ENS Event | |
|---|---|
05:45 Jul 14, 2004 | |
| Title | Rps and Containment Isolation Actuation Due to Low Rpv Level |
| Event Description | On July 14, 2004, at 0045 CDT, the Clinton Power Station experienced a drop in RPV [Reactor Pressure Vessel] level from nominally 30 inches to the Level 3 (the RPS and Isolation setpoint). At this time control rods were fully inserted [see Event Notification - #40868], however, the containment isolation valves associated with this setpoint were open, and these valves automatically closed successfully.
Level was restored to normal by automatic makeup from the condensate system. There were no other malfunctions. The cause for the level drop is being investigated. The licensee will notify the NRC Resident Inspector. |
| Where | |
|---|---|
Clinton  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-1.83 h-0.0763 days <br />-0.0109 weeks <br />-0.00251 months <br />) | |
| Opened: | Bill Carsky 03:55 Jul 14, 2004 |
| NRC Officer: | Bill Gott |
| Last Updated: | Jul 14, 2004 |
| 40869 - NRC Website
Loading map... | |
Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 580402025-11-14T19:51:00014 November 2025 19:51:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Emergency Diesel Generators ENS 541972019-08-03T07:26:0003 August 2019 07:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge En Revision Imported Date 8/7/2019 ENS 536232018-09-26T05:00:00026 September 2018 05:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Undervoltage Condition Initiates an Automatic Start of the Diesel Generator ENS 475332011-12-18T15:30:00018 December 2011 15:30:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Rhr Cooling Due to Incorrect Reactor Water Level Indication ENS 408692004-07-14T05:45:00014 July 2004 05:45:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps and Containment Isolation Actuation Due to Low Rpv Level ENS 403682003-12-02T22:58:0002 December 2003 22:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Low Reactor Water Feed Pump Suction Pressure 2025-11-14T19:51:00 | |