ENS 48763
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ENS Event | |
|---|---|
18:45 Feb 17, 2013 | |
| Title | Pressure Boundary Leakage Discovered During Containment Walkdown |
| Event Description | CCNPP [Calvert Cliffs Nuclear Power Plant] U-2 discovered during the Mode 3 NOP/NOT containment walkdown that 2CV-100F Pressurizer Spray valve had a pin hole leak on the leak-off welded cap. This indicates that the bellows has a leak and in addition, the packing is leaking, pressurizing the leak-off line thus the leak-off line is the pressure boundary making this pressure boundary leakage. Technical Specification 3.4.13 [Action B] requires the unit be in mode 3 in 6 hrs. Unit was in mode 3 when discovered and unit will be placed in mode 5 within 36 hrs. Currently, the plant is at 400 degrees and 950 PSIA.
The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Calvert Cliffs  Maryland (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-2.9 h-0.121 days <br />-0.0173 weeks <br />-0.00397 months <br />) | |
| Opened: | James Groom 15:51 Feb 17, 2013 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Feb 17, 2013 |
| 48763 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
Calvert Cliffs with 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 551222021-03-04T08:23:0004 March 2021 08:23:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Notification of Degraded Condition ENS 543252019-10-11T17:00:00011 October 2019 17:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Initiated ENS 517472016-02-20T08:30:00020 February 2016 08:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Pressurizer Safety Relief Valve Weld ENS 503072014-07-25T03:15:00025 July 2014 03:15:00 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 Reactor Coolant System Pressure Boundary Leakage ENS 493232013-09-05T17:14:0005 September 2013 17:14:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Failure to Align Control Element Assembly During Testing ENS 487632013-02-17T18:45:00017 February 2013 18:45:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Discovered During Containment Walkdown ENS 481832012-08-12T16:34:00012 August 2012 16:34:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Due to Fully Inserted Control Rod While Operating ENS 481242012-07-21T16:10:00021 July 2012 16:10:00 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 Rcs Pressure Boundary Instrument Line Leakage ENS 481162012-07-17T04:00:00017 July 2012 04:00:00 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 Small Rcs Pressure Boundary Instrument Line Leak ENS 473162011-10-03T14:35:0003 October 2011 14:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification (Ts) Required Shutdown Due to Both 'A' Train Edg'S Inoperable ENS 466232011-02-18T05:51:00018 February 2011 05:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Inactive Leak Identified on Presurizer Heater Well ENS 457372010-03-02T12:30:0002 March 2010 12:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressurizer Safety Nozzle Weld Degradation ENS 457192010-02-23T20:12:00023 February 2010 20:12:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Weld Leak Due to Vibrating Valve Attachment Wire ENS 440062008-02-25T06:40:00025 February 2008 06:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Leakage on a Pressurizer Heater Sleeve ENS 424842006-04-09T03:42:0009 April 2006 03:42:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Control Element Assembly Stuck During Physics Testing ENS 414482005-02-27T20:00:00027 February 2005 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Reactor Coolant Boundary Weld ENS 414452005-02-26T20:30:00026 February 2005 20:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Reactor Coolant Boundary Weld 2021-03-04T08:23:00 | |
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