ENS 40519
ENS Event | |
|---|---|
11:25 Feb 13, 2004 | |
| Title | 24 Hour Notification Per Licensee Condition 2.F |
| Event Description | On February 13, 2004, Waterford 3 reactor power reached an estimated maximum reactor power level of 101.9% due to Atmospheric Dump Valve #2 (ADV#2) failing full open. ADV#2 failed open due to the control system setpoint failing low. Operations personnel promptly responded to the condition by reducing turbine load (5 megawatts per minute ) and manually closing ADV#2, to restore plant power. ADV#2 was open for less than a minute. Per the FSAR, this transient is an analyzed event and is bounded by the safety analyses. This event is being reported in accordance with Waterford 3 event notification and reporting procedure, UNT-006-010, which is more conservative than the guidance provided in NRC Inspection Procedure 61706. This event is being reported pursuant to Waterford 3 License Condition 2.F as a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification.
The licensee notified the NRC Resident Inspector.
On February 13, 2004, Waterford 3 provided a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC (reference EN 40519) stating that due to a failed open atmospheric dump valve, plant reactor power level momentarily reached a value of 101.9%. The event was reported conservatively based on the guidance provided in the plant's event notification and reporting procedure. The procedure has been revised to incorporate the guidance provided by NRC inspection Procedure 61706, 'Core Thermal Power Evaluation.' Based on this guidance, reporting of events such as stated above (transient power increases) are not required unless reactor power level exceeds 102%. Accordingly, this event is not reportable as power level only reached 101.9% momentarily. Based on the above, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification made on 2/13/2004 is being retracted. The licensee has notified the NRC Resident Inspector. Notified R4 DO (J. Clark) |
| Where | |
|---|---|
Waterford  Louisiana (NRC Region 4) | |
| Reporting | |
| Other Unspec Reqmnt | |
| Time - Person (Reporting Time:+9.12 h0.38 days <br />0.0543 weeks <br />0.0125 months <br />) | |
| Opened: | Greg Scott 20:32 Feb 13, 2004 |
| NRC Officer: | Eric Thomas |
| Last Updated: | Mar 15, 2004 |
| 40519 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 523372016-10-31T16:00:00031 October 2016 16:00:00
[Table view]Other Unspec Reqmnt Supplemental Cooling Inoperable During Movement of Dry Cask Storage Hi-Track Transfer Cask ENS 468242011-05-06T07:09:0006 May 2011 07:09:00 Other Unspec Reqmnt Discovery of an After-The-Fact Unusual Event ENS 406322004-04-01T01:19:0001 April 2004 01:19:00 Other Unspec Reqmnt, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition New Worst Case Single Failure May Exceed 10 Cfr 50.46 Acceptance Criterion for Sbloca ENS 405192004-02-13T11:25:00013 February 2004 11:25:00 Other Unspec Reqmnt 24 Hour Notification Per Licensee Condition 2.F 2016-10-31T16:00:00 | |