ENS 48182
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ENS Event | |
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08:18 Aug 12, 2012 | |
Title | Degraded Condition Reported Based On The Discovery Of Pressure Boundary Leakage |
Event Description | Following a planned shutdown to investigate the source of elevated Primary Coolant System (PCS) Unidentified Leakage, the Mode 3 PCS walk-down identified a steam leak on CRD-24, Control Rod Drive Mechanism (CRD), pressure housing. The leak is ~ 1 foot above the CRD to Reactor Head flange. The leak was observed from the Refueling floor deck and appears to be coming from an area of the CRD with no bolted connections. Leakage from this area is unexpected and the mechanism of failure is not understood at this time. Closer examination of the leak is expected to occur in parallel with plant cool-down.
The plant entered T.S. 3.4.14 (PCS Operational Leakage) Condition B. at 0418 EDT hours this morning and this requires the plant to be placed in Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The leakage is considered Pressure Boundary Leakage. Operations is in progress of performing the plant cool-down from Mode 3 to Mode 5. The licensee discovered this condition following a shutdown the morning of 8/12/12 to investigate unidentified primary coolant leakage of about 0.3 gpm that had been recently trending upwards. Plant conditions are currently 400 degrees F with primary system pressure at about 1000 psi. The licensee has notified the NRC Resident Inspect |
Where | |
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Palisades Michigan (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+2.78 h0.116 days <br />0.0165 weeks <br />0.00381 months <br />) | |
Opened: | Todd Mulford 11:05 Aug 12, 2012 |
NRC Officer: | Bill Huffman |
Last Updated: | Aug 12, 2012 |
48182 - NRC Website
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Unit 1 | |
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Reactor critical | Not Critical |
Scram | No |
Before | Hot Standby (0 %) |
After | Hot Standby (0 %) |
WEEKMONTHYEARENS 548972020-09-11T23:30:00011 September 2020 23:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Degraded Condition ENS 537492018-11-21T05:00:00021 November 2018 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Identified During Surface Inspection of Reactor Head Nozzle Penetration ENS 537342018-11-11T04:00:00011 November 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Indication During Ultrasonic Inspection of Reactor Head Nozzle Penetration ENS 537332018-11-10T05:00:00010 November 2018 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Boric Acid Identified on Reactor Vessel Head Penetration ENS 527222017-05-02T13:28:0002 May 2017 13:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Failed Ultrasonic Testing of Weld ENS 497962014-02-05T18:00:0005 February 2014 18:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Pressurizer Nozzle Weld During Testing ENS 497732014-01-29T14:00:00029 January 2014 14:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Indications Identified on Control Rod Drive Mechanism Housings ENS 481822012-08-12T08:18:00012 August 2012 08:18:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Reported Based on the Discovery of Pressure Boundary Leakage ENS 411282004-10-16T21:30:00016 October 2004 21:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Vessel Head Nozzle Cracking 2020-09-11T23:30:00 [Table view] | |
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