Event Notification Report for May 26, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/25/2015 - 05/26/2015
Power Reactor
Event Number: 51089
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN FINLAY
HQ OPS Officer: STEVEN VITTO
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN FINLAY
HQ OPS Officer: STEVEN VITTO
Notification Date: 05/26/2015
Notification Time: 15:20 [ET]
Event Date: 05/26/2015
Event Time: 11:25 [CDT]
Last Update Date: 05/26/2015
Notification Time: 15:20 [ET]
Event Date: 05/26/2015
Event Time: 11:25 [CDT]
Last Update Date: 05/26/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY - ALCOHOL CONTAINER FOUND IN PROTECTED AREA
On May 26, 2015, at approximately 1125 CDT, an empty beer can was found by a mechanical maintenance worker performing scaffolding work. Site Security took possession of the can and it was removed from the protected area. The can appears to be extremely old (20 plus years) with dust and debris on it. This report is submitted pursuant to 10 CFR 26.719(b)(1) based on the presence of an alcohol container within the protected area.
The licensee notified the NRC Resident Inspector.
On May 26, 2015, at approximately 1125 CDT, an empty beer can was found by a mechanical maintenance worker performing scaffolding work. Site Security took possession of the can and it was removed from the protected area. The can appears to be extremely old (20 plus years) with dust and debris on it. This report is submitted pursuant to 10 CFR 26.719(b)(1) based on the presence of an alcohol container within the protected area.
The licensee notified the NRC Resident Inspector.
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
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
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
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
PART 21/50.55 REACT (EMAI)
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 |
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.
"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.