ENS Event | |
|---|---|
08:33 Oct 12, 2009 | |
| Title | Technical Specification Shutdown Due to Unidentified Leakage from Rcs |
| Event Description | This notification is being provided in accordance with 10CFR50.72(b)(2)(i), plant shutdown required by Technical Specifications.
At 0300 [CDT] on 10/12/09, LaSalle Unit 2 commenced a plant shutdown. At 2333 [CDT] on 10/11/09, LaSalle Unit 2 exceeded the 2 gpm increase in unidentified leakage within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period of Technical Specification [TS] LCO 3.4.5.d. per required action B.1, unidentified leakage increase was required to be restored to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. At 0333 [CDT] on 10/12/09, TS 3.4.5 required action 8.1 was declared not met, and TS 3.4.5 condition C was entered which requires the unit to be in mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. TS LCO 3.4.5, RCS operational leakage requires the plant to be in mode 3 by 10/12/09 at 1533 [CDT] and mode 4 by 10/13/09 at 1533 [CDT]. The unidentified leakage is currently at 2.3 gpm. Although not physically verified, the source of the leakage is suspected to be from the 2B21-F016, Inboard Main Steam Line drain valve packing. Other primary containment parameters - Drywell Air Temperature, Drywell and Suppression Chamber Pressure, Suppression Pool Average Temperature - remain within TS limits. The licensee expects to enter mode 3 by 1200 CDT on 10/12/09 and mode 4 by 0000 on 10/13/09. The licensee suspects the leakage to be from the Inboard Main Steam Line Drain Valve packing due to an earlier maintenance requiring cycling of that valve. All safety-related systems required for plant shutdown and cooldown are operable. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
LaSalle  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
| Time - Person (Reporting Time:+-3 h-0.125 days <br />-0.0179 weeks <br />-0.00411 months <br />) | |
| Opened: | Dan Coveyou 05:33 Oct 12, 2009 |
| NRC Officer: | Dong Park |
| Last Updated: | Oct 12, 2009 |
| 45426 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (70 %) |
WEEKMONTHYEARENS 532762018-03-22T08:00:00022 March 2018 08:00:00
[Table view]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 Pressure Boundary Leakage ENS 489772013-04-28T02:24:00028 April 2013 02:24:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Plant Shutdown ENS 466052011-02-10T00:04:00010 February 2011 00:04:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage ENS 461712010-08-13T00:52:00013 August 2010 00:52:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Environmental Conditions Resulting in Elevated Ultimate Heat Sink Temperature ENS 454262009-10-12T08:33:00012 October 2009 08:33:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Due to Unidentified Leakage from Rcs 2018-03-22T08:00:00 | |