| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/09/2016 - 09/12/2016 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 52215 | Rep Org: INTEGRITY TESTLAB
Licensee: INTEGRITY TESTLAB
Region: 1
City: NEW CASTLE State: DE
County:
License #: 07-30791-01
Agreement: N
Docket:
NRC Notified By: WILLIAM BATTING
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/01/2016
Notification Time: 13:11 [ET]
Event Date: 09/01/2016
Event Time: 11:15 [EDT]
Last Update Date: 09/01/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text UNABLE TO RETRACT SOURCE INTO SHIELDED POSITION
"At 1122 [EDT], the RSO [Radiation Safety Officer] for Integrity Testlabs [ITL], LLC, received a telephone notification from the field radiographer at the client's location that he was unable to retract the source fully into the shielded position. The radiographer attempted to retract the source twice. The radiographer realized the source was not going to get shielded because he noticed that the control cable housing was laying on equipment which was later determined to be approximately 500 degrees F. This melted the control cable housing and in turn prevented the complete retraction of the source into the shielded position. The radiographer kept the source to the fully exposed position within the 4HVL collimator and proceeded to extended the posted radiation area boundaries to 2mR/hr or less, then contacted the RSO at 1122 [EDT]. The RSO was approximately 50 miles away and stated he was on his way to assist in the recovery process. The company and RSO are authorized to perform recovery of sources.
"The radiographer then contacted his supervisor, who was the senior radiographer onsite. The supervisor also attempted to retract the source into the shielded position. The supervisor contacted the RSO and explained the situation. By direction from the RSO via telephone communication, the supervisor was able to disconnect the control housing at the remote control crank and pull the control cable so that the source was retracted into the shielded position. The radiography operations were terminated for the day. Surveys were performed after the source was shielded with no unusual readings. All equipment was returned to ITL's facility.
"The following self-reading pocket dosimeter readings were recorded at the conclusion of this event. The radiographer and assistant radiographer had performed 6 exposures for the day. The 6 exposures included the event.
Radiographer 100mR
Assistant 20mR
Supervisor 23mR during the recovery process
No radiographic personnel or member of the pubic was overexposed during the entire event.
"The affected equipment will be inspected, repaired or replaced, as needed.
"A follow report will be submitted to Region I as soon as practical.
"Equipment: QSA Global Model 880s #S1667 w/ IR-192 #32053G - 56.5Curies
25Ft Extreme Control Cables with two extreme guide tubes, each guide tube 7ft long and the outer most guide stop having a source stop.
One - 4HVL Tungsten collimator" |
| Power Reactor | Event Number: 52229 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: ANTON PESTKA
HQ OPS Officer: DONG HWA PARK | Notification Date: 09/09/2016
Notification Time: 03:59 [ET]
Event Date: 09/08/2016
Event Time: 18:56 [MST]
Last Update Date: 09/09/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
THOMAS HIPSCHMAN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF THE SEISMIC MONITORING SYSTEM COMPUTER
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10 CFR 50.73.
"This event is being reported pursuant to 10 CFR 50.72(b)(3)(xiii) for a loss of emergency assessment capability at the Palo Verde Nuclear Generating Station (PVNGS). On September 8, 2016 at 1856 [MST], seismic monitoring (SM) system computer AJSMNXYQI0001**INSTRU was determined to be non-functional due to a power spike which caused a temporary loss of power to the seismic instrumentation and resulted in a locked in the Control Room alarm. At 2305, I&C technicians re-booted the computer and verified the SM system was functioning.
"On September 8, 2016, at approximately 2353, further review of this equipment failure and the related impact to the capability of the SM system determined that this was a reportable loss of emergency assessment capability during the period between 1856 and 2305.
"This specific SM functions to provide indication that the Operational Basis Earthquake threshold has been exceeded following a seismic event and is used in the PVNGS Emergency Plan to perform classification for emergency action level HA1.1, Natural or Destructive Phenomena affecting Vital Areas. As a compensatory measure, PVNGS procedures for seismic event evaluation provide alternative methods for HA1.1 event classification with the SM out of service. Maintenance to correct the condition has been completed.
"The NRC Resident Inspector has been informed of this condition." |
| Power Reactor | Event Number: 52230 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JIM RITCHIE
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/09/2016
Notification Time: 12:55 [ET]
Event Date: 09/09/2016
Event Time: 10:23 [EDT]
Last Update Date: 09/09/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MEL GRAY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 99 | Power Operation | 99 | Power Operation | Event Text OFFSITE NOTIFICATION TO LOCAL AUTHORITIES DUE TO OUT-OF-SERVICE SEWAGE RADIATION MONITOR
"Oyster Creek Nuclear Station made notifications to local authorities that a sewage radiation monitor was out of service due to an equipment deficiency for greater than 24 hours. Alternate sampling methods are being utilized."
The licensee notified Ocean County Utilities Commission, Lacey Municipal Utilities, and the NRC Resident Inspector. |
| Power Reactor | Event Number: 52231 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN WHALLEY
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/09/2016
Notification Time: 20:01 [ET]
Event Date: 09/09/2016
Event Time: 17:39 [EDT]
Last Update Date: 09/09/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MEL GRAY (R1DO)
BERN STAPLETON (NSIR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text OFFSITE NOTIFICATION - RELEASE OF HYDROGEN GAS IN EXCESS OF THE REPORTABLE QUANTITY OF TEN POUNDS
"At 1739 [EDT] on Friday September 9, 2016 the Massachusetts Department of Environmental Protection and the Plymouth Massachusetts Fire Department were notified of a Hydrogen release in accordance with plant procedures and 310CMR40.300, Massachusetts Contingency Plan Notification for Oil and Hazardous Material; Identification and Listing of Oil and Hazardous Material, due to a release of hydrogen gas to the environment exceeding the reportable quantity of ten pounds. The Massachusetts DEP Tracking Number is RTN4-26311. The release was from the generator hydrogen cooling system. There was no plant damage. Hydrogen system pressure has been restored to the normal operating band with the Main Generator secured and is stable. The cause of the event is under investigation.
"This event posed no danger to the health and safety of plant personnel or members of the general public.
"The NRC Resident Inspector has been notified.'' |
| Power Reactor | Event Number: 52232 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: TOM COBBLEDICK
HQ OPS Officer: JEFF HERRERA | Notification Date: 09/10/2016
Notification Time: 07:23 [ET]
Event Date: 09/10/2016
Event Time: 03:43 [EDT]
Last Update Date: 09/10/2016 | 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):
KARLA STOEDTER (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC UNIT TRIP DUE TO MAIN GENERATOR LOCK-OUT
"At 0343 EDT, with the unit operating at approximately 100% full power, an automatic reactor trip occurred due to a Main Generator lock-out. The cause of the generator lock-out is being investigated at this time. All control rods fully inserted. Post trip, the Steam Feedwater Rupture Control System was actuated due to high Steam Generator 1 level. The cause of the high Steam Generator 1 level is being investigated at this time.
"The unit is currently in Mode 3 (Hot Standby) and stable, at approximately 550 degrees F and 2155 psig. Steam is being discharged through the Atmospheric Vent Valves for decay heat removal. There is no known primary to secondary leakage, and all safety systems functioned as expected.
"The NRC Resident Inspector has been notified of the event."
The licensee notified the State of Ohio, Ottawa and Lucas County. |
| Power Reactor | Event Number: 52234 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: BUCK DICKSON
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/11/2016
Notification Time: 17:44 [ET]
Event Date: 09/11/2016
Event Time: 14:51 [CDT]
Last Update Date: 09/11/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
THOMAS HIPSCHMAN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 93 | Power Operation | 93 | Power Operation | Event Text INADEQUATE DESIGN PROTECTION OF SAFETY-RELATED EQUIPMENT IDENTIFIED DURING TORNADO MISSILE IMPACT EVALUATION
"During performance of an extent of condition evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, Arkansas Nuclear One, Unit 1, identified non-conforming conditions in the plant design such that specific TS equipment on Unit 1 is considered not be adequately protected from tornado missiles. The reportable condition is postulated by tornado missiles entering the Unit 1 Controlled Access area, elevation 386', Upper North Electrical Penetration Room (UNEPR) through penetrating a hollow metal door and then striking safety related cables. A tornado could generate multiple missiles capable of striking the Unit 1 UNEPR and rendering both safety related emergency feedwater trains inoperable.
"This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety, and per 10 CFR 50.72(b)(3)(v)(B) and (D) for any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to (B) Remove residual heat, or (D) Mitigate the consequences of an accident.
"This condition was identified as part of an on-going extent of condition review of potential tornado missile related site impacts. Licensee Event Report (LER) 50-313/2016-002-00 was recently submitted addressing previously identified tornado missile vulnerabilities at the Unit 1 plant.
"Enforcement discretion per Enforcement Guidance Memorandum EGM 15-002 has been implemented and required actions taken. Corrective actions will be documented in a follow-on licensee event report.
"The licensee has notified the NRC Resident Inspector."
A similar evaluation is on going for Unit 2. | |