Event Notification Report for September 13, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/12/2016 - 09/13/2016
EVENT NUMBERS
52238522395224052302
Agreement State
Event Number: 52238
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: EXXONMOBIL
Region: 4
City: BATON ROUGE State: LA
County:
License #: LA-2349-L01
Agreement: Y
Docket:
NRC Notified By: RUSSELL CLARK
HQ OPS Officer: STEVEN VITTO
Licensee: EXXONMOBIL
Region: 4
City: BATON ROUGE State: LA
County:
License #: LA-2349-L01
Agreement: Y
Docket:
NRC Notified By: RUSSELL CLARK
HQ OPS Officer: STEVEN VITTO
Notification Date: 09/13/2016
Notification Time: 17:00 [ET]
Event Date: 09/13/2016
Event Time: 09:10 [CDT]
Last Update Date: 09/13/2016
Notification Time: 17:00 [ET]
Event Date: 09/13/2016
Event Time: 09:10 [CDT]
Last Update Date: 09/13/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
AGREEMENT STATE REPORT - DENSITY GAUGE EQUIPMENT MALFUNCTION
The following was received from the State of Louisiana via email:
"On September 13, 2016, at approximately 0910, Central Standard Time, Radiation Safety Officer (RSO) of ExxonMobil notified LDEQ [Louisiana Department of Environmental Quality] of a potential equipment malfunction. A Ronan Model SA-1-C5 level/density gauge, device serial number LA8122A, containing a 100 mCi sealed source of Cs-137 and installed on D-Line Low Pressure Separator Vessel, V-231, was undergoing a routine annual shutter test when the gauge shutter became stuck in the open position. The RSO called Ronan and left the manufacturer a message requesting service and repair of the gauge. This is not an emergency. ExxonMobil Radiation Safety Office staff are monitoring the vessel condition and have the situation under control. There is no potential for off-site exposure."
Event Report ID NO.: LA160009
The following was received from the State of Louisiana via email:
"On September 13, 2016, at approximately 0910, Central Standard Time, Radiation Safety Officer (RSO) of ExxonMobil notified LDEQ [Louisiana Department of Environmental Quality] of a potential equipment malfunction. A Ronan Model SA-1-C5 level/density gauge, device serial number LA8122A, containing a 100 mCi sealed source of Cs-137 and installed on D-Line Low Pressure Separator Vessel, V-231, was undergoing a routine annual shutter test when the gauge shutter became stuck in the open position. The RSO called Ronan and left the manufacturer a message requesting service and repair of the gauge. This is not an emergency. ExxonMobil Radiation Safety Office staff are monitoring the vessel condition and have the situation under control. There is no potential for off-site exposure."
Event Report ID NO.: LA160009
Power Reactor
Event Number: 52239
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN ALEXANDER
HQ OPS Officer: STEVE SANDIN
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN ALEXANDER
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/13/2016
Notification Time: 22:28 [ET]
Event Date: 09/13/2016
Event Time: 17:30 [CDT]
Last Update Date: 12/22/2016
Notification Time: 22:28 [ET]
Event Date: 09/13/2016
Event Time: 17:30 [CDT]
Last Update Date: 12/22/2016
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):
RAY AZUA (R4DO)
RAY AZUA (R4DO)
| 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 |
UNANALYZED CONDITION INVOLVING STATION SERVICE WATER TRAINS
"Based on a walk down in the Service Water Intake Structure (SWIS) with the NRC Resident [Inspector], it was observed that a vertical section of 4 inch Fire Protection pipe that provides a normally pressurized source of fire water supply to the overhead sprinkler system in the SWIS is not Moderate Energy Line Break (MELB) shielded similar to the horizontal segment of the same line near the ceiling. In the event of a MELB crack along any portion of the unshielded pipe, the MELB has a potential impact to the function of any one of the 4 Service Water pumps. Only one train at a time would be affected during the event. This is due to the physical characteristics of the postulated MELB and the configuration/separation relative to the source line and target pumps and/or associated Motor Control Centers (MCCs) that support pump operation.
"Since the Service Water trains have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, if the MELB were to have occurred during these times and affected the opposite train, then two Service Water trains could have been inoperable and this represents an unanalyzed condition. At the time of discovery, all four Service Water trains were operable, therefore, this condition is not reportable as a loss of safety function per 10 CFR 50.72(b)(3)(vi).
"Currently, Service Water Train B on each Unit has been declared inoperable per Technical Specification (TS) 3.7.8. This condition will be corrected within the 72-hour Completion Time of TS 3.7.8.
"Currently, Emergency Diesel Generator B on each Unit has been declared inoperable per Technical Specification (TS) 3.8.1. This condition will be corrected within the 72-hour Completion Time of TS 3.8.1.
"The NRC Resident Inspector was informed."
* * * UPDATE ON 10/6/2016 AT 2009 EDT FROM DAMON SCHROEDER TO DONG PARK * * *
"This is an update to Event Number 52239. On September 13, 2016 at 2228 EDT, Comanche Peak reported an unanalyzed condition involving station service water trains per 10CFR50.72(b)(3)(ii)(B). Specifically, the reported condition involved a vertical section of 4 inch Fire Protection pipe in the SWIS that was not adequately shielded for a Moderate Energy Line Break (MELB). In the event of a MELB crack along any portion of the unshielded pipe, the MELB had a potential impact to the function of any one of the 4 Service Water pumps.
"On October 6, 2016 at 1410 hours CDT, a section of eyewash station pipe in the Unit 2 Safeguards Building was identified as a result of extent of condition walkdowns that was not adequately shielded for a Moderate Energy Line Break (MELB). In the event of a MELB crack along any portion of this unshielded pipe, the MELB had the potential to impact Unit 2 Train B 480V Motor Control Center (MCC) 2EB2-1. This MCC provides power to Unit 2 Train B Emergency Core Cooling, Battery Charger, Containment Spray, and Containment Isolation Valve equipment. The affected eyewash station pipe was isolated shortly after it was discovered to not be adequately shielded for a MELB.
"Since 480V MCC 2EB1-1 and the Unit 2 Train A Emergency Core Cooling, Battery Charger, Containment Spray, and Containment Isolation Valve equipment trains have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, if the MELB were to have occurred during these times and affected the opposite train, then 2EB1-1, 2EB2-1 and both trains of the Unit 2 Emergency Core Cooling, Battery Charger, Containment Spray, and Containment Isolation Valve equipment could have been inoperable and this represents an unanalyzed condition. At the time of discovery, 2EB1-1 and the Unit 2 Train A Emergency Core Cooling, Battery Charger, Containment Spray, and Containment Isolation Valve equipment was operable. Therefore, this condition is not reportable as a loss of safety function per 10 CFR 50.72(b)(3)(vi).
"The NRC Resident Inspector was informed."
Notified R4DO (Werner).
* * * UPDATE FROM ROBERT DANIELS TO DONALD NORWOOD AT 2233 EDT ON 10/10/2016 * * *
"This is an additional update to Event Number 52239. On September 13, 2016 at 2228 EDT and again on October 6, 2016 at 2009 EDT, Comanche Peak reported unanalyzed conditions involving Station Service Water System trains and a 480V Motor Control Center (MCC) per 10 CFR 50.72(b)(3)(ii)(B). The reported conditions involved sections of piping that were not adequately shielded for a Moderate Energy Line Break (MELB). In the event of a MELB crack along any portion of the unshielded piping, the MELB had a potential impact to the function of safety-related equipment in the Service Water Intake Structure and the Unit 2 Safeguards Building.
"On October 10, 2016 at 1708 CDT, as a result of ongoing extent of condition walkdowns, a section of fire protection pipe in the Unit 1 Safeguards Building was identified that was not adequately shielded for a MELB. In the event of a MELB crack along any portion of this unshielded pipe, the MELB had the potential to impact Unit 1 Train B Switchgear 1EA2, Unit 1 Train B 480V MCC 1EB4-2, and Unit 1 Train B Distribution Panel 1ED2-2. Only one of these power supplies at a time would be affected. 1EA2 provides 6.9KV electrical power to various Unit 1 Train B safety-related pumps, panels, sequencer, and transformers. 1EB4-2 provides 480V electrical power to various Unit 1 Train B safety-related pumps, valves, fans, panels, and transformers. 1ED2-2 provides 125VDC electrical power to EDG 1-02 channel 1 starting circuit. The affected fire protection pipe was isolated shortly after it was discovered to not be adequately shielded for a MELB.
"Since Unit 1 Train A Switchgear 1EA1, Unit 1 Train A 480V MCC 1EB3-2, and Unit 1 Train A Distribution Panel 1ED1-2 have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, if the MELB were to have occurred during these times and affected the opposite train, then both trains of Unit 1 6.9KV power (1EA2 and 1EA1), both trains of Unit 1 480V power (1EB4-2 and 1EB3-2), and both trains of Unit 1 125VDC power (1ED2-2 and 1ED1-2) along with the safety-related equipment they supply could potentially have been inoperable and this represents an unanalyzed condition per 10 CFR 50.72(b)(3)(ii)(B). At the time of discovery, none of the affected Train A equipment was inoperable. Therefore, this condition is not reportable as a loss of safety function per 10 CFR 50.72(b)(3)(v).
"The NRC Resident Inspector was informed."
Notified R4DO (Werner).
* * * UPDATE FROM HUNTER SCHILL TO DONALD NORWOOD AT 1457 EST ON 11/7/2016 * * *
"This is an update to Event Number 52239. On November 17, 2016 at 0730 CST, during ongoing extent of condition walkdowns in the Boric Acid Transfer Pump Area of the Auxiliary Building, two pressurized fire protection pipe segments were identified that did not contain Moderate Energy Line Break (MELB) shielding. In the event of a MELB crack along the unshielded portion of these pipes, the MELB had the potential to impact Unit 1 Train B 480V Motor Control Center (MCC) 1 EB4-1. This MCC provides 480V electrical power to various Unit 1 Train B safety-related pumps, valves, fans, battery chargers, and transformers.
"At 0743 CST, Technical Specification 3.8.9 Condition A was entered for one AC electrical power distribution subsystem inoperable. At 1021 CST, MCC 1 EB4-1 was declared Operable after MELB shielding was installed on the affected fire protection lines.
"Since Unit 1 Train A 480V MCC 1 EB3-1 and the associated Unit 1 Train A safety-related pumps, valves, fans, battery chargers, and transformers have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, given the MELB condition, 1 EB4-1, 1 EB3-1 and both trains of the Unit 1 safety-related pumps, valves, fans, battery chargers, and transformers they supply could have been inoperable and this represents an unanalyzed condition. At the time of discovery, 1 EB3-1 and the associated Unit 1 Train A safety-related pumps, valves, fans, battery chargers, and transformers were operable. Therefore, this condition is not reportable as a loss of safety function per 10 CFR 50.72(b)(3)(v).
"The NRC Resident Inspector was informed."
Notified R4DO (Azua).
* * * UPDATE ON 12/05/2016 AT 1730 EST FROM HUNTER SCHILL TO STEVEN VITTO * * *
"This is an update to Event Number 52239. On December 5, 2016 during ongoing extent of condition walk downs in the Auxiliary Building, pressurized fire protection pipe segments (a flange and a pipe elbow) were identified which did not contain Moderate Energy Line Break (MELB) shielding. In the event of a MELB crack along the un-shielded portion of the pipes, a MELB had the potential to impact Unit 2 Train B 480V Motor Control Center (MCC) 2EB4-1. This MCC provides 480V electrical power to various Unit 2 Train B safety-related pumps, valves, fans, battery chargers, and transformers.
"At approximately 1355 CST Technical Specification 3.8.9 Condition A was entered for one AC electrical power distribution subsystem inoperable. At 1459 CST, MCC 2EB4-1 was declared Operable after MELB shielding was installed on the affected fire protection line locations.
"Since Unit 2 Train A 480V MCC 2EB3-1 and the associated Unit 2 Train A safety-related pumps, valves, fans, battery chargers, and transformers have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, given the MELB condition, 2EB4-1 , 2EB3-1 and both trains of the Unit 2 safety-related pumps, valves, fans, battery chargers, and transformers they supply could have been inoperable and this represents an un-analyzed condition. At the time of discovery, 2EB3-1 and the associated Unit 2 Train A safety-related pumps, valves, fans, battery chargers, and transformers were operable. Therefore, this condition is not reportable as a loss of safety function per 10CFR 50.72(b)(3)(v).
"The NRC Resident Inspector was informed."
Notified R4DO (Gaddy).
* * * UPDATE ON 12/22/2016 AT 1649 EST FROM HUNTER SCHILL TO DONG PARK * * *
"This is an update to Event Number 52239. On December 22, 2016 at approximately 1046 [CST] during ongoing extent of condition walk downs in the common Auxiliary Building (AB) corridor room (X-179), several normally pressurized Waste Processing (WP) pipe segments and one Vent & Drain (VD) segment which are greater than 1" nominal pipe diameter, did not contain MELB shielding. In the event of a MELB crack along the unshielded portion of these pipes, a MELB could have had the potential to impact Unit 1, Train B 480V Motor Control Center (MCC) 1EB4-1. This MCC provides 480V electrical power to various Unit 1 Train B safety-related pumps, valves, fans, battery chargers, and transformers.
"Prior to the field walkdown, the subject WP and VD line segments were either isolated and depressurized (WP lines) and/or the AB sump discharges realigned (VD) such that the subject lines would pose no threat to the MCC 1EB4-1 if confirmed that shielding is required. As such, the identified condition does not adversely affect operability of 1EB4-1 and entry into a Technical Specification action statement was not required. Field activities continue to install MELB shielding in the affected locations.
"Since Unit 1 Train A 480V MCC 1EB3-1 and the associated Unit 1 Train A safety-related pumps, valves, fans, battery chargers, and transformers have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, given the MELB condition, 1EB4-1, 1EB3-1 and both trains of the Unit 1 safety-related pumps, valves, fans, battery chargers, and transformers they supply could have been inoperable and this represents an unanalyzed condition. At the time of discovery, 1EB3-1 and the associated Unit 1 Train A safety-related pumps, valves, fans, battery chargers, and transformers were operable. Therefore, this condition is not reportable as a loss of safety function per 10CFR 50.72(b)(3)(v).
"The NRC Resident Inspector was informed."
Notified R4DO (Hay).
"Based on a walk down in the Service Water Intake Structure (SWIS) with the NRC Resident [Inspector], it was observed that a vertical section of 4 inch Fire Protection pipe that provides a normally pressurized source of fire water supply to the overhead sprinkler system in the SWIS is not Moderate Energy Line Break (MELB) shielded similar to the horizontal segment of the same line near the ceiling. In the event of a MELB crack along any portion of the unshielded pipe, the MELB has a potential impact to the function of any one of the 4 Service Water pumps. Only one train at a time would be affected during the event. This is due to the physical characteristics of the postulated MELB and the configuration/separation relative to the source line and target pumps and/or associated Motor Control Centers (MCCs) that support pump operation.
"Since the Service Water trains have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, if the MELB were to have occurred during these times and affected the opposite train, then two Service Water trains could have been inoperable and this represents an unanalyzed condition. At the time of discovery, all four Service Water trains were operable, therefore, this condition is not reportable as a loss of safety function per 10 CFR 50.72(b)(3)(vi).
"Currently, Service Water Train B on each Unit has been declared inoperable per Technical Specification (TS) 3.7.8. This condition will be corrected within the 72-hour Completion Time of TS 3.7.8.
"Currently, Emergency Diesel Generator B on each Unit has been declared inoperable per Technical Specification (TS) 3.8.1. This condition will be corrected within the 72-hour Completion Time of TS 3.8.1.
"The NRC Resident Inspector was informed."
* * * UPDATE ON 10/6/2016 AT 2009 EDT FROM DAMON SCHROEDER TO DONG PARK * * *
"This is an update to Event Number 52239. On September 13, 2016 at 2228 EDT, Comanche Peak reported an unanalyzed condition involving station service water trains per 10CFR50.72(b)(3)(ii)(B). Specifically, the reported condition involved a vertical section of 4 inch Fire Protection pipe in the SWIS that was not adequately shielded for a Moderate Energy Line Break (MELB). In the event of a MELB crack along any portion of the unshielded pipe, the MELB had a potential impact to the function of any one of the 4 Service Water pumps.
"On October 6, 2016 at 1410 hours CDT, a section of eyewash station pipe in the Unit 2 Safeguards Building was identified as a result of extent of condition walkdowns that was not adequately shielded for a Moderate Energy Line Break (MELB). In the event of a MELB crack along any portion of this unshielded pipe, the MELB had the potential to impact Unit 2 Train B 480V Motor Control Center (MCC) 2EB2-1. This MCC provides power to Unit 2 Train B Emergency Core Cooling, Battery Charger, Containment Spray, and Containment Isolation Valve equipment. The affected eyewash station pipe was isolated shortly after it was discovered to not be adequately shielded for a MELB.
"Since 480V MCC 2EB1-1 and the Unit 2 Train A Emergency Core Cooling, Battery Charger, Containment Spray, and Containment Isolation Valve equipment trains have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, if the MELB were to have occurred during these times and affected the opposite train, then 2EB1-1, 2EB2-1 and both trains of the Unit 2 Emergency Core Cooling, Battery Charger, Containment Spray, and Containment Isolation Valve equipment could have been inoperable and this represents an unanalyzed condition. At the time of discovery, 2EB1-1 and the Unit 2 Train A Emergency Core Cooling, Battery Charger, Containment Spray, and Containment Isolation Valve equipment was operable. Therefore, this condition is not reportable as a loss of safety function per 10 CFR 50.72(b)(3)(vi).
"The NRC Resident Inspector was informed."
Notified R4DO (Werner).
* * * UPDATE FROM ROBERT DANIELS TO DONALD NORWOOD AT 2233 EDT ON 10/10/2016 * * *
"This is an additional update to Event Number 52239. On September 13, 2016 at 2228 EDT and again on October 6, 2016 at 2009 EDT, Comanche Peak reported unanalyzed conditions involving Station Service Water System trains and a 480V Motor Control Center (MCC) per 10 CFR 50.72(b)(3)(ii)(B). The reported conditions involved sections of piping that were not adequately shielded for a Moderate Energy Line Break (MELB). In the event of a MELB crack along any portion of the unshielded piping, the MELB had a potential impact to the function of safety-related equipment in the Service Water Intake Structure and the Unit 2 Safeguards Building.
"On October 10, 2016 at 1708 CDT, as a result of ongoing extent of condition walkdowns, a section of fire protection pipe in the Unit 1 Safeguards Building was identified that was not adequately shielded for a MELB. In the event of a MELB crack along any portion of this unshielded pipe, the MELB had the potential to impact Unit 1 Train B Switchgear 1EA2, Unit 1 Train B 480V MCC 1EB4-2, and Unit 1 Train B Distribution Panel 1ED2-2. Only one of these power supplies at a time would be affected. 1EA2 provides 6.9KV electrical power to various Unit 1 Train B safety-related pumps, panels, sequencer, and transformers. 1EB4-2 provides 480V electrical power to various Unit 1 Train B safety-related pumps, valves, fans, panels, and transformers. 1ED2-2 provides 125VDC electrical power to EDG 1-02 channel 1 starting circuit. The affected fire protection pipe was isolated shortly after it was discovered to not be adequately shielded for a MELB.
"Since Unit 1 Train A Switchgear 1EA1, Unit 1 Train A 480V MCC 1EB3-2, and Unit 1 Train A Distribution Panel 1ED1-2 have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, if the MELB were to have occurred during these times and affected the opposite train, then both trains of Unit 1 6.9KV power (1EA2 and 1EA1), both trains of Unit 1 480V power (1EB4-2 and 1EB3-2), and both trains of Unit 1 125VDC power (1ED2-2 and 1ED1-2) along with the safety-related equipment they supply could potentially have been inoperable and this represents an unanalyzed condition per 10 CFR 50.72(b)(3)(ii)(B). At the time of discovery, none of the affected Train A equipment was inoperable. Therefore, this condition is not reportable as a loss of safety function per 10 CFR 50.72(b)(3)(v).
"The NRC Resident Inspector was informed."
Notified R4DO (Werner).
* * * UPDATE FROM HUNTER SCHILL TO DONALD NORWOOD AT 1457 EST ON 11/7/2016 * * *
"This is an update to Event Number 52239. On November 17, 2016 at 0730 CST, during ongoing extent of condition walkdowns in the Boric Acid Transfer Pump Area of the Auxiliary Building, two pressurized fire protection pipe segments were identified that did not contain Moderate Energy Line Break (MELB) shielding. In the event of a MELB crack along the unshielded portion of these pipes, the MELB had the potential to impact Unit 1 Train B 480V Motor Control Center (MCC) 1 EB4-1. This MCC provides 480V electrical power to various Unit 1 Train B safety-related pumps, valves, fans, battery chargers, and transformers.
"At 0743 CST, Technical Specification 3.8.9 Condition A was entered for one AC electrical power distribution subsystem inoperable. At 1021 CST, MCC 1 EB4-1 was declared Operable after MELB shielding was installed on the affected fire protection lines.
"Since Unit 1 Train A 480V MCC 1 EB3-1 and the associated Unit 1 Train A safety-related pumps, valves, fans, battery chargers, and transformers have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, given the MELB condition, 1 EB4-1, 1 EB3-1 and both trains of the Unit 1 safety-related pumps, valves, fans, battery chargers, and transformers they supply could have been inoperable and this represents an unanalyzed condition. At the time of discovery, 1 EB3-1 and the associated Unit 1 Train A safety-related pumps, valves, fans, battery chargers, and transformers were operable. Therefore, this condition is not reportable as a loss of safety function per 10 CFR 50.72(b)(3)(v).
"The NRC Resident Inspector was informed."
Notified R4DO (Azua).
* * * UPDATE ON 12/05/2016 AT 1730 EST FROM HUNTER SCHILL TO STEVEN VITTO * * *
"This is an update to Event Number 52239. On December 5, 2016 during ongoing extent of condition walk downs in the Auxiliary Building, pressurized fire protection pipe segments (a flange and a pipe elbow) were identified which did not contain Moderate Energy Line Break (MELB) shielding. In the event of a MELB crack along the un-shielded portion of the pipes, a MELB had the potential to impact Unit 2 Train B 480V Motor Control Center (MCC) 2EB4-1. This MCC provides 480V electrical power to various Unit 2 Train B safety-related pumps, valves, fans, battery chargers, and transformers.
"At approximately 1355 CST Technical Specification 3.8.9 Condition A was entered for one AC electrical power distribution subsystem inoperable. At 1459 CST, MCC 2EB4-1 was declared Operable after MELB shielding was installed on the affected fire protection line locations.
"Since Unit 2 Train A 480V MCC 2EB3-1 and the associated Unit 2 Train A safety-related pumps, valves, fans, battery chargers, and transformers have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, given the MELB condition, 2EB4-1 , 2EB3-1 and both trains of the Unit 2 safety-related pumps, valves, fans, battery chargers, and transformers they supply could have been inoperable and this represents an un-analyzed condition. At the time of discovery, 2EB3-1 and the associated Unit 2 Train A safety-related pumps, valves, fans, battery chargers, and transformers were operable. Therefore, this condition is not reportable as a loss of safety function per 10CFR 50.72(b)(3)(v).
"The NRC Resident Inspector was informed."
Notified R4DO (Gaddy).
* * * UPDATE ON 12/22/2016 AT 1649 EST FROM HUNTER SCHILL TO DONG PARK * * *
"This is an update to Event Number 52239. On December 22, 2016 at approximately 1046 [CST] during ongoing extent of condition walk downs in the common Auxiliary Building (AB) corridor room (X-179), several normally pressurized Waste Processing (WP) pipe segments and one Vent & Drain (VD) segment which are greater than 1" nominal pipe diameter, did not contain MELB shielding. In the event of a MELB crack along the unshielded portion of these pipes, a MELB could have had the potential to impact Unit 1, Train B 480V Motor Control Center (MCC) 1EB4-1. This MCC provides 480V electrical power to various Unit 1 Train B safety-related pumps, valves, fans, battery chargers, and transformers.
"Prior to the field walkdown, the subject WP and VD line segments were either isolated and depressurized (WP lines) and/or the AB sump discharges realigned (VD) such that the subject lines would pose no threat to the MCC 1EB4-1 if confirmed that shielding is required. As such, the identified condition does not adversely affect operability of 1EB4-1 and entry into a Technical Specification action statement was not required. Field activities continue to install MELB shielding in the affected locations.
"Since Unit 1 Train A 480V MCC 1EB3-1 and the associated Unit 1 Train A safety-related pumps, valves, fans, battery chargers, and transformers have been periodically declared inoperable at various times in the last three years for surveillance testing or maintenance, given the MELB condition, 1EB4-1, 1EB3-1 and both trains of the Unit 1 safety-related pumps, valves, fans, battery chargers, and transformers they supply could have been inoperable and this represents an unanalyzed condition. At the time of discovery, 1EB3-1 and the associated Unit 1 Train A safety-related pumps, valves, fans, battery chargers, and transformers were operable. Therefore, this condition is not reportable as a loss of safety function per 10CFR 50.72(b)(3)(v).
"The NRC Resident Inspector was informed."
Notified R4DO (Hay).
Power Reactor
Event Number: 52240
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: MICHAEL MOORE
HQ OPS Officer: DONG HWA PARK
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: MICHAEL MOORE
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/14/2016
Notification Time: 01:02 [ET]
Event Date: 09/13/2016
Event Time: 20:30 [EDT]
Last Update Date: 09/14/2016
Notification Time: 01:02 [ET]
Event Date: 09/13/2016
Event Time: 20:30 [EDT]
Last Update Date: 09/14/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
SHAKUR WALKER (R2DO)
SHAKUR WALKER (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 |
STEAM PROPAGATION BARRIER DOOR FOUND OPEN
"During routine operator rounds at 2030 EDT, a steam propagation barrier door (SPBD) was discovered propped open for maintenance activities without appropriate station controls. This condition was in existence from approximately 1720 EDT to 2042 EDT when the SPBD was restored to its normal configuration. Throughout the approximate 3 hours and 22 minutes, when the SPBD was propped open, both trains of chill water were rendered non-functional due to a potential high energy line break. This subsequently rendered both trains of high-head safety injection inoperable, which placed the plant in Technical Specification 3.0.3. This condition was corrected prior to commencing a Technical Specification 3.0.3 plant shutdown. This condition is reportable under 10 CFR 50.72(b)(3)(v) as any event or condition that at the time of discovery could have prevented the fulfillment of a safety function.
"The NRC Senior Resident Inspector has been notified."
"During routine operator rounds at 2030 EDT, a steam propagation barrier door (SPBD) was discovered propped open for maintenance activities without appropriate station controls. This condition was in existence from approximately 1720 EDT to 2042 EDT when the SPBD was restored to its normal configuration. Throughout the approximate 3 hours and 22 minutes, when the SPBD was propped open, both trains of chill water were rendered non-functional due to a potential high energy line break. This subsequently rendered both trains of high-head safety injection inoperable, which placed the plant in Technical Specification 3.0.3. This condition was corrected prior to commencing a Technical Specification 3.0.3 plant shutdown. This condition is reportable under 10 CFR 50.72(b)(3)(v) as any event or condition that at the time of discovery could have prevented the fulfillment of a safety function.
"The NRC Senior Resident Inspector has been notified."
Part 21
Event Number: 52302
Rep Org: C&D TECHNOLOGIES INC
Licensee: C&D TECHNOLOGIES INC
Region: 1
City: BLUE BELL State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT MALLEY
HQ OPS Officer: DONALD NORWOOD
Licensee: C&D TECHNOLOGIES INC
Region: 1
City: BLUE BELL State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT MALLEY
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/18/2016
Notification Time: 16:23 [ET]
Event Date: 09/13/2016
Event Time: 00:00 [EDT]
Last Update Date: 10/18/2016
Notification Time: 16:23 [ET]
Event Date: 09/13/2016
Event Time: 00:00 [EDT]
Last Update Date: 10/18/2016
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):
CHRISTOPHER CAHILL (R1DO)
JOHN KRAMER (R4DO)
PART 21/50.55 REACT (EMAI)
CHRISTOPHER CAHILL (R1DO)
JOHN KRAMER (R4DO)
PART 21/50.55 REACT (EMAI)
PART 21 - EVALUATION REGARDING TERMINAL WELDING FAILURE IN 3DCU-9 BATTERIES
The following information is a synopsis of information received via E-mail:
On August 8, 2016 a user of commercial grade (non-Class 1E) 3DCU-5 batteries notified C&D of an issue with two units that exhibited high on-charge voltage and sulfated positive plates. The batteries were returned and analyzed. On September 13, 2016 C&D's laboratory issued a report showing that the batteries had failed welds between the terminal posts and the external battery terminals. This weld has the function of carrying current between the battery energy storage elements and the customer load. Failure of the welds could interrupt the current flow to customer loads during discharge.
Although the batteries were not sold or used in a nuclear safety related application, C&D conducted an extent of condition analysis to determine whether this condition could exist in DCU products sold into safety related products. Although no similar reports have been made from users of Class 1E DCU batteries, based on the results of this analysis, there is a risk that this condition may exist in safety related products.
The batteries in question are DCU Batteries, manufactured from April 2010 to August 2016. The battery manufacturing date is on the label.
The following nuclear plants were supplied DCU batteries for use in 1E applications, with shipment dates of April 2010 to August 2016: Energy Northwest - Columbia, Exelon - Nine Mile, Talen Energy - Susquehanna, Entergy - Grand Gulf, and Exelon - Limerick.
As corrective actions, C&D has implemented a discharge test to detect and eliminate any improperly made welds prior to shipment to end users. C&D has also performed additional training and qualification work with employees responsible for terminal welding on DCU products. These actions were implemented prior to shipment of Class 1E nuclear products in September 2016, and now are complete.
The following information is a synopsis of information received via E-mail:
On August 8, 2016 a user of commercial grade (non-Class 1E) 3DCU-5 batteries notified C&D of an issue with two units that exhibited high on-charge voltage and sulfated positive plates. The batteries were returned and analyzed. On September 13, 2016 C&D's laboratory issued a report showing that the batteries had failed welds between the terminal posts and the external battery terminals. This weld has the function of carrying current between the battery energy storage elements and the customer load. Failure of the welds could interrupt the current flow to customer loads during discharge.
Although the batteries were not sold or used in a nuclear safety related application, C&D conducted an extent of condition analysis to determine whether this condition could exist in DCU products sold into safety related products. Although no similar reports have been made from users of Class 1E DCU batteries, based on the results of this analysis, there is a risk that this condition may exist in safety related products.
The batteries in question are DCU Batteries, manufactured from April 2010 to August 2016. The battery manufacturing date is on the label.
The following nuclear plants were supplied DCU batteries for use in 1E applications, with shipment dates of April 2010 to August 2016: Energy Northwest - Columbia, Exelon - Nine Mile, Talen Energy - Susquehanna, Entergy - Grand Gulf, and Exelon - Limerick.
As corrective actions, C&D has implemented a discharge test to detect and eliminate any improperly made welds prior to shipment to end users. C&D has also performed additional training and qualification work with employees responsible for terminal welding on DCU products. These actions were implemented prior to shipment of Class 1E nuclear products in September 2016, and now are complete.