ENS 41657
ENS Event | |
|---|---|
10:11 May 2, 2005 | |
| Title | Technical Specification Required Shutdown - Reactor Vessel Level Instrumentation |
| Event Description | On 5/1/05 at 19:16, the plant entered MODE 2 and began a reactor startup. After withdrawing control rods, but prior to criticality, perturbations were noticed on reactor vessel level indications and control rod withdrawal was halted.
At 22:32 control rods were inserted in reverse order to maintain the reactor subcritical. At that time, level instrumentation associated with the 'A' level reference leg was declared inoperable. All control rods were inserted at 23:02 in Mode 2. At 23:32 on 5/1/05 a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shutdown statement was entered due to the inoperable level instrumentation. Efforts were underway to troubleshoot and restore the level Instrumentation. On 5/2/05 at 06:11 the reactor mode switch was placed in shutdown - level instrumentation will not be restored within the time allowed by Technical Specifications. Instrument fill and vent procedures are being implemented at this time. The plant expects to enter Mode 2 later today. Technical specification 3.3.6.1 requires restoration within one hour, shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This reference leg level affects both the wide and narrow range level instruments and feed into the Reactor Protective System, Emergency Core Cooling System Instrumentation, and Isolation Instrumentation systems. The licensee notified the NRC Resident Inspector.
Update to Event Notification (EN 41657) Retraction: A 4-hour notification was made on May 2, 2005, in accordance with 10CFR50.72(b)(2)(i), for a shutdown required by Technical Specifications. The report was made due to inserting all withdrawn control rods during a startup, prior to criticality, for Technical Specification 3.3.6.1 required actions. Technical Specification 3.3.6.1 was entered as a result of level perturbations determined to have been caused by reference leg keep-fill system operation when the reactor pressure vessel (RPV) was under vacuum conditions with minor component compression fitting leaks. Actions were taken to fix the minor leaks in the reference leg keep-fill panel. Additionally, the reference leg keep-fill system was removed from service until the RPV was pressurized. It was subsequently determined that since the reactor had not yet been taken critical, the reactor was in a shutdown condition. Per NUREG-1022, rev 2, section 3.2.1 'Plant Shutdown Required by Technical Specifications,' the 'initiation of any nuclear plant shutdown' does not include mode changes required by TS if initiated after the plant is already in a shutdown condition. Since the plant remained in a shutdown condition, this issue is not reportable. Since the condition is not reportable. EN 41657 is retracted. The licensee notified the NRC Resident Inspector. The R3DO (Burgess) has been notified. |
| Where | |
|---|---|
Perry  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
| Time - Person (Reporting Time:+-0.47 h-0.0196 days <br />-0.0028 weeks <br />-6.43806e-4 months <br />) | |
| Opened: | Steven Benedict 09:43 May 2, 2005 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Jun 3, 2005 |
| 41657 - NRC Website
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WEEKMONTHYEARENS 571362024-05-23T08:00:00023 May 2024 08:00:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 530002017-10-04T06:50:0004 October 2017 06:50:00 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, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Perry Commenced Technical Specification Required Shutdown ENS 516792016-01-24T02:22:00024 January 2016 02:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Ts Required Shutdown Due to Unidentified Leakage in Drywell ENS 498042014-02-07T11:00:0007 February 2014 11:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Required by Technical Specifications Due to Containment Isolation Valve Over Leak Rate Limit ENS 491212013-06-16T04:00:00016 June 2013 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 Shutdown Due to Small Reactor Coolant Leak on a Recirculation Flow Control Valve Vent Line ENS 473122011-10-02T05:00:0002 October 2011 05:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shutdown Required by Technical Specifications Due to Transformer Fault ENS 459182010-05-12T03:18:00012 May 2010 03:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Manual Reactor Scram Due to Loss of Control Rod Drive Charging Water Header Pumps ENS 454342009-10-15T16:25:00015 October 2009 16:25:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unit Commenced Shutdown Due to Inoperable Division 2 Emergency Service Water System ENS 416572005-05-02T10:11:0002 May 2005 10:11:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown - Reactor Vessel Level Instrumentation ENS 410852004-10-02T19:00:0002 October 2004 19:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Reactor Power Being Reduced Due to Entering Ts 3.0.3 Because of Inopeable Recirc Vent System ENS 407672004-05-21T20:00:00021 May 2004 20:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown 2024-05-23T08:00:00 | |