ENS 43410
ENS Event | |
|---|---|
17:10 Jun 6, 2007 | |
| Title | Containment Isolation Valves Found Misaligned |
| Event Description | On 6/06/07 at 13:10 EDT while performing a surveillance to verify the position of administratively locked valves for Containment and Shield Building Integrity, two manual Containment Isolation valves were found Locked Open, versus the required Locked Closed position. The valves were restored to the Locked Closed position at 13:30 EDT of the same day.
The subject valves, V18794 and V18796, provide Service Air (a non-safety class system) to the Containment during Mode 5 and 6 conditions through Containment Penetration #8. The subject valves are required to be returned to Locked Closed prior to entering Mode 4 in accordance with the Plant Technical Specifications 3.6.1.1 for Containment Integrity and plant procedures. The valves are to be verified in the Locked Closed position once every 31 days per Administrative Procedure 1-0010123 Appendix E, which was last performed on 5/09/07. Unit 1 exited Mode 5 and entered Mode 4 on 5/20/07 following a refueling outage and is currently in Mode 1 at 100% power. It is assumed the valves have been incorrectly positioned since entering Mode 4. The Service Air System is intact and pressurized at approximately 110 psig. There is no open path from Containment to the outside atmosphere. This event is being reported pursuant to 10CFR50.72(b)(3)(ii)(A), based on principal safety barriers being seriously degraded. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Saint Lucie  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+1 h0.0417 days <br />0.00595 weeks <br />0.00137 months <br />) | |
| Opened: | Calvin Ward 18:10 Jun 6, 2007 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Jun 6, 2007 |
| 43410 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 569122024-01-03T17:57:0003 January 2024 17:57:00
[Table view]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)(A), Seriously Degraded Pressure Boundary Degraded / Both Trains of High Pressure Safety Injection Inoperable ENS 568932023-12-16T01:45:00016 December 2023 01:45:00 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)(A), Seriously Degraded Reactor Coolant System Leak ENS 535982018-09-11T04:00:00011 September 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Weld Defect on Pressurizer Interface ENS 525232017-01-31T17:00:00031 January 2017 17:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant Pressure Boundary Piping Defect ENS 503102014-07-25T15:29:00025 July 2014 15:29:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to a Safety Injection Valve Defect ENS 452002009-07-13T11:00:00013 July 2009 11:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Identified ENS 439412008-01-29T10:31:00029 January 2008 10:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip to Repair Rcp "2B1" Seal Package ENS 438632007-12-21T19:45:00021 December 2007 19:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Pressure Boundary Leakage on Rcp Seal Injection Line ENS 435802007-08-19T21:00:00019 August 2007 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Plant Shutdown Due to Unisolable Reactor Coolant System Leakage ENS 434102007-06-06T17:10:0006 June 2007 17:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Isolation Valves Found Misaligned ENS 414012005-02-10T21:00:00010 February 2005 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Leakage Identified During Plant Startup Walkdowns 2024-01-03T17:57:00 | |