ENS Event | |
|---|---|
17:50 Mar 23, 2006 | |
| Title | 24-Hour Condition of License Report Due to Thermal Power Potentially Exceeding Licensed Limit |
| Event Description | McGuire Unit 1 and Unit 2 may have been operating greater than design thermal power limits of 3411 MW [Megawatt] by approximately 0.08% due to discovery of non-conservative thermal power calculations. Preliminary evaluation of Steam Generator Blow Down inputs into the thermal power calorimetric indicates a non-conservative error resulting in indicated total thermal power being approximately 0.08% lower than actual. Additional evaluations to confirm indicated power are ongoing. Power was reduced as soon as the on duty shift was made aware of the error and both Unit 1 and Unit 2 indicated thermal power is being limited to less than 99.85% to ensure actual reactor power remains less than 3411 MW.
This notification is being made pursuant to the McGuire Facility Operating License Condition 2.C.(1) Maximum Power Level. The licensee will inform the NRC Resident Inspector.
McGuire Nuclear Station is retracting event number 42446 which was reported to the NRC Operations Center on 3/23/06 at 1820. This event is now determined to be not reportable because further analyses of plant parameters, engineering margins, and actual plant power operation history indicated that neither Unit 1 nor Unit 2 exceeded 3411 megawatt thermal. The analyses and the bases for this retraction can be found under the plant corrective action program. Notified the R2DO (Bonser). The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
McGuire  North Carolina (NRC Region 2) | |
| Reporting | |
| Other Unspec Reqmnt | |
| Time - Person (Reporting Time:+0.5 h0.0208 days <br />0.00298 weeks <br />6.849e-4 months <br />) | |
| Opened: | Fred Kirk 18:20 Mar 23, 2006 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Apr 4, 2006 |
| 42446 - NRC Website
Loading map... | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (99 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (99 %) |
WEEKMONTHYEARENS 424462006-03-23T17:50:00023 March 2006 17:50:00
[Table view]Other Unspec Reqmnt 24-Hour Condition of License Report Due to Thermal Power Potentially Exceeding Licensed Limit ENS 422032005-12-12T23:30:00012 December 2005 23:30:00 Other Unspec Reqmnt Violation of Spent Fuel Handling Conditions 2006-03-23T17:50:00 | |