ENS 40639
ENS Event | |
|---|---|
15:50 Apr 3, 2004 | |
| Title | Valid Actuation of Auxiliary Feedwater System During Maintenance |
| Event Description | This is an 8-hour notification being made to report that a valid ESF Auxiliary Feed actuation occurred. Salem Unit 1 is in mode 5 with RHR providing shutdown cooling. '11' Aux Feed Pump was in service to fill '13' and '14' steam generators for wet lay-up conditions. Actual levels were low in both '13' and '14' steam generators but jumpers were installed on steam generator narrow range level channel III and IV to prevent an ESF actuation. On 4/03/04 at 1050 AM, a breaker effecting reactor protection system channel III was cleared and tagged as part of preparations to remove 1C 4KV vital bus from service. The actual low level in '13' and '14' steam generators along with the power loss to channel III caused 2 out of 3 logic to be satisfied and initiated an AFW actuation. '11' Auxiliary Feed Pump remained running. '12' Auxiliary Feed Pump auto started. '13' Auxiliary Feedwater Pump was removed from service prior to the actuation and did not start. The '13' and '14' steam generators continued to fill. '11' and '12" Auxiliary Feed Valves (11AF21 and 12AF21) were closed and no level rise was observed. The breaker was restored and reactor protection system channel III was placed back in service. All auto start signals cleared after power was restored and the '12' Aux Feed Pump was stopped at 1101. There were no unusual or unexpected plant response from the actuation. All safety systems and equipment performed as expected. Entry into mode 6 is expected this afternoon and progress of the refueling outage is expected to continue. There were no personnel injured.
The licensee will inform the Lower Alloways Creek Township (LAC) and has informed the NRC Resident Inspector.
On April 3, 2004 at 1410 PSEG made an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification to report a valid ESF actuation of the auxiliary feedwater system (Event Number 40639). At the time of the report 11 Auxiliary feedwater pump was in service to fill the 13 and 14 steam generators for wet lay-up. The levels on those generators were low (as previous plant condition had demanded) and the jumpers had been installed in the level detectors to prevent the automatic start of the auxiliary feedwater pumps. 12 auxiliary feedwater pump was out of service. The steam driven auxiliary feedwater pump was tagged out of service. Core heat removal was being provided by the Residual Heat Removal System. On April 3, with the steam generator level being carried below the low level setpoint, in accordance with procedures, as a result of other activities associated with the refueling outage the installed jumpers were removed causing the auto start of the 12 pump. Subsequent investigation Into this event and further review of NUREG 1022 has determined that the condition described above is not reportable under the requirements of 10CFR50.72(b)(3)(iv) or 50.73(a)(2)(iv). As stated In NUREG 1022 the intent of reporting under this paragraph is '..to report actuations of systems that mitigate the consequences of significant events .. The Staff does not consider this to include single component actuation because single components of complex systems, by themselves usually do not mitigate the consequences of significant events.' Furthermore valid signals are defined as ' those signals that are Initiated in response to actual plant conditions .. Satisfying the requirements for initiation of a safety function of the system.' (emphasis added on safety function). In this particular event the required Safety Function to maintain the core cooled and decay heat removal was being accomplished by the Residual Heat Removal System and it remained unaffected throughout this event. The plant was in a condition where the steam generators in conjunction with the Auxiliary Feedwater System were not part of the ultimate heat sink or a principal means to remove decay heat. The Auxiliary Feedwater System was only functional and available to provide a means to place the steam generators in wet lay-up in support of outage activities. The 11 pump was already in service providing for this non-safety related function. Thus the auto start of the 12 pump was not as a result of a valid signal for a significant event that required initiation of a mitigating function; e.g. an ESF actuation. Therefore this event was not reportable under 10CFR50.72 or 50.73, as per the guidance provided in NUREG 1022. The licensee notified the NRC Resident Inspector. Notified R1DO(Della Greca). |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-1.67 h-0.0696 days <br />-0.00994 weeks <br />-0.00229 months <br />) | |
| Opened: | Jason Mikulka 14:10 Apr 3, 2004 |
| NRC Officer: | Steve Sandin |
| Last Updated: | May 5, 2004 |
| 40639 - NRC Website
Loading map... {"minzoom":false,"maxzoom":false,"mappingservice":"leaflet","width":"350px","height":"250px","centre":false,"title":"","label":"","icon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"zoom":6,"defzoom":14,"layers":["OpenStreetMap"],"image layers":[],"overlays":[],"resizable":false,"fullscreen":false,"scrollwheelzoom":true,"cluster":false,"clustermaxzoom":20,"clusterzoomonclick":true,"clustermaxradius":80,"clusterspiderfy":true,"geojson":"","clicktarget":"","imageLayers":[],"locations":[{"text":"\u003Cb\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003E\u003Ca class=\"mw-selflink selflink\"\u003EENS 40639\u003C/a\u003E - \u003Ca href=\"/Salem\" title=\"Salem\"\u003ESalem\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EValid Actuation of Auxiliary Feedwater System During Maintenance\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 40639 - Salem\n","link":"","lat":39.46302222222222,"lon":-75.53561388888889,"icon":"/w/images/c/cc/PSEG_icon.png"}],"imageoverlays":null} | |
Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 562862022-12-24T07:22:00024 December 2022 07:22:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 542112019-08-11T12:14:00011 August 2019 12:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Feedwater Regulating Valve Malfunction ENS 538522019-01-31T08:01:00031 January 2019 08:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip - Circulating Water Icing Conditions ENS 536062018-09-14T04:00:00014 September 2018 04:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to a Failure of the Steam Generator Feed Regulating Valve ENS 533862018-05-07T07:25:0007 May 2018 07:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 526812017-04-14T17:57:00014 April 2017 17:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Emergency Diesel Generator Start Due to Loss of a 4160 V Bus ENS 522132016-08-31T19:11:00031 August 2016 19:11:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Reactor Coolant Flow ENS 520482016-06-28T08:23:00028 June 2016 08:23:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Main Generator Protection Signal ENS 517382016-02-16T13:27:00016 February 2016 13:27:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Pump Auto Start Due to Feed Pump Trip ENS 517342016-02-15T01:58:00015 February 2016 01:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Main Generator Protection Trip ENS 517082016-02-04T16:21:0004 February 2016 16:21:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Main Turbine Trip ENS 512902015-08-05T19:38:0005 August 2015 19:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Reactor Coolant Flow ENS 505502014-10-20T00:51:00020 October 2014 00:51:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Resulting in Aux Feedwater Actuation ENS 500922014-05-07T08:56:0007 May 2014 08:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip Due to Generator Protection Relay ENS 500322014-04-14T01:13:00014 April 2014 01:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Actuation of Main Generator Protection Relay ENS 500122014-04-09T01:14:0009 April 2014 01:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manually Tripped Following the Loss of an Operating Steam Generator Feed Pump (Sgfp) ENS 486172012-12-21T10:28:00021 December 2012 10:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Automatic Reactor Trip on Turbine Trip ENS 485342012-11-25T16:30:00025 November 2012 16:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Steam Generator Feedwater Regulator Valve Not Responding to Demand Signal ENS 484572012-10-30T05:09:00030 October 2012 05:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip from 100% Power ENS 477662012-03-23T18:28:00023 March 2012 18:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip Followed by Automatic Reactor Trip ENS 469922011-06-26T04:00:00026 June 2011 04:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Loss of Reactor Coolant Pump ENS 467742011-04-21T20:01:00021 April 2011 20:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Circulating Water Pumps Out of Service ENS 463372010-10-17T09:12:00017 October 2010 09:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to 4 Kv Group Bus Undervoltage Condition ENS 463362010-10-16T03:21:00016 October 2010 03:21:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to a Turbine Trip ENS 460752010-07-07T15:17:0007 July 2010 15:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Caused by Main Generator and Turbine Trip ENS 458482010-04-16T20:41:00016 April 2010 20:41:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Emergency Diesel Generator Start Due to Loss of a 4160 V Bus ENS 456472010-01-21T23:20:00021 January 2010 23:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Low Steam Generator Water Level ENS 456042010-01-03T13:04:0003 January 2010 13:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Circulators After Uptake of River Ice ENS 446292008-11-05T05:57:0005 November 2008 05:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Start Due to Unexpected Esf Signal ENS 438732007-12-28T22:54:00028 December 2007 22:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip on Failure of Station Power Transformer ENS 435502007-08-06T17:10:0006 August 2007 17:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Spurious Interlock Signal to Feedwater Regulating Valves ENS 432592007-03-28T00:50:00028 March 2007 00:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Low Steam Generator Water Level Initiated Auxiliary Feedwater Signal and a Reactor Trip Signal ENS 429462006-10-30T01:11:00030 October 2006 01:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Auxiliary Feedwater During Msiv Testing ENS 423952006-03-08T16:09:0008 March 2006 16:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip as a Result of a Turbine Generator Trip ENS 408752004-07-15T23:44:00015 July 2004 23:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Trip from 8% Power Due to Lowering Water Level on 23 Steam Generator ENS 408652004-07-13T17:05:00013 July 2004 17:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Low Steam Generator Water Level. ENS 406652004-04-11T04:23:00011 April 2004 04:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Plant Had a Valid Esf Signal to Start 1C Emergency Diesel Generator ENS 406392004-04-03T15:50:0003 April 2004 15:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Auxiliary Feedwater System During Maintenance 2022-12-24T07:22:00 | |