ENS 46557
ENS Event | |
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16:10 Jan 20, 2011 | |
Title | Technical Specification Required Shutdown |
Event Description | The 1B and 2B trains of Nuclear Service Water Systems (Raw Water Nuclear RN) were declared inoperable on 1/18/11 at 0423 EST due to fouling of the respective suction strainers when aligned to the Standby Nuclear Service Water Pond (SNSWP).
Tech. Spec. 3.0.3 was entered at 1110 EST on 1/20/11 due to the lack of reasonable assurance of operability pertaining to 1A and 2A RN trains in the event of a potential realignment to the SNSWP due to a seismic event. The licensee plans to reduce power and place both Units in Mode 5. Unit 1 has been reduced to 90% and Unit 2 is holding at 100% and will begin reducing power later. The fouling is being caused by fish being sucked into the RN train suction strainers. The licensee has been back-flushing the strainers to clear the fouling. The pond was chemically treated approximately 1 year ago to eliminate the fish. The licensee notified the NRC Resident Inspector.
McGuire Units 1 & 2 entered Technical Specification 3.0.3 with a requirement to be in Mode 5 in 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. A Notification of Enforcement Discretion was verbally approved by the Nuclear Regulatory Commission on 1/20/11 at 2336 EST, therefore both Unit 1 & 2 will remain in Mode 3. The licensee notified the NRC Resident Inspector. Notified R2DO (Sykes), NRR EO (Thomas), and IRD MOC (Gott)
This is an amendment to Event Notification #46557 to include the following 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> non-emergency notifications previously omitted by the NRC from the event report: 50.72(b)(3)(v)(A) POT UNABLE TO SAFE S/D 50.72(b)(3)(v)(B) POT RHR INOP 50.72(b)(3)(v)(D) ACCIDENT MITIGATION The licensee will notify the NRC Resident Inspector. |
Where | |
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Mcguire ![]() North Carolina (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
Time - Person (Reporting Time:+-3.4 h-0.142 days <br />-0.0202 weeks <br />-0.00466 months <br />) | |
Opened: | Teresa Putnam 12:46 Jan 20, 2011 |
NRC Officer: | John Shoemaker |
Last Updated: | Jan 24, 2011 |
46557 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (90 %) |
Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
McGuire ![]() | |
WEEKMONTHYEARENS 559552022-06-22T02:40:00022 June 2022 02:40:00
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