ENS 42194

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v t e ENS Event
20:44 Dec 9, 2005
Title	Rcs Pressure Boundary Leakage Identified
Event Description	At 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br /> on 12/5/05, Unit 2 entered abnormal operating procedure 18004-C 'RCS Leakage' due to increasing containment atmospheric radiation levels as identified on 2RE2562A. Per procedure, an RCS leak rate determination was commenced and completed as of 1629 hours0.0189 days <br />0.453 hours <br />0.00269 weeks <br />6.198345e-4 months <br />, 12/8/05 (identified = 0.032gpm, unidentified = 0.254gpm, total = 0.286gpm). While making preparations for a containment entry for leakage inspection, a second leak rate [determination] was completed at 2020 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br />, 12/8/05 (identified = 0.070gpm, unidentified = 0.267gpm, total = 0.337gpm). At 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br />, 12/8/05, the team performing the containment leak inspection reported no leakage identified outside the bioshield. Another leak rate [determination] was completed at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br />, 12/9/05, the team performing the containment leak inspection reported that by using a robotic camera, water was observed coming down the inside wall of the bioshield in the area of loop 2. At 0433 hours0.00501 days <br />0.12 hours <br />7.159392e-4 weeks <br />1.647565e-4 months <br />, 12/9/05, a shutdown of Unit 2 was initiated to allow further investigation / repair of the RCS leak inside containment. Unit 2 was placed in Mode 3 at 1313 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />4.995965e-4 months <br />, 12/9/05. At 1544 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.87492e-4 months <br />, 12/9/05, the containment leak inspection team reported pressure boundary leakage at a welded connection where a 3/4 inch bypass line is welded to the RCS loop upstream of the RHR loop suction valve 2HV8701B. [Plant Vogtle personnel are] presently preparing to commence shutdown to Mode 5 for repair of the leak. Technical specification 3.4.14 applies and requires no pressure boundary leakage. The plant is currently removing decay heat by steaming from the steam generators through the steam dump valves to the condenser. All safety related electrical buses are available. Emergency diesel generators are available and in standby. The licensee notified the NRC Resident Inspector. * * UPDATE RECEIVED BY PHONE ON 12/12/2005 AT 13:50 FROM JIM POLICKOSKI TO ABRAMOVITZ * * * Two corrections were communicated. The date of the initial event was "at 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br /> on 12/8/05." The technical specification quoted is changed to 3.4.13. Notified the R2DO (Henson).

ENS 42194 +/-
Where
Vogtle Georgia (NRC Region 2)
Reporting

10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown
Time - Person (Reporting Time:+-2.55 h-0.106 days <br />-0.0152 weeks <br />-0.00349 months <br />)
Opened:	Steve Phillips 18:11 Dec 9, 2005
NRC Officer:	Pete Snyder
Last Updated:	Dec 12, 2005
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v • d • e

v t e Emergency Notification System
Vogtle with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown
WEEKMONTHYEAR2016-12-10T01:42:00 [Table view]
[ENS list for Vogtle]

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