ENS 43132
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ENS Event | |
|---|---|
04:10 Jan 30, 2007 | |
| Title | Automatic Reactor Scram on Low Reactor Pressure Vessel (Rpv) Water Level |
| Event Description | On 1/29/07 with Hope Creek reactor startup in progress, in mode 1 at 22% Reactor power, Secondary Condensate Pump Minimum Flow Control Valves began to cycle. Reactor water level reached 39" (RPV level 7) and then lowered to 30" (RPV level 4). Manual control of the Reactor Feed pumps was taken, however, RPV water level continued to lower to 15" (Reactor scram on RPV water level is 12.5") at which time the reactor mode switch was locked in shutdown. There were no ECCS injections and all ECCS systems are operable. Initial review of the event indicates that all systems operated as expected with the exception of the Secondary Condensate pump minimum flow valves and the 'A' IRM failed to insert. Current plant conditions as of 1/30/07 at 0010 are: Hope Creek is in mode 3 at 565 psig. The Main Steam Line Isolation valves are open. 'B' and 'C' Primary Condensate Pumps, 'B' and 'C' Secondary Condensate Pumps, and 'A' Rx Feed Pump are feeding the vessel. All control rods have fully inserted on the scram and Main Turbine Bypass valves are removing decay heat.
The licensee will inform the LAC (Lower Alloways Creek Township) and has informed the NRC Resident Inspector.
Based on the post-trip review performed by the licensee, it was determined that the in-service Reactor Feed Pump Minimum Flow Recirculation Valve opened in response to the feed flow adjustments. Reactor vessel level reached the low-level trip set point and an automatic reactor scram occurred. During the event analysis it was determined that the operator initiated the manual scram two seconds after the automatic low level scram occurred. A post event equipment performance review concluded that the Secondary Condensate Pump Minimum Flow Recirculation Valves operated as expected. The licensee notified the NRC Resident Inspector. The R1DO (Cahill) notified. |
| Where | |
|---|---|
Hope Creek  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-3.35 h-0.14 days <br />-0.0199 weeks <br />-0.00459 months <br />) | |
| Opened: | Bernie Litkett 00:49 Jan 30, 2007 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Feb 1, 2007 |
| 43132 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (22 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 568892023-12-15T00:39:00015 December 2023 00:39:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram ENS 541982019-08-03T23:47:0003 August 2019 23:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Manual Actuation of Reactor Core Isolation Cooling ENS 514302015-09-29T00:46:00029 September 2015 00:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Following Trip of Both Reactor Recirculation Pumps ENS 496082013-12-05T08:25:0005 December 2013 08:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Following Turbine Trip on High Moisture Separator Level ENS 495922013-12-01T11:13:0001 December 2013 11:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Main Turbine Trip ENS 491082013-06-12T17:33:00012 June 2013 17:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Circulating Water Pump Trip Leads to Reactor Scram ENS 450742009-05-17T07:35:00017 May 2009 07:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Loss of Scram Air Header ENS 431322007-01-30T04:10:00030 January 2007 04:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram on Low Reactor Pressure Vessel (Rpv) Water Level ENS 411092004-10-10T22:14:00010 October 2004 22:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Manual Reactor Scram Due to a Steam Leak in the Turbine Building ENS 404372004-01-12T15:48:00012 January 2004 15:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram Following Invalid Containment Isolation Signal ENS 402242003-10-04T21:13:0004 October 2003 21:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation While Critical 2023-12-15T00:39:00 | |
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