00022 June 2015 18:06:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Sodium Hydroxide Below Technical Specification Required Concentration ENS 505732014-10-29T11:11:00029 October 2014 11:11:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Loss of Control Room Emergency Air Conditioning System Operability ENS 504052014-08-27T06:48:00027 August 2014 06:48:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Safety Injection Pump Failed to Start ENS 489492013-04-20T08:22:00020 April 2013 08:22:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Accident Mitigation - Common Control Room Emergency Air Conditioning System ENS 480712012-07-05T14:00:0005 July 2012 14:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Valve Improperly Aligned for Accident Mitigation 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 441202008-04-04T16:59:0004 April 2008 16:59:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Accident Mitigation - Common Control Room Emergency Air Conditioning System 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 415252005-03-25T01:15:00025 March 2005 01:15:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Reactor Coolant Leakage Outside Containment Exceeding Design Basis 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 411182004-10-13T19:41:00013 October 2004 19:41:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Reactor Coolant Leakage Outside Containment Exceeding Final Safety Analysis Limits 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 407802004-05-27T10:30:00027 May 2004 10:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Automatic Safety Injection Function Inadvertantly Blocked ENS 406702004-04-12T14:33:00012 April 2004 14:33:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Accident Mitigation - Common Control Room Emergency Air Conditioning System ENS 404802004-01-25T22:00:00025 January 2004 22:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Differential Pressure in Auxiliary Building 2018-06-01T04:00:00 | |
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