ENS 53584
ENS Event | |
|---|---|
04:00 Mar 19, 2018 | |
| Title | Invalid Specified System Actuation |
| Event Description | Pursuant to 50.73(a)(1) the following information is provided as a sixty (60) day telephone notification to the NRC. This notification, reported under 50.73(a)(2)(iv), is being provided in lieu of the submittal of a written LER [Licensee Event Report] to report a condition that resulted in an invalid actuation of the high pressure coolant injection (HPCI). At Nine Mile Point Unit 1, HPCI is a flow control mode of the normal feedwater system and is not an emergency core cooling system.
On March 19, 2018 Nine Mile Point Unit 1 (NMP1) was at 0 percent power and in cold shutdown in support of a planned maintenance outage. At approximately 0118 [EDT], a reactor water level transient initiated by the fill and vent of 12 Reactor Recirculation Pump (12 RRP) occurred. During the fill and vent, Reactor Pressure Vessel (RPV) level lowered quickly from the initial level of 68 inches and a low level alarm was received. Control Room Operators reduced Reactor Water Clean-Up (RWCU) reject flow to turn the level trend and clear the low level alarm generated off of the compensated, GEMAC, level instrumentation. RWCU reject flow was reduced by 50 percent which caused RPV level to start to rise. RPV level was raised to approximately 72 inches at which time the Reactor Operator began to raise reject flow to reestablish the normal level band. During the RPV level transient, with actual water level at 74 inches on the GEMAC, the Yarway level instrumentation, which is not density compensated and therefore invalid, reached 92 inches causing an invalid high RPV water level turbine trip signal and associated invalid HPCI initiation signal. At no point in time did actual RPV water level reach the high RPV water level turbine trip set point of 92 inches. The potential for a turbine trip signal to occur due to shutdown activities was understood and tags were hung to lockout the Feedwater Pumps to prevent the HPCI start signal. Therefore, no HPCI injection occurred. The Licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Nine Mile Point  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
| Time - Person (Reporting Time:+4117.3 h171.554 days <br />24.508 weeks <br />5.64 months <br />) | |
| Opened: | Gregory Bixby 17:18 Sep 6, 2018 |
| NRC Officer: | Andrew Waugh |
| Last Updated: | Sep 6, 2018 |
| 53584 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 535842018-03-19T04:00:00019 March 2018 04:00:00
[Table view]10 CFR 50.73(a)(1), Submit an LER Invalid Specified System Actuation ENS 527472017-03-20T06:16:00020 March 2017 06:16:00 10 CFR 50.73(a)(1), Submit an LER 60-Day Optional Telephone Notification for an Invalid High Pressure Coolant Injection System Actuation ENS 509092015-01-21T15:00:00021 January 2015 15:00:00 10 CFR 50.73(a)(1), Submit an LER 60-Day Optional Notification - Invalid Containment Isolation Signal ENS 490842013-04-02T13:46:0002 April 2013 13:46:00 10 CFR 50.73(a)(1), Submit an LER 6O-Day Optional Telephone Notification for an Invalid Specified System Actuation ENS 485702012-10-12T14:12:00012 October 2012 14:12:00 10 CFR 50.73(a)(1), Submit an LER Temperature Switch Failure Causes Division I Isolation Signal ENS 481132012-05-24T14:20:00024 May 2012 14:20:00 10 CFR 50.73(a)(1), Submit an LER 60 - Day Optional Telephone Notification of an Invalid Division 2 Containment Isolation Signal ENS 475472011-11-08T03:31:0008 November 2011 03:31:00 10 CFR 50.73(a)(1), Submit an LER Invalid Specified System Actuation Due to a Possible Faulty Temperature Switch ENS 457792010-03-15T16:43:00015 March 2010 16:43:00 10 CFR 50.73(a)(1), Submit an LER Inadvertent Start of Emergency Diesel Generator ENS 439232008-01-14T18:41:00014 January 2008 18:41:00 10 CFR 50.73(a)(1), Submit an LER Invalid Actuation of Group 5 and Group 10 Primary Containment Valves During Surveillance Testing ENS 438552007-11-08T15:21:0008 November 2007 15:21:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System (Pcis) Actuation ENS 407182004-04-01T07:06:0001 April 2004 07:06:00 10 CFR 50.73(a)(1), Submit an LER Invalid Automatic Start of Emergency Diesel Generator During Surveillance Test 2018-03-19T04:00:00 | |