ENS Event | |
|---|---|
23:28 Aug 29, 2004 | |
| Title | Alarm Indication of Inoperable Reactor Water Cleanup Supply Isolation Valve |
| Event Description | On 08/29/04 at 1928 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.33604e-4 months <br /> [EDT], an alarm was received in the control room indicating the reactor water cleanup (RWCU) high differential flow isolation channel for the outboard RWCU supply isolation valve was inoperable. At the time, the channel functional test for the inboard RWCU high differential flow isolation channel was being performed. During the channel functional test, power to the inboard isolation valve is removed to permit continued RWCU system operation while the isolation function is tested. With the outboard isolation actuation instrumentation channel inoperable and the inboard isolation valve deenergized, in the event of a break in the RWCU system, the required isolation function may not be completed.
This event is being reported in accordance with 10CFR50.72(b)(3)(v)(C) as a condition that could have prevented the fulfillment of a safety function. In accordance with Technical Specification requirements, the RWCU system was removed from service and the inboard and outboard supply Isolation valves were closed. There is no immediate impact on water chemistry and the licensee is investigating the cause of the original failure as well as possible long term degradation of the reactor water chemistry. The licensee notified the NRC Resident Inspector and will notify the local township authorities of this incident. |
| Where | |
|---|---|
Hope Creek  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| Time - Person (Reporting Time:+3.43 h0.143 days <br />0.0204 weeks <br />0.0047 months <br />) | |
| Opened: | Art Bready 02:54 Aug 30, 2004 |
| NRC Officer: | Arlon Costa |
| Last Updated: | Aug 30, 2004 |
| 40996 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (98 %) |
| After | Power Operation (98 %) |
WEEKMONTHYEARENS 512742015-07-28T17:58:00028 July 2015 17:58:00
[Table view]10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Discovered One Inch Diameter Hole Between Reactor Building and Auxiliary Building ENS 496652013-12-19T20:11:00019 December 2013 20:11:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Loss of Reactor Building Ventilation ENS 450482009-05-08T12:17:0008 May 2009 12:17:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Primary Containment Isolation Valves Discovered Open ENS 409962004-08-29T23:28:00029 August 2004 23:28:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Alarm Indication of Inoperable Reactor Water Cleanup Supply Isolation Valve 2015-07-28T17:58:00 | |