| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/28/2015 - 05/29/2015 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 51094 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: QUOC VO
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/28/2015
Notification Time: 03:35 [ET]
Event Date: 05/27/2015
Event Time: 22:17 [PDT]
Last Update Date: 05/28/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
WAYNE WALKER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text AREA RADIATION MONITORS NON-FUNCTIONAL DURING PLANNED BUS OUTAGE
"A planned outage of the Division 2 medium voltage switchgear (SM-8) was initiated at 22:17 PDT on 5/27/15. The bus outage results in all area radiation monitors required for emergency classification being non-functional. Compensatory measure monitoring equipment has been established prior to the loss to provide alternate means of monitoring area radiation levels. The SM-8 outage window is scheduled to last 124 hours. Although the monitoring function is maintained by the compensatory monitoring equipment, the planned loss of area radiation monitors for greater than 72 hours is being reported as a major loss of emergency assessment capability in accordance with 10 CFR 50. 72(b )(3)(xiii).
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 51095 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK TURKAL
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 05/28/2015
Notification Time: 13:18 [ET]
Event Date: 05/26/2015
Event Time: 15:36 [EDT]
Last Update Date: 05/28/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
PART 21/50.55 REACT (EMAI)
|
| 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 PART 21 NOTIFICATION - ALLEN BRADLEY 700RTC RELAY CONFIGURATION
"This is a non-emergency notification, required by 10 CFR 21.21(d)(3)(i).
"Brunswick has determined that Allen Bradley relays, base model 700RTC, contain an unevaluated Complex Programmable Logic Device (CPLD). This was an unpublished design change that was implemented to replace an obsolete integrated circuit chip. The undocumented design change did not result in a part number change from Allen Bradley. There was no change to the external appearance of the relay that would indicate that a design change had been made to the relay configuration. Therefore, qualification/dedication of the modified relays have not included additional testing for the new CPLD component. Testing, performed by Duke Energy, has demonstrated that this CPLD can be affected by electrical noise from operation of nearby relays which can reset the timing of the relay. This condition was discovered as a result of a post-maintenance test of an emergency diesel generator. Additional details associated with the discovery of this condition are contained in Brunswick Licensee Event Report 1-2015-002, dated May 20, 2015.
"Brunswick purchased, as commercial grade, 25 of the modified Allen Bradley 700RTC relays beginning in October, 2008. Duke Energy dedicated these relays for use in safety related applications at Brunswick. The dedicated relays were not provided to any third party customers.
"The NRC Senior Resident Inspector has been notified."
Brunswick has taken applicable compensatory measures to insure no equipment is inoperable because of these relays.
This problem was previously reported by AZZ/NLI Nuclear Logistics, Inc. in EN #51030. | |