| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/21/2015 - 12/22/2015 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51605 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: UNION CARBIDE CORP - SEADRIFT OPERATIONS UNIT
Region: 4
City: PORT LAVACA State: TX
County:
License #: 00051
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/14/2015
Notification Time: 15:14 [ET]
Event Date: 12/14/2015
Event Time: [CST]
Last Update Date: 12/14/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED GAUGE WITH SHUTTER STUCK IN THE OPEN POSITION
The following report was received from the State of Texas via email:
"On December 14, 2015, the Agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer [RSO] that while performing routine test of gauge shutters they found a gauge where the shutter failed to operate. The gauge is located on a polyurethane tank/vessel. The gauge is an Ohmart Vega model SHF2 containing source serial number 9754GK of 200 millicurie cesium - 137. The shutter was left in the normal operating, unshielded position [open]. The source does not pose any additional risk of exposure to the workers or members of the general public. The RSO stated they have called TechStar to repair the gauge within the next few days."
Texas Report #: I 9365 |
| Power Reactor | Event Number: 51615 | Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS DEDAS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 12/21/2015
Notification Time: 18:06 [ET]
Event Date: 12/21/2015
Event Time: 15:33 [CST]
Last Update Date: 12/21/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JACK WHITTEN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 48 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO FEEDWATER ISOLATION
"At 1519 [CST], the Main Turbine was tripped due to an Oscillating Governor Valve 2 (cause not known). At 1533, Unit 1 was manually tripped due to a feedwater isolation P-14 [caused by steam generator swell induced high steam generator level, resulting in] steam generator low level [after the isolation]. Aux feedwater actuated as designed.
"All Control and Shutdown Rods fully inserted.
"Intermediate Range NI 36 failed above P-10 so SR-Nis [source range nuclear instruments] were manually energized.
"No primary relief valves lifted.
"All Steam Generator PORVs [power operated relief valves] opened.
"There were no electrical bus problems.
"Normal operating temperature and pressure (NOT/NOP) is 567F and 2235 psig.
"There were no significant TS LCOs [Technical Specification limiting conditions for operations] entered.
"This event was not significant to the health and safety of the public based on all safety systems performed as designed."
Unit 2 was not affected and continues to operate at 100% power. The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51616 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JEFF HUMAN
HQ OPS Officer: DONG HWA PARK | Notification Date: 12/21/2015
Notification Time: 22:12 [ET]
Event Date: 12/21/2015
Event Time: 16:25 [CST]
Last Update Date: 12/21/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
MICHAEL KUNOWSKI (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 | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNANALYZED CONDITION DUE TO NON-COMPLIANT FIRE PROTECTION MANUAL OPERATOR ACTIONS
"As part of the License Amendment development to transition to NFPA 805, PINGP [Prairie Island Nuclear Generating Plant] Calculation ENG-ME-353, Mechanical MOV [Motor Operated Valve] Analysis to support IN-92-18 Response, revision 1, issued in 1998, was reviewed for applicability for the transition to NFPA 805. Recent consultation with an MOV engineer regarding the scope of the revision indicated ENG-ME-353 is out of date.
"On 12/21/2015, during technical review for a new weak link calculation, several MOVs were identified from the list of MOVs that are credited to be manually operated from outside the control room in the event of a fire in the control room or relay room per PINGP Procedure F5 Appendix B, Control Room Evacuation (Fire), that could be damaged if hot shorts were to bypass the torque and limit switches. There are also four other motor valves associated with the Gland Steam system of both Unit 1 and Unit 2 that were added to the procedure F5 Appendix B, Control Room Evacuation (Fire), that have not been analyzed for a weak link. This unanalyzed condition could impact the ability of plant operators to implement procedure F5 Appendix B, Control Room Evacuation (Fire).
"New hourly fire watch impairments were created for Fire Area 13 (Control Room) and Fire Area 18 (Relay and Cable Spreading Room) as compensatory measures.
"Therefore, this is an unanalyzed condition reportable under 10 CFR 50.72(b)(3)(ii)(B).
"The public health and safety is not impacted.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 51617 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KYLE SAYLER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 12/21/2015
Notification Time: 22:44 [ET]
Event Date: 12/21/2015
Event Time: 19:55 [CST]
Last Update Date: 12/21/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JACK WHITTEN (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 | Event Text LOSS OF TONE ALERT RADIO SYSTEM TOWER
"At 1955 CST on 12/21/2015, Cooper Nuclear Station was notified by the National Weather Service that the Shubert radio transmission tower was not functioning. This affects the tone alert radios used to notify the public in the event of an emergency condition. This is considered to be a major loss of the public prompt notification system capability and is reportable under 10CFR50.72(b)(3)(xiii).
"At 2017 CST, Nemaha, Richardson and Atchison county authorities within the 10 mile EPZ were notified of the condition and the effect on the tone alert radios and will utilize local route notification (backup notification method) making this condition reportable under 10CFR50.72(b)(2)(xi) for notification of other government agencies.
"Estimated return to service time is unknown. The cause of the failure is a loss of communication with the tower.
"The NRC Senior Resident Inspector has been notified of this condition." | |