Junk plant Browns Ferry: Reactor Protection Sytem Going Cracy On Us

Sounds like a special inspection. It is a disgrace starting up a reactor in this runaway condition.

The pre startup testing is supposed to catch this.

Back to the bad old days???

Facility: BROWNS FERRY Region: 2 State: AL Unit: [ ] [2] [ ] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: MARK MOEBES HQ OPS Officer: BETHANY CECERE	Notification Date: 03/29/2017 Notification Time: 23:36 [ET] Event Date: 03/29/2017 Event Time: 18:44 [CDT] Last Update Date: 03/29/2017
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION	Person (Organization): EUGENE GUTHRIE (R2DO)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
2	M/R	Y	1	Startup	0	Hot Shutdown

Event Text

MANUAL SCRAM INITIATED DURING STARTUP "At 1844 CDT on 3/29/2017, Unit 2 initiated a manual scram due to multiple rods inserting. "At 1842 during Unit 2 start-up, Intermediate Range Monitor (IRM) 'G' drifted low. The operator adjusted the range down one position with no immediate reaction. At 1844, a spike on IRM 'G' caused a half scram on Reactor Protection System (RPS) 'A' trip system. The half scram was being reset after evaluating no trip condition was present. As the operator reset groups 2 and 3, a trip signal from IRM 'F' was received on the RPS 'B' trip system, resulting in rod insertion for groups 1 and 4. When the operator identified multiple rods inserting, the actions of procedure 2-AOI-100-1 were followed and a manual scram was inserted. Investigation is ongoing. "All safety systems remained in standby readiness configuration. No Emergency Core Cooling System (ECCS) or Reactor Core Isolation Cooling (RCIC) reactor water level initiation set points were reached. Primary Containment Isolations Systems did not receive an actuation signal and performed as designed. "This event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) 'any event or condition that results in actuation of the RPS when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' It is also reportable within 8 hours per 10 CFR 50.72(b)(3)(iv)(A) 'any event or condition that results in valid actuation of systems listed in paragraph (b)(3)(iv)(B) Reactor Protection System(RPS) including reactor scram and reactor trip'. This event requires an LER within 60 days per 10 CFR 50.73(a)(2)(iv)(A). "The NRC Resident Inspector has been notified."