ENS 40437
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ENS Event | |
|---|---|
15:48 Jan 12, 2004 | |
| Title | Manual Scram Following Invalid Containment Isolation Signal |
| Event Description | On 01/12/04 at 1048 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98764e-4 months <br />, the Hope Creek Generating Station reactor was manually scrammed following an invalid containment isolation signal on Reactor Building High-High Radiation. The invalid signal was caused by the combination of a scheduled sensor calibration on channel 'C', coincident with an emergent failure on channel 'A.' This combination of trip signals made up the two out of three trip logic for the Reactor Building High-High Radiation containment isolation signal. While recovering from the spurious isolation signal, the operating crew observed two of the inboard MSIV's drifting closed from a loss of pneumatic pressure as a result of the isolation signal. In response to this condition, the operating crew manually scrammed the reactor. A low reactor water level scram signal was received at 12.5 inches as expected, and reactor level was subsequently returned to the normal band using the reactor feedpumps. At the time of this event, the 'A' Control Room Ventilation Train was inoperable but available pending emergent corrective maintenance. The 'C' channel Reactor Building Radiation monitor has been returned to service and is operable, and the 'A' channel remains failed in the tripped condition. All other systems functioned as expected, and a post-transient review team is being assembled to investigate the event.
Decay heat is being removed via steam to the main condenser using the bypass valves. The condensate and feedwater system is in operation maintaining reactor vessel water level. No SRVs lifted during the transient and the electrical system is stable in a normal lineup. The licensee notified the NRC Resident Inspector and will be notifying the LAC Township. |
| Where | |
|---|---|
Hope Creek  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-3.3 h-0.138 days <br />-0.0196 weeks <br />-0.00452 months <br />) | |
| Opened: | Art Bready 12:30 Jan 12, 2004 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Jan 12, 2004 |
| 40437 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (68 %) |
| 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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