Event Notification Report for June 28, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/27/2024 - 06/28/2024
EVENT NUMBERS
57199
57199
Power Reactor
Event Number: 57199
Facility: Monticello
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: Brian Olson
HQ OPS Officer: Robert A. Thompson
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: Brian Olson
HQ OPS Officer: Robert A. Thompson
Notification Date: 06/28/2024
Notification Time: 16:28 [ET]
Event Date: 06/28/2024
Event Time: 01:10 [CDT]
Last Update Date: 07/01/2024
Notification Time: 16:28 [ET]
Event Date: 06/28/2024
Event Time: 01:10 [CDT]
Last Update Date: 07/01/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(B) - Pot RHR Inop 50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(B) - Pot RHR Inop 50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Skokowski, Richard (R3DO)
Skokowski, Richard (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
BOTH DIVISIONS OF LPCI INOPERABLE
The following information was provided by the licensee via email:
"This condition is being reported in accordance with 10 CFR50.72(b)(3)(v) as a condition that could have prevented fulfillment of a safety function. On 6/27/2024 at 2158 CDT, [technical specification] TS 3.5.1 condition 'D' (both divisions of [low pressure coolant injection] LPCI inoperable) was entered for surveillance testing. On 6/28/2024 at 0110 CDT, MO-2012 [residual heat removal] RHR Division 1 LPCI injection outboard valve was attempted to be cycled. It was discovered to be inoperable resulting in an inability to exit TS 3.5.1 'D'. Initial review of this condition for immediate reportability under 50.72(b)(3)(v) event or a condition that could have prevented fulfillment of a safety function, concluded the condition was not reportable based on the operability of other emergency core cooling systems (ECCS). Specifically, core spray and high pressure coolant injection were both operable to perform the function of emergency core cooling. Subsequent reviews determined that the reportability decision under 50.72(b)(3)(v) as an event or condition that could have prevented fulfillment of a safety function should be based on the safety function at the LPCI system level, rather than at the ECCS system level. The decision to report the inoperability of LPCI under 50.72(b)(3)(v) was made at 1030 CDT on 6/28/2024. The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"This condition is being reported in accordance with 10 CFR50.72(b)(3)(v) as a condition that could have prevented fulfillment of a safety function. On 6/27/2024 at 2158 CDT, [technical specification] TS 3.5.1 condition 'D' (both divisions of [low pressure coolant injection] LPCI inoperable) was entered for surveillance testing. On 6/28/2024 at 0110 CDT, MO-2012 [residual heat removal] RHR Division 1 LPCI injection outboard valve was attempted to be cycled. It was discovered to be inoperable resulting in an inability to exit TS 3.5.1 'D'. Initial review of this condition for immediate reportability under 50.72(b)(3)(v) event or a condition that could have prevented fulfillment of a safety function, concluded the condition was not reportable based on the operability of other emergency core cooling systems (ECCS). Specifically, core spray and high pressure coolant injection were both operable to perform the function of emergency core cooling. Subsequent reviews determined that the reportability decision under 50.72(b)(3)(v) as an event or condition that could have prevented fulfillment of a safety function should be based on the safety function at the LPCI system level, rather than at the ECCS system level. The decision to report the inoperability of LPCI under 50.72(b)(3)(v) was made at 1030 CDT on 6/28/2024. The NRC Resident Inspector has been notified."