ENS 46094
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ENS Event | |
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23:34 Jul 14, 2010 | |
Title | Tech Spec Shutdown Due to Through Wall Flaws in S/G Sample Line, Secondary Side |
Event Description | At 1834 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97837e-4 months <br /> on 7/14/10, the Unit 1 'C' Reactor Coolant Loop was declared inoperable due to small unisolable leaks on the 'C' Steam Generator secondary side surface sample line. Two small through-wall flaws were identified in the piping upstream of 1 -SS-217, 'C' Steam Generator surface sample line manual isolation valve. The piping is Class 2 and the non-conforming condition could not be evaluated with the steam generator pressurized. Based on the condition of the piping and the inability to evaluate the flaw, the 'C' Steam Generator was declared inoperable per Technical Requirements Manual 3.4.6, ASME Code Class 1, 2 and 3 Components. Subsequently, Technical Specification 3.4.4 was entered to place Unit 1 in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
At 1934 hours0.0224 days <br />0.537 hours <br />0.0032 weeks <br />7.35887e-4 months <br /> on 7/14/10, North Anna Unit 1 initiated a shutdown in accordance with Technical Specification 3.4.4. The unit will be shutdown and the line will be evaluated and repaired. The licensee is presently at 82% power and coasting down in power. All safety systems are fully operable. The licensee has notified the NRC Resident Inspector.
North Anna Unit 1 entered mode 3 at 2353 hrs. There were no complications during shutdown. One source range monitor failed downscale low. The other source range monitor is operating correctly. The failure of this source range monitor did not affect shutdown capabilities. Notified R2DO (Seymour). |
Where | |
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North Anna Virginia (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
Time - Person (Reporting Time:+-3.68 h-0.153 days <br />-0.0219 weeks <br />-0.00504 months <br />) | |
Opened: | Page Kemp 19:53 Jul 14, 2010 |
NRC Officer: | John Knoke |
Last Updated: | Jul 15, 2010 |
46094 - NRC Website | |
Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (82 %) |
WEEKMONTHYEARENS 546522020-04-09T05:00:0009 April 2020 05:00:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Reactor Coolant System Pressure Boundary Leakage ENS 521372016-07-30T15:52:00030 July 2016 15:52:00 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 Unisolable Reactor Coolant System Boundary Leakage ENS 507002014-12-23T03:30:00023 December 2014 03:30:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 1 Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage ENS 460942010-07-14T23:34:00014 July 2010 23:34:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Tech Spec Shutdown Due to Through Wall Flaws in S/G Sample Line, Secondary Side ENS 454602009-10-23T20:34:00023 October 2009 20:34:00 Other Unspec Reqmnt, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Due to Excess Letdown Heat Exchanger Tube Leak and After-The-Fact Unusual Event ENS 431952007-02-28T00:47:00028 February 2007 00:47:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Failed Surveillance Testing 2020-04-09T05:00:00 | |
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