| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/09/2018 - 01/10/2018 ** EVENT NUMBERS ** |
 | Non-Power Reactor | Event Number: 53157 | Facility: MASSACHUSETTS INSTITUTE OF TECH
RX Type: 6000 KW TANK RESEARCH HW
Comments:
Region: 0
City: CAMBRIDGE State: MA
County: MIDDLESEX
License #: R-37
Agreement: Y
Docket: 05000020
NRC Notified By: AL QUEIROLO
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/09/2018
Notification Time: 11:01 [ET]
Event Date: 01/08/2018
Event Time: 16:00 [EST]
Last Update Date: 01/09/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
| Person (Organization):
BETH REED (NRR)
PATRICK BOYLE (NRR)
| Event Text TECHNICAL SPECIFICATION VIOLATION
"On January 8, 2018, two in-core experiments were removed from their in-core positions at a time when one of the two minimum required Neutron Flux Level instruments was inoperable.
"This is in violation of Technical Specification No. 3.2.3, Specification No. 2."
The reactor was shutdown for maintenance at the time of the event.
The licensee notified their NRR Project Manager (Boyle). |
| Part 21 | Event Number: 53158 | Rep Org: CURTISS WRIGHT NUCLEAR DIVISION
Licensee: CURTISS WRIGHT NUCLEAR DIVISION
Region: 3
City: CINCINNATI State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TIMOTHY FRANCHUK
HQ OPS Officer: DONALD NORWOOD | Notification Date: 01/09/2018
Notification Time: 15:28 [ET]
Event Date: 10/17/2017
Event Time: [EST]
Last Update Date: 01/09/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
MARK JEFFERS (R3DO)
PART 21/50.55 REACTO (EMAI)
| Event Text PART 21 - FAILURE OF UNDER-VOLTAGE RELEASE MECHANISM
The following is a synopsis of information received via E-mail:
On October 17, 2017, Palisades alerted Curtiss-Wright of the failure of the under-voltage dropout mechanism in a molded case circuit breaker to trip the breaker in an under-voltage condition. The specific component was a Westinghouse / Eaton Cutler Hammer P/N KD2200U18, containing CAT# UVH3LB08, Style 1492D79G24 under-voltage release mechanism (manufactured prior to 1999). Six of these components were supplied to Palisades in 1992.
Findings indicated that the under-voltage release mechanism's failure was a result of a misalignment of the solenoid due to excessive play in the design/manufacturing process which allowed the plunger to miss the target that would cause the breaker to trip in an under-voltage condition. Palisades identified this failure and mentioned two previous failures, one in 1996, and one in 2009.
The under-voltage trip mechanism was redesigned in the 1997-1998 time frame. The new design has not exhibited any reported failures. The observed failure on a 1992 breaker having failed in the installed condition took 50 trials to repeat the failure. Given that the excessive play could be a result of combined tolerances, worn tooling, as well as the design itself, and since the OEM has redesigned this mechanism almost 20 years ago, Curtiss-Wright would recommend end users to conduct their own evaluation to determine if a defect, which could create a substantial safety hazard, exists. |
| Power Reactor | Event Number: 53159 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: RICHARD LANGFORD
HQ OPS Officer: DONALD NORWOOD | Notification Date: 01/09/2018
Notification Time: 23:38 [ET]
Event Date: 01/09/2018
Event Time: 17:59 [CST]
Last Update Date: 01/09/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
FRANK EHRHARDT (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION IDENTIFIED DURING NATIONAL FIRE PROTECTION ASSOCIATION 805 IMPLEMENTATION
"On January 9, 2018, at 1759 CST, during review of NFPA 805 requirements and circuit analysis, it was determined that the NFPA 805 analysis and Fire Safe Shutdown Modeling did not consider all fire-induced failures. As such, a condition could possibly exist during a postulated fire where both safety related electrical trains could be impacted.
"This notification is to report a condition involving the fire safe shutdown analysis. The condition could result in an adverse impact on the ability of operators to respond to a postulated fire in these areas. Therefore, this notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(B), any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.
"Compensatory fire watches have been established in the affected areas."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 53160 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PHIL BALES
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 01/10/2018
Notification Time: 02:13 [ET]
Event Date: 01/09/2018
Event Time: 19:28 [EST]
Last Update Date: 01/10/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
FRANK EHRHARDT (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text BOTH TRAINS OF CONTAINMENT AIR RETURN FANS INOPERABLE
"During normal power operations at 100 percent power on Unit 2, both trains of Containment Air Return Fans (CARF) were declared inoperable at 19:28 [EST] on January 9, 2018 due to a common issue with control power fuses. The fuses potentially could not handle the in-rush current upon re-energizing the circuits. This condition resulted in a loss of a reasonable expectation that the Unit 2 Containment Air Return Fans would meet their design safety function and mitigate an accident. This loss of safety function is reportable under 10CFR50.72(b)(3)(v)(D), 8 hour report. The site entered T.S. 3.0.3 at 19:28 and exited at 20:54 when repairs to 2B CARF were completed. 2A CARF repairs are complete. There was no impact on the health and safety of the public or plant personnel. The senior NRC Resident Inspector has been notified."
The licensee verified this problem does not affect unit-1. | |