Tuesday, October 12, 2021

Susquehanna - AUTOMATIC REACTOR SCRAM AFTER MAIN TURBINE TRIP

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
10/08/2021 - 10/12/2021
 
   55514
Power Reactor
Event Number: 55514
Facility: Susquehanna
Region: 1     State: PA
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Charles Yoder
HQ OPS Officer: Lloyd Desotell
Notification Date: 10/11/2021
Notification Time: 17:05 [ET]
Event Date: 10/11/2021
Event Time: 13:21 [EDT]
Last Update Date: 10/11/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(A) - Eccs Injection
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
CARFANG, ERIN (R1)

Power Reactor Unit Info
UnitSCRAM CodeRX CritInitial PWRInitial RX ModeCurrent PWRCurrent RX Mode
2A/RY95Power Operation0Hot Standby

Event Text
AUTOMATIC REACTOR SCRAM AFTER MAIN TURBINE TRIP

"At 1321 EDT on October 11, 2021, Susquehanna Steam Electric Station Unit 2 reactor automatically scrammed due to a trip of the Main Turbine.

"Unit 2 reactor was being operated at approximately 95 percent RTP [rated thermal power] with no evolutions in progress. The Control Room received indication of a Main Turbine trip with both divisions of RPS [Reactor Protection System] actuated and all control rods inserted. Turbine bypass valves opened automatically to control reactor pressure and subsequently failed open causing the reactor to depressurize. When reactor pressure reached approximately 560 psig, the operations crew manually closed the Main Steam Isolation Valves (MISVs) to stop the depressurization. Reactor water level lowered to -31 inches causing Level 3 (+13 inches) isolations. No [automatic] ECCS [Emergency Core Cooling System] actuations occurred. HPCI [High Pressure Coolant Injection] and RCIC [Reactor Core Isolation Cooling] were manually initiated to control reactor water level. The Operations crew subsequently maintained reactor water level at the normal operating band using RCIC and reactor pressure was controlled with HPCI in pressure control mode and main steam line drains. The Reactor Recirculation Pumps tripped as designed on EOC-RPT [end of cycle recirculation pump trip].

"The reactor is currently stable in Mode 3. An investigation into the cause of the turbine trip is underway.

"The NRC Resident Inspector was notified. A voluntary notification to PEMA will be made.

"This event requires a 4 hour ENS notification in accordance with 10 CFR 50.72(b)(2)(iv)(A), 10 CFR 50.72(b)(2)(iv)(B) and an 8 hour ENS notification in accordance with 10 CFR 50.72(b)(3)(iv)(A)."
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Page Last Reviewed/Updated Tuesday, October 12, 2021

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