Event Notification Report for April 06, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/05/2023 - 04/06/2023
Power Reactor
Event Number: 56455
Facility: Perry
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Michael Brogan
HQ OPS Officer: Ian Howard
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Michael Brogan
HQ OPS Officer: Ian Howard
Notification Date: 04/06/2023
Notification Time: 16:46 [ET]
Event Date: 04/06/2023
Event Time: 16:46 [EDT]
Last Update Date: 04/06/2023
Notification Time: 16:46 [ET]
Event Date: 04/06/2023
Event Time: 16:46 [EDT]
Last Update Date: 04/06/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
Person (Organization):
Orlikowski, Robert (R3DO)
Orlikowski, Robert (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Cold Shutdown |
MAIN STEAM LINE 'B' LEAKAGE IN EXCESS OF TECH SPEC LIMITS
The following information was provided by the licensee via phone and email:
"On March 4, 2023, it was determined that the main steam line (MSL) local leak rate test results for MSL 'B' were in exceedance of technical specification (TS) surveillance requirement (SR) 3.6.1.3.10 limits. Additionally, the leakage at the outboard main steam isolation valve (MSIV) 'B', was indeterminate due to a gross packing gland leak. An engineering calculation dated April 6, 2023, showed that this leakage, in conjunction with a design basis loss of coolant accident, would result in the radiological dose exceeding Updated Safety Analysis Report limits to the exclusion area boundary, the low population zone, and the control room. Therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B) as a condition that results in the power plant being in an unanalyzed condition that degrades plant safety.
"Both inboard and outboard 'B' MSIVs have been reworked and are within the TS SR limits.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"On March 4, 2023, it was determined that the main steam line (MSL) local leak rate test results for MSL 'B' were in exceedance of technical specification (TS) surveillance requirement (SR) 3.6.1.3.10 limits. Additionally, the leakage at the outboard main steam isolation valve (MSIV) 'B', was indeterminate due to a gross packing gland leak. An engineering calculation dated April 6, 2023, showed that this leakage, in conjunction with a design basis loss of coolant accident, would result in the radiological dose exceeding Updated Safety Analysis Report limits to the exclusion area boundary, the low population zone, and the control room. Therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B) as a condition that results in the power plant being in an unanalyzed condition that degrades plant safety.
"Both inboard and outboard 'B' MSIVs have been reworked and are within the TS SR limits.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
Part 21
Event Number: 56457
Rep Org: Framatome ANP
Licensee: Framatome ANP
Region: 1
City: Lynchburg State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Gayle Elliot
HQ OPS Officer: Ernest West
Licensee: Framatome ANP
Region: 1
City: Lynchburg State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Gayle Elliot
HQ OPS Officer: Ernest West
Notification Date: 04/07/2023
Notification Time: 16:01 [ET]
Event Date: 04/06/2023
Event Time: 00:00 [EDT]
Last Update Date: 04/07/2023
Notification Time: 16:01 [ET]
Event Date: 04/06/2023
Event Time: 00:00 [EDT]
Last Update Date: 04/07/2023
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):
Gray, Mel (R1DO)
Miller, Mark (R2DO)
Warnick, Greg (R4DO)
Part 21/50.55 Reactors, - (EMAIL)
Gray, Mel (R1DO)
Miller, Mark (R2DO)
Warnick, Greg (R4DO)
Part 21/50.55 Reactors, - (EMAIL)
PART 21 - BREAKERS POTENTIALLY CLOSING FOLLOWING CHARGING
The following is a synopsis of information provided by Framatome, Inc. via email:
In 2011, Framatome supplied a DS-206DC breaker that incorrectly closes at the end of the charging cycle of the closing mechanism. Such a defect could result in potential unwanted start of the load of the breaker. The cause of this issue is due to an Eaton trigger roller (Eaton part number 783A446H01) being out of round. The trigger roller is a component in the main cam assembly (Eaton part number 436B418G03).
This issue was determined to be a 10 CFR 21 Defect by Framatome on April 6, 2023.
Framatome has identified this and other breakers with this potential defect listed below:
Calvert Cliffs / Electrical Load / DS-206, DS-416 Breakers
Oconee / Reactor Trip Switchgear / DSII-516 Breakers
South Texas Project / Electrical Load / DS-206, DS-416 Breakers
TVA (Watts Bar and Sequoyah) / Electrical Load / DS-206, DS-416 and DS-632 Breakers
Eaton made changes to their manufacturing process to correct the issue. Affected utilities will be provided an inspection procedure to determine if the defect is located in affected components that may be in storage or in operation. Also, Framatome will provide written correspondence to each customer regarding the issue and respond to technical questions regarding the issue.
Affected Plants with potentially defected parts include Calvert Cliffs, Oconee, South Texas Project, Sequoyah, and Watts Bar.
The following is a synopsis of information provided by Framatome, Inc. via email:
In 2011, Framatome supplied a DS-206DC breaker that incorrectly closes at the end of the charging cycle of the closing mechanism. Such a defect could result in potential unwanted start of the load of the breaker. The cause of this issue is due to an Eaton trigger roller (Eaton part number 783A446H01) being out of round. The trigger roller is a component in the main cam assembly (Eaton part number 436B418G03).
This issue was determined to be a 10 CFR 21 Defect by Framatome on April 6, 2023.
Framatome has identified this and other breakers with this potential defect listed below:
Calvert Cliffs / Electrical Load / DS-206, DS-416 Breakers
Oconee / Reactor Trip Switchgear / DSII-516 Breakers
South Texas Project / Electrical Load / DS-206, DS-416 Breakers
TVA (Watts Bar and Sequoyah) / Electrical Load / DS-206, DS-416 and DS-632 Breakers
Eaton made changes to their manufacturing process to correct the issue. Affected utilities will be provided an inspection procedure to determine if the defect is located in affected components that may be in storage or in operation. Also, Framatome will provide written correspondence to each customer regarding the issue and respond to technical questions regarding the issue.
Affected Plants with potentially defected parts include Calvert Cliffs, Oconee, South Texas Project, Sequoyah, and Watts Bar.