ENS 48402
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ENS Event | |
|---|---|
09:20 Oct 12, 2012 | |
| Title | Reactor Power Exceeded Fsar Analyzed Value |
| Event Description | On 10/12/12 at 0420 CDT the Unit 2 Steam Generator B Atmospheric Steam Dump Valve (ADV) spuriously opened while in automatic control. This resulted in indicated reactor power exceeding the FSAR analyzed value of 1810.8 MWt. Prompt operator action was taken and reactor power was restored to within limits in approximately four minutes. The operators placed the Atmospheric Steam Dump Controller to manual and closed the ADV successfully. This event is being reported under the criteria in 10 CFR 50.72 (b)(3)(ii)(B).
All other plant systems responded as expected. The licensee has notified the NRC Resident Inspector.
This notification is being made to retract Event Notification EN #48402 which reported power exceeding the FSAR analyzed value of 1810.8 MWt due to a spurious opening of an Atmospheric Steam Dump Valve. While 1810.8 MWt is the normal PBNP [Point Beach Nuclear Plant] full power value without consideration to uncertainties, subsequent reviews show that the peak power level reached during the event was bounded by FSAR analyzed events. Additionally, the opening of the valve is an Anticipated Operational Occurrence, described and analyzed in the FSAR. The power excursion during the event was below excursions evaluated in the FSAR. The event was analyzed and plant safety was not significantly degraded. Therefore, the event does not meet the criteria of 10CFR50.72(b)(3) and NextEra Energy Point Beach retracts Event Notification EN #48402. The licensee notified the NRC Resident Inspector. Notified the R3DO (Pelke). |
| Where | |
|---|---|
Point Beach  Wisconsin (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+2.15 h0.0896 days <br />0.0128 weeks <br />0.00295 months <br />) | |
| Opened: | Russ Parker 11:29 Oct 12, 2012 |
| NRC Officer: | John Knoke |
| Last Updated: | Dec 4, 2012 |
| 48402 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 532392018-03-01T22:43:0001 March 2018 22:43:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Tornado Missile Vulnerabilities ENS 529762017-09-18T22:24:00018 September 2017 22:24:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Control Room Envelope Not Maintained ENS 507402015-01-15T23:04:00015 January 2015 23:04:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Inadequately Sealed Piping Penetrations and Postulated Flooding Event ENS 484022012-10-12T09:20:00012 October 2012 09:20:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Reactor Power Exceeded Fsar Analyzed Value ENS 443512008-07-16T20:16:00016 July 2008 20:16:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Potential Fire Propagation Between Rooms Could Affect Appendix R Safe Shutdown ENS 434872007-07-12T15:15:00012 July 2007 15:15:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Inspection Analysis of Pressurizer Porvs and Block Valves ENS 433532007-05-09T21:23:0009 May 2007 21:23:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Due to Identified Non Compliant Fire Protection Manual Operator Actions ENS 421292005-11-08T14:44:0008 November 2005 14:44:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Design Basis for Long Term Cooling Not Correctly Modeled ENS 421092005-11-02T05:00:0002 November 2005 05:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Required Shutdown Due to Degradation of Containment Coatings ENS 420202005-09-27T15:00:00027 September 2005 15:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Postulated Faults Have Electrical Current in Excess of the Maximum Listed Interrupting Ratings. ENS 418562005-07-20T09:51:00020 July 2005 09:51:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Minimum Recirculation Valves Will Not Automatically Open in Local Operating Mode ENS 417582005-06-08T22:24:0008 June 2005 22:24:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition - Fire Organizational Plan No Longer Aligned with Safe Shutdown Analysis ENS 417542005-06-07T23:00:0007 June 2005 23:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Appendix R Safe Shutdown Strategy Deficiency 2018-03-01T22:43:00 | |
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