ENS 42549
ENS Event | |
|---|---|
02:30 May 4, 2006 | |
| Title | Rcic Declared Inoperable Due to Degraded Flow Instrument |
| Event Description | The licensee indicated the Reactor Core Isolation Cooling (RCIC) has been made inoperable by a degraded flow instrument. The deficiency will prevent RCIC from achieving its design flow of 410 gpm. The degraded condition limits the flow to 360 gpm. This condition put the licensee into LCO 3.5.3.A. To exit the LCO an I&C tech will need to perform a venting operation on the flow transmitter.
The licensee will notify the NRC Resident Inspector.
The licensee provided the following additional information: EVENT NOTIFICATION RETRACTION At 0607 on 05/04/2006 the James A. FitzPatrick Nuclear Power Plant notified the NRC Operations Center that, 'Reactor Core Isolation Cooling (RCIC) System has been made inoperable by a degraded flow instrument. The deficiency will prevent RCIC from achieving its design flow rate of 410 gpm. Estimated flow rate in the current condition is 360 gpm.' This notification was made pursuant to 10 CFR 50.72(b)(3)(ii)(A) 'Any event or condition that results in: (A) The conditions of the nuclear power plant, including its principal safety barriers, being seriously degraded;' Subsequent review of this event determined that the degradation of the RCIC System did not result in any of the plant's principal safety barriers (i.e., fuel cladding, reactor coolant pressure boundary, or the primary containment integrity) being degraded therefore, criterion 10 CFR 50.72(b)(3)(ii)(A) is not applicable to the event. Additionally the guidance contained in Regulatory Issue Summary (RIS) 2001-14, 'Position on Reportability Requirements for Reactor Core Isolation Cooling System Failure' was reviewed and it was confirmed that the RCIC System is not credited in the UFSAR for mitigating the consequences of a rod ejection accident, so the 10 CFR 50.72(b)(3)(v)(D) accident mitigation criterion does not apply. Consequently this notification is being retracted. The licensee informed the NRC Resident Inspector. Notified R1DO (Bellamy). |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+3.62 h0.151 days <br />0.0215 weeks <br />0.00496 months <br />) | |
| Opened: | John Walkowiak 06:07 May 4, 2006 |
| NRC Officer: | John Knoke |
| Last Updated: | May 4, 2006 |
| 42549 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 525032017-01-22T19:00:00022 January 2017 19:00:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Weld Defect Found During a Shutdown Inspection ENS 524902017-01-14T11:13:00014 January 2017 11:13:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Through-Wall Leak ENS 505092014-10-04T18:08:0004 October 2014 18:08:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Leak Rate Exceeds Acceptance Criteria ENS 445162008-09-23T19:00:00023 September 2008 19:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Recirc Nozzle Weld Axial Crack ENS 425492006-05-04T02:30:0004 May 2006 02:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcic Declared Inoperable Due to Degraded Flow Instrument ENS 418152005-06-30T23:29:00030 June 2005 23:29:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Inoperable Due to Small Crack in Torus 2017-01-22T19:00:00 | |