Event Notification Report for September 14, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/13/2015 - 09/14/2015
Agreement State
Event Number: 51396
Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: RESOLUTE FOREST PRODUCTS
Region: 1
City: CATAWBA State: SC
County:
License #: 030
Agreement: Y
Docket:
NRC Notified By: JAMES PETERSON
HQ OPS Officer: JEFF ROTTON
Licensee: RESOLUTE FOREST PRODUCTS
Region: 1
City: CATAWBA State: SC
County:
License #: 030
Agreement: Y
Docket:
NRC Notified By: JAMES PETERSON
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/15/2015
Notification Time: 15:52 [ET]
Event Date: 09/14/2015
Event Time: 00:00 [EDT]
Last Update Date: 09/15/2015
Notification Time: 15:52 [ET]
Event Date: 09/14/2015
Event Time: 00:00 [EDT]
Last Update Date: 09/15/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
SILAS KENNEDY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
SILAS KENNEDY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
SOUTH CAROLINA AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE WITH A STUCK SHUTTER
The following information was provided by the State of South Carolina via email:
"The licensee provided notification of a stuck shutter, on a Berthold Model LB7440D fixed gauging device, discovered while performing a semi-annual shutter check. The gauging device contains 30 mCi of Cs-137. The device remains mounted to the process piping with no gap available to permit personnel exposure to the radiation beam. A licensed contractor has been contacted and will proceed with corrective maintenance on the shutter mechanism within the next 30 days."
State Event Report ID No.: SC-04-2015
The following information was provided by the State of South Carolina via email:
"The licensee provided notification of a stuck shutter, on a Berthold Model LB7440D fixed gauging device, discovered while performing a semi-annual shutter check. The gauging device contains 30 mCi of Cs-137. The device remains mounted to the process piping with no gap available to permit personnel exposure to the radiation beam. A licensed contractor has been contacted and will proceed with corrective maintenance on the shutter mechanism within the next 30 days."
State Event Report ID No.: SC-04-2015
Power Reactor
Event Number: 51392
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE TUTHILL
HQ OPS Officer: JEFF HERRERA
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE TUTHILL
HQ OPS Officer: JEFF HERRERA
Notification Date: 09/14/2015
Notification Time: 08:12 [ET]
Event Date: 09/14/2015
Event Time: 04:26 [EDT]
Last Update Date: 09/14/2015
Notification Time: 08:12 [ET]
Event Date: 09/14/2015
Event Time: 04:26 [EDT]
Last Update Date: 09/14/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
SCOTT SHAEFFER (R2DO)
SCOTT SHAEFFER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO LOSS OF POWER TO VITAL INSTRUMENT BOARD
"At 0426 EDT on 9/14/2015, Sequoyah Unit 1 was at 100% power when the Vital Instrument Power Board (VIPB) 1-II deenergized. A manual reactor trip was initiated in accordance with the Abnormal Operating Procedure for the loss of VIPB 1-II.
"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically initiated as expected from the Feedwater Isolation Signal.
"Unit 1 is currently being maintained in Mode 3 at NOT/NOP [Normal Operating Temperature/Normal Operating Pressure], approximately 547 degrees F and 2235 psig, with auxiliary feedwater supplying the steam generators and decay heat removal via the condenser steam dumps.
"Current Temperature and Pressure - Reactor Coolant System (RCS) temperature is 547 degrees F and stable and RCS pressure is 2235 psig and stable. There is no indication of any primary to secondary leakage. All rods fully inserted on the reactor trip and remain inserted. The electrical alignment is normal with shutdown power supplied from off-site power. There is no operational impact to Unit 2. Unit 2 continues to operate in Mode 1 at 100 [percent].
"There was no impact on public health and safety. Post-trip investigation is in progress and planned restart timeline has not yet been determined.
"The licensee notified the NRC Resident Inspector. "
"At 0426 EDT on 9/14/2015, Sequoyah Unit 1 was at 100% power when the Vital Instrument Power Board (VIPB) 1-II deenergized. A manual reactor trip was initiated in accordance with the Abnormal Operating Procedure for the loss of VIPB 1-II.
"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically initiated as expected from the Feedwater Isolation Signal.
"Unit 1 is currently being maintained in Mode 3 at NOT/NOP [Normal Operating Temperature/Normal Operating Pressure], approximately 547 degrees F and 2235 psig, with auxiliary feedwater supplying the steam generators and decay heat removal via the condenser steam dumps.
"Current Temperature and Pressure - Reactor Coolant System (RCS) temperature is 547 degrees F and stable and RCS pressure is 2235 psig and stable. There is no indication of any primary to secondary leakage. All rods fully inserted on the reactor trip and remain inserted. The electrical alignment is normal with shutdown power supplied from off-site power. There is no operational impact to Unit 2. Unit 2 continues to operate in Mode 1 at 100 [percent].
"There was no impact on public health and safety. Post-trip investigation is in progress and planned restart timeline has not yet been determined.
"The licensee notified the NRC Resident Inspector. "