ENS 52724
ENS Event | |
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21:00 May 2, 2017 | |
Title | Unanalyzed Condition for Combustion Turbine Generator Configuration |
Event Description | On May 2, 2017, while performing a past operability review associated with Combustion Turbine Generator (CTG) 11-1, it was determined that a past configuration of CTG 11-1 could not have assured all of the applicable Appendix R success criteria under all of the postulated scenarios described in the Updated Final Safety Analysis Report [UFSAR]. From November 21, 2016 until March 18, 2017 when Mode 4 was entered, CTG 11-1 was in a configuration where it could not be started from the dedicated shutdown panel, although it could be started locally. One of the specific scenarios for Appendix R in the UFSAR credits CTG 11-1 to support a safe shutdown based on an assumed time required to start CTG 11-1 and then provide flow to the reactor pressure vessel using the Standby Feedwater System. During the time period where CTG 11-1 could only be started locally, this assumed time would have been exceeded. Therefore, this event is being reported as an 'unanalyzed condition that significantly affects plant safety' under 50.72(b)(3)(ii)(B). At the time of discovery, CTG 11-1 was fully operable and the described condition had already been corrected.
The NRC Resident Inspector has been notified.
The purpose of this notification is to retract a previous report made on May 2, 2017 (EN 52724) under 10 CFR 50.72(b)(3)(ii)(B). The notification to the NRC involved an event where Combustion Turbine Generator (CTG) 11-1 could only be started locally such that required operator actions during an Appendix R safe shutdown scenario could be delayed. Subsequent to the initial notification, the event, additional site documentation, and the NRC guidance in NUREG-1022 pertaining to 10 CFR 50.72(b)(3)(ii)(B) were reviewed further. lt was verified that Fermi 2 procedures contained actions to ensure Appendix R safe shutdown capability under the plant conditions during the relevant time period. A time validation study was performed [May 9, 2017] which verified that the operator actions could have been completed within the time described in the Updated Final Safety Analysis Report (UFSAR) for initiating Standby Feedwater flow to the reactor pressure vessel. In addition, a review of the supporting design calculation identified margin in the required time described in the UFSAR. Based on this information, the condition of CTG 11-1 during the time period from November 21, 2016 until March 18, 2017 would not have prevented compliance with the Appendix R safe shutdown requirements. Under these circumstances, the event does not represent an 'unanalyzed condition that significantly affects plant safety' under 10 CFR 50.72(b)(3)(ii)(B) per the guidance in NUREG-1022. Therefore, EN 52724 can be retracted and no Licensee Event Report (LER) under 10 CFR 50.73(a)(2)(ii)(B) is required to be submitted. The licensee has notified the NRC Resident Inspector. Notified R3DO (Cameron). |
Where | |
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Fermi Michigan (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
Time - Person (Reporting Time:+-2.43 h-0.101 days <br />-0.0145 weeks <br />-0.00333 months <br />) | |
Opened: | Kelley Belenky 18:34 May 2, 2017 |
NRC Officer: | Bethany Cecere |
Last Updated: | May 19, 2017 |
52724 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
WEEKMONTHYEARENS 552312021-05-03T13:30:0003 May 2021 13:30:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition ENS 537122018-11-01T04:00:0001 November 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition En Revision Imported Date 12/31/2018 ENS 536742018-10-19T04:00:00019 October 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Low Pressure Core Injection Pumps Incapable of Automatic Startup ENS 527242017-05-02T21:00:0002 May 2017 21:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for Combustion Turbine Generator Configuration ENS 523422016-11-02T14:34:0002 November 2016 14:34:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition for Control Rod Drop Accident at Low Power ENS 522142016-08-31T23:50:00031 August 2016 23:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition with a Potential Tornado ENS 522022016-08-25T20:29:00025 August 2016 20:29:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Mechanical Draft Cooling Tower Declared Inoperable ENS 514402015-10-02T12:25:0002 October 2015 12:25:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Loose Safety Relief Valve Discharge Flange Bolts ENS 422242005-12-23T03:25:00023 December 2005 03:25:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Eecw Temperature Control Valve Not Fully Open ENS 418472005-07-18T02:31:00018 July 2005 02:31:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition of Maintenance Bus Tie Breakers ENS 418162005-06-30T23:31:00030 June 2005 23:31:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Related to the Standby Feedwater Pumps and Control Circuits ENS 417142005-05-18T22:50:00018 May 2005 22:50:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Identification of Design and Operating Procedure Deficiencies Related to Appendix R Events ENS 415512005-03-30T21:00:00030 March 2005 21:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Identification of Design and Operating Procedure Deficiencies 2021-05-03T13:30:00 | |