ENS 45390
ENS Event | |
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23:50 Sep 29, 2009 | |
Title | Technical Specification Shutdown Due to Unidentified Leakage from Rcs |
Event Description | At 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> CDT, operators initiated a plant shutdown required by Technical Specification 3.4.5, Reactor Coolant System (RCS) Operational Leakage, due to a greater than 2 gpm increase in unidentified leakage within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in MODE 1.
At 1544 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.87492e-4 months <br /> CDT, a control room operator noticed drywell pressure increased from 0.68 to 0.81 psig. At 1552, the drywell cooler differential temperature alarm actuated, drywell cooling HVAC chiller amps increased from 50 amps to 56 amps, and the Fission Product Monitor particulate and iodine indications were trending up. At 1555, operators entered the abnormal coolant leakage procedure and evacuated containment. At 1615, drywell floor drain leakage rate alarm actuated. At 1616, plant entered the 4-hour Technical Specification action to verify the source of the unidentified leakage source is not due to service sensitive type 304 or type 316 austenitic stainless steel. At 1730, operators started a power reduction in an attempt to verify the source of the leak. At 1850, the leakage source could not be verified to not be service sensitive stainless steel; entered TS Required Action 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 />. A reactor shutdown has been initiated. At 1930 floor drain leakage (unidentified leakage) was 3.3 gpm and stable. MODE 3 is expected to be entered by 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> on 9/30/09. The licensee has notified the NRC Resident Inspector. |
Where | |
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Clinton ![]() Illinois (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
LER: | 05000461/LER-2009-004 |
Time - Person (Reporting Time:+-3.07 h-0.128 days <br />-0.0183 weeks <br />-0.00421 months <br />) | |
Opened: | Jim Peterson 20:46 Sep 29, 2009 |
NRC Officer: | John Knoke |
Last Updated: | Sep 29, 2009 |
45390 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (97 %) |
After | Power Operation (53 %) |
WEEKMONTHYEARENS 453902009-09-29T23:50:00029 September 2009 23:50:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Due to Unidentified Leakage from Rcs ENS 434302007-06-19T11:35:00019 June 2007 11:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Tech Spec Required Shutdown Due to Instrument Line Steam Leak 2009-09-29T23:50:00 | |