| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/06/2017 - 09/07/2017 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52916 | Rep Org: NIST
Licensee: NIST
Region: 1
City: GAITHERSBURG State: MD
County:
License #: SNM-362
Agreement: Y
Docket:
NRC Notified By: MANUEL MEJIAS
HQ OPS Officer: STEVEN VITTO | Notification Date: 08/19/2017
Notification Time: 12:07 [ET]
Event Date: 08/18/2017
Event Time: 14:00 [EDT]
Last Update Date: 09/06/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(1) - UNPLANNED CONTAMINATION
| Person (Organization):
HAROLD GRAY (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
TYRONE NAQUIN (PM)
| Event Text UNPLANNED CONTAMINATION EVENT - BROKEN FLAME-SEALED GLASS AMPOULE
"The purpose of this communication is to provide additional details surrounding the circumstances that led to the identification of unplanned contamination in one of the laboratories designated as a restricted area under the US NRC license SNM-362. As indicated verbally during the initial report at 1207 EDT, and required by 10 CFR 30.50(b)(1), this event is described as having a broken flame-sealed glass ampoule that resulted in contamination of the lead-shielding storage area on top of the countertop and other surfaces within room C11 in building 245 of the NIST Gaithersburg, MD campus. This was discovered at approximately 1400 EDT on 8/18/2017.
"The ampoule contained a well-characterized solution of Am-241 with an activity of approximately 47 MBq (most restrictive ALI [Annual Limit on Intake] is 0.006 uCi) and is registered in our database as being in a solution of nitric acid.
"The initial report requirements of 10 CFR 30.50(b)(1)(i) through (iii) are satisfied by the phone notification and supplemented by this communication and attachments. Additional information regarding corrective actions taken and planned, as well as evaluations and/or assessments, will be provided to our Project Manager and Region I in the near future and the required written report will be provided within the required 30 days.
"After reporting event #52916, at the direction of the Radiation Safety Officer and with the support of the NIST Senior Management, multiple efforts will continue to evaluate the extent of the condition and a Stop Work Order will be issued effective today for all other laboratories at NIST Gaithersburg that store similar ampoules until the extent of condition is evaluated and/or mitigated.
"Extensive surveys of the area and air monitoring have confirmed that the contamination is isolated to portions of room C11."
Access has been restricted to room C11.
The licensee notified NRC R1 (Ullrich) and NRC HQ PM (Naquin) regarding this event.
* * * UPDATE FROM MANUEL MEJIAS TO HOWIE CROUCH AT 1209 EDT ON 9/6/17 * * *
The licensee received three bioassay results from personnel exposure to the contaminant. Two of the bioassays were negative. The third bioassay indicated the exposed individual received 9.1 REM whole body with 87 REM to the bone surface of the target organ. Additional bioassays are being performed.
The licensee notified R1 (Ullrich and Jackson) and HQ (Naquin).
Notified R1DO (Dentel), NMSS (Rivera-Capella), and NMSS Events Notification (email). |
| Agreement State | Event Number: 52939 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: CATALYST PAPER OPERATIONS INC.
Region: 3
City: BIRON State: WI
County:
License #: 141-2060-01
Agreement: Y
Docket:
NRC Notified By: KYLE WALTON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/30/2017
Notification Time: 16:18 [ET]
Event Date: 08/30/2017
Event Time: [CDT]
Last Update Date: 08/30/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANN MARIE STONE (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - SHUTTER FAILED OPEN
The following report was received via e-mail:
"On August 30, 2017, the licensee noticed that a shutter indicator light on a Pm-147 Honeywell-Measurex fixed gauge device, on a paper mill line, was not functioning correctly. The light was on and indicating that the shutter was closed, when the shutter was actually in the open position. However, the device shutter is still working and communicating as usual. The licensee utilized a survey meter to determine that even though the light was on, the shutter was open. The licensee roped off the area, instructed all operators to the status of the shutter, and re-instructed to always use a survey meter if they needed to approach the device and to assume the shutter is open. The licensee is continuing operations, but controlling access to the area while a fix is arranged. The licensee is in contact with the manufacturer to determine the next steps. The state is in contact with the licensee and will be continuing to follow the situation."
Wisconsin Event: WI 170013 |
| Power Reactor | Event Number: 52948 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JAY CAWLEY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/06/2017
Notification Time: 14:11 [ET]
Event Date: 09/06/2017
Event Time: 11:15 [EDT]
Last Update Date: 09/06/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GLENN DENTEL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO POTENTIAL RELEASE OF TRITIUM BEARING WATER AND SECONDARY CHEMICALS INTO THE PROTECTED AREA
"Inspection of an underground pipe used to discharge the contents of the Unit 3 Condensate Polishing Facility in accordance with the National Pollutant Discharge Elimination System (NPDES) Discharge Permit identified the potential for small amounts of water containing tritium and Secondary chemicals to be released to the ground within the plant Protected Area. The water met all permit limits for discharge to the normal discharge point. Groundwater tritium levels were well below reportable limits. The line has been removed from service. The Connecticut Department of Energy and Environmental Protection was notified at 1115 [EDT] on September 6, 2017.
"This event is being reported in accordance with 10CFR50.72(b)(2)(xi) for 'Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made." |
| Power Reactor | Event Number: 52950 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: JASON QUICK
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/06/2017
Notification Time: 15:41 [ET]
Event Date: 09/06/2017
Event Time: 11:57 [EDT]
Last Update Date: 09/06/2017 | 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):
GLENN DENTEL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM ON LOW REACTOR VESSEL WATER LEVEL
"On September 6, 2017 at 1157 [EDT], Nine Mile Point Unit 1 experienced an automatic reactor scram with a Main Steam Isolation Valve (MSIV) and Containment isolation. The scram was due to reactor vessel low water level. The cause of the reactor vessel low water level is under investigation. All control rods fully inserted. Following the scram, pressure was momentarily controlled through the use of the Emergency Condenser (EC) system. At 1205, pressure control was established through the main steam lines to the condenser through the turbine bypass valves. All plant systems responded per design following the scram. The reactor scram is a 4-hour report per 10 CFR 50.72(b)(2)(iv)(B).
"The following systems automatically actuated after the scram as expected. These system actuations are an 8-hour report per 10 CFR 50.72(b)(3)(iv)(A):
1. The High Pressure Coolant Injection (HPCI) system. HPCI initiated at 1157 and was reset at 1158 when RPV level was restored above the HPCI system low level actuation set point. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System.
2. The Core Spray system actuated, but did not discharge to the Reactor Coolant system. The Core Spray system was secured at 1216.
3. Containment and MSIV isolation on reactor vessel low-low water level signal.
"Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor vessel water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using the turbine bypass valves. The offsite grid is stable with no grid restrictions or warnings in effect.
"The licensee has notified the NRC Resident Inspector."
No safety relief valves lifted during the transient. The main steam isolation valves were opened after the isolation signal cleared to facilitate decay heat removal. Offsite power is supplying all plant loads. There was no effect on Unit 2.
The licensee notified New York State Department of Environmental Protection and will be issuing a press release. | |