Event Notification Report for May 03, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/02/2016 - 05/03/2016
EVENT NUMBERS
51900519015190251903
Power Reactor
Event Number: 51900
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT URBANSKI
HQ OPS Officer: DONG HWA PARK
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT URBANSKI
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/03/2016
Notification Time: 15:13 [ET]
Event Date: 05/03/2016
Event Time: 08:33 [EDT]
Last Update Date: 05/03/2016
Notification Time: 15:13 [ET]
Event Date: 05/03/2016
Event Time: 08:33 [EDT]
Last Update Date: 05/03/2016
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):
MIKE ERNSTES (R2DO)
MIKE ERNSTES (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TEMPORARY LOSS OF CONTROL ROOM ENVELOPE BOUNDARY
"At 0833 [EDT] on May 3, 2016, security received an alarm on a Main Control Room (MCR) door. At 0847 [EDT], security notified the MCR staff of the door alarm and that the door was incapable of closure. At this time, both control room ventilation filtration trains (CREVS) were declared inoperable in accordance with Technical Specification 3.7.10, Condition B, due to the inoperability of the Control Room Envelope (CRE). Attempts to close the door were made, and it was identified that a screw had become wedged at the base of the door preventing it from latching. At 0855 [EDT], the screw was removed and the door verified to close as designed. CREVS was determined to be operable and LCO 3.7.10, Condition B was exited.
"The safety function of the CRE boundary is to ensure the in-leakage of unfiltered air into the CRE will not exceed the in-leakage assumed in the licensing basis analysis of Design Basis Accident (DBA) consequences to CRE occupants. In addition to an intact CRE boundary maintaining CRE occupant dose from a large radioactive release below the calculated dose in the licensing basis consequence analysis for DBAs, it also ensures the occupants are protected from hazardous chemicals and smoke.
"This condition had no impact to the health and safety of the public.
"The NRC Resident Inspector has been notified."
"At 0833 [EDT] on May 3, 2016, security received an alarm on a Main Control Room (MCR) door. At 0847 [EDT], security notified the MCR staff of the door alarm and that the door was incapable of closure. At this time, both control room ventilation filtration trains (CREVS) were declared inoperable in accordance with Technical Specification 3.7.10, Condition B, due to the inoperability of the Control Room Envelope (CRE). Attempts to close the door were made, and it was identified that a screw had become wedged at the base of the door preventing it from latching. At 0855 [EDT], the screw was removed and the door verified to close as designed. CREVS was determined to be operable and LCO 3.7.10, Condition B was exited.
"The safety function of the CRE boundary is to ensure the in-leakage of unfiltered air into the CRE will not exceed the in-leakage assumed in the licensing basis analysis of Design Basis Accident (DBA) consequences to CRE occupants. In addition to an intact CRE boundary maintaining CRE occupant dose from a large radioactive release below the calculated dose in the licensing basis consequence analysis for DBAs, it also ensures the occupants are protected from hazardous chemicals and smoke.
"This condition had no impact to the health and safety of the public.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 51901
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NJ
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/03/2016
Notification Time: 15:40 [ET]
Event Date: 05/03/2016
Event Time: 11:30 [EDT]
Last Update Date: 05/03/2016
Notification Time: 15:40 [ET]
Event Date: 05/03/2016
Event Time: 11:30 [EDT]
Last Update Date: 05/03/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
FRED BOWER (R1DO)
FFD GROUP (EMAI)
FRED BOWER (R1DO)
FFD GROUP (EMAI)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY POLICY VIOLATION
A non-licensed employee supervisor violated the fitness-for-duty policy during a random fitness-for-duty test. The employee's access to the plant has been denied.
The licensee has notified the NRC Resident Inspector.
A non-licensed employee supervisor violated the fitness-for-duty policy during a random fitness-for-duty test. The employee's access to the plant has been denied.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 51902
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/03/2016
Notification Time: 16:04 [ET]
Event Date: 05/03/2016
Event Time: 13:01 [EDT]
Last Update Date: 05/03/2016
Notification Time: 16:04 [ET]
Event Date: 05/03/2016
Event Time: 13:01 [EDT]
Last Update Date: 05/03/2016
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):
FRED BOWER (R1DO)
FRED BOWER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
ANOMALIES IDENTIFIED DURING VISUAL INSPECTION OF REACTOR VESSEL INTERNALS
"With Salem Unit One in a defueled condition during a planned refueling outage, anomalies were identified on baffle-former bolts while conducting a scheduled visual inspection of reactor vessel internals. Due to the visual anomalies, PSEG commenced ultrasonic inspection of the baffle-former bolts to determine the extent of condition and determine a repair plan.
"Based on initial results of ultrasonic inspections received on May 03, 2016, this condition was determined to be reportable pursuant to 10 CFR 50.72(b)(3)(ii)(B), since the as-found conditions were not previously analyzed.
"Additional details regarding the extent of condition will be supplied in the 60 day report.
"The NRC Resident Inspector has been informed. The licensee will notify State and local government agencies as appropriate."
"With Salem Unit One in a defueled condition during a planned refueling outage, anomalies were identified on baffle-former bolts while conducting a scheduled visual inspection of reactor vessel internals. Due to the visual anomalies, PSEG commenced ultrasonic inspection of the baffle-former bolts to determine the extent of condition and determine a repair plan.
"Based on initial results of ultrasonic inspections received on May 03, 2016, this condition was determined to be reportable pursuant to 10 CFR 50.72(b)(3)(ii)(B), since the as-found conditions were not previously analyzed.
"Additional details regarding the extent of condition will be supplied in the 60 day report.
"The NRC Resident Inspector has been informed. The licensee will notify State and local government agencies as appropriate."
Agreement State
Event Number: 51903
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: HONEYWELL INTERNATIONAL, INC.
Region: 1
City: SOUTH CHESTERFIELD State: VA
County: CHESTERFIELD
License #:
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: DONG HWA PARK
Licensee: HONEYWELL INTERNATIONAL, INC.
Region: 1
City: SOUTH CHESTERFIELD State: VA
County: CHESTERFIELD
License #:
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/03/2016
Notification Time: 15:41 [ET]
Event Date: 05/03/2016
Event Time: 00:00 [EDT]
Last Update Date: 05/03/2016
Notification Time: 15:41 [ET]
Event Date: 05/03/2016
Event Time: 00:00 [EDT]
Last Update Date: 05/03/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
AGREEMENT STATE REPORT - MISSING TRITIUM EXIT SIGNS
The following was received from the Commonwealth of Virginia via email:
"Honeywell International is authorized by general licenses to possess a number of tritium exit signs. It was discovered during an internal physical inventory that eight tritium signs were unaccounted. All were distributed by Safety Shield, Inc., and included one Model L3, s/n T8543, 11.5 curies; one Model XT, s/n S1075, 7.5 curies; and six Model 2040's, s/n 207011 through 207016, 7.5 curies each. The signs were received several years ago. Honeywell was unable to locate the signs despite a search of the facility and additional record review. Honeywell has submitted a procedural change in an effort to better track the remaining tritium signs at the facility. The licensee will keep the agency informed of any additional information.
"Event Report ID No.: VA-16-002"
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
The following was received from the Commonwealth of Virginia via email:
"Honeywell International is authorized by general licenses to possess a number of tritium exit signs. It was discovered during an internal physical inventory that eight tritium signs were unaccounted. All were distributed by Safety Shield, Inc., and included one Model L3, s/n T8543, 11.5 curies; one Model XT, s/n S1075, 7.5 curies; and six Model 2040's, s/n 207011 through 207016, 7.5 curies each. The signs were received several years ago. Honeywell was unable to locate the signs despite a search of the facility and additional record review. Honeywell has submitted a procedural change in an effort to better track the remaining tritium signs at the facility. The licensee will keep the agency informed of any additional information.
"Event Report ID No.: VA-16-002"
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf