ENS 56957: Difference between revisions

v t e ENS Event
18:22 Feb 9, 2024
Title	Unanalyzed Condition - Inadequate Fuses for Fuel Pool Cooling
Event Description	The following information was provided by the licensee via email: On 2/9/24 at 1322 EST, it was determined that the unit was in an unanalyzed condition. A review of DC feeder circuit protection schemes identified a circuit for the fuel pool cooling system is uncoordinated due to inadequate fuse sizing. This results in a concern that postulated fire damage in one area could cause a short circuit without adequate protection, leading to the unavailability of equipment credited for in 10 CFR 50 Appendix R, Fire Safe Shutdown. This condition is not bounded by existing design and licensing documents; however, it poses no impact to the health and safety of the public or plant personnel. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). The postulated event affects the following fire zones: fire areas 6S and 6N (within the Unit 2 reactor building). Compensatory actions for affected fire areas have been implemented. An extent of condition review is being performed. The NRC Senior Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: Fire watches have been established in the affected areas. These will be maintained until the protection scheme is revised. * * UPDATE ON 03/08/24 FROM PAUL BOKUS TO TOM HERRITY * * * The following updated information was provided by the licensee via email and phone call: On 03/08/24 at 1418, extent of condition reviews identified circuit(s) in the Units 2 and 3 Reactor Protection Systems (RPS) which are also uncoordinated due to improper fuse sizing. These circuits are not bounded by existing design and licensing documents for 10 CFR 50 Appendix R Fire Safe Shutdown and, therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). This event poses no impact to the health and safety of the public or plant personnel. The postulated event affects the following fire areas: 32, 33, 38 and 39 (Units 2 and 3 Switchgear Rooms). In accordance with procedural requirements, compensatory actions for the affected fire areas have been implemented and will remain until the condition is resolved. The NRC Senior Resident Inspector has been notified. Notified R1DO (Arner) * * UPDATE ON 3/13/2024 AT 1538 FROM TROY RALSTON TO SAM COLVARD * * * On March 13, 2024, at 1350 EDT, extent of condition reviews identified a circuit in the Unit 2 reactor protection system (RPS) which is also uncoordinated due to improper fuse sizing. This circuit is not bounded by existing design and licensing documents for 10 CFR 50, Appendix R, Fire Safe Shutdown, therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). This event poses no impact to the health and safety of the public or plant personnel. The postulated event affects fire area 57 (Switchgear Corridor, common to Units 2 and 3). In accordance with procedural requirements, compensatory actions for the affected fire areas have been implemented and will remain until the condition is resolved. Additionally, it was previously reported that fire area 6N contained a circuit which was not bounded by the Fire Safe Shutdown analysis; however, after further review it has been determined that compliance is maintained in this fire area and is therefore retracted from the scope of this report. The NRC Senior Resident Inspector has been notified. Notified R1DO (Jackson)

ENS 56957 +/-
Where
Peach Bottom Pennsylvania (NRC Region 1)
Reporting

10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition
Time - Person (Reporting Time:+-3.25 h-0.135 days <br />-0.0193 weeks <br />-0.00445 months <br />)
Opened:	Bill Linell 15:07 Feb 9, 2024
NRC Officer:	Thomas Herrity
Last Updated:	Mar 13, 2024
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v • d • e

v t e Emergency Notification System
Peach Bottom with 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition
WEEKMONTHYEAR2024-02-09T18:22:00 [Table view]
[ENS list for Peach Bottom]

@@ Line 15: / Line 15: @@
 | NRC officer = Thomas Herrity
 | event date = 02/09/2024 13:22 EST
-| last update date = 03/08/2024
+| last update date = 03/13/2024
 | title = Unanalyzed Condition - Inadequate Fuses for Fuel Pool Cooling
 | event text = The following information was provided by the licensee via email:
@@ Line 28: / Line 28: @@
 The postulated event affects the following fire areas: 32, 33, 38 and 39 (Units 2 and 3 Switchgear Rooms). In accordance with procedural requirements, compensatory actions for the affected fire areas have been implemented and will remain until the condition is resolved.
 The NRC Senior Resident Inspector has been notified.
-Notified R1DO(Arner)
+Notified R1DO (Arner)
-| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2024/20240311en.html#en56957
+* * * UPDATE ON 3/13/2024 AT 1538 FROM TROY RALSTON TO SAM COLVARD * * *
+On March 13, 2024, at 1350 EDT, extent of condition reviews identified a circuit in the Unit 2 reactor protection system (RPS) which is also uncoordinated due to improper fuse sizing. This circuit is not bounded by existing design and licensing documents for 10 CFR 50, Appendix R, Fire Safe Shutdown, therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). This event poses no impact to the health and safety of the public or plant personnel.
+The postulated event affects fire area 57 (Switchgear Corridor, common to Units 2 and 3). In accordance with procedural requirements, compensatory actions for the affected fire areas have been implemented and will remain until the condition is resolved.
+Additionally, it was previously reported that fire area 6N contained a circuit which was not bounded by the Fire Safe Shutdown analysis; however, after further review it has been determined that compliance is maintained in this fire area and is therefore retracted from the scope of this report.
+The NRC Senior Resident Inspector has been notified.
+Notified R1DO (Jackson)
+| URL = https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2024/20240314en.html#en56957
 }}{{unit info
 | Unit = 2

v t e Unit 2
GE-4
Reactor critical	Critical
Scram	No
Before	Power Operation (100 %)
After	Power Operation (100 %)

ENS 56957: Difference between revisions

Revision as of 07:30, 14 March 2024

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ENS 56957: Difference between revisions

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