| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/03/2017 - 10/04/2017 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52990 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: US STEEL CORPORATION - CLAIRTON WORKS
Region: 1
City: CLAIRTON State: PA
County:
License #: PA-1280
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: DONALD NORWOOD | Notification Date: 09/25/2017
Notification Time: 08:23 [ET]
Event Date: 08/25/2017
Event Time: [EDT]
Last Update Date: 09/25/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK / BROKEN SHUTTER
The following information was received via email:
"On September 22, 2017, the licensee informed the Department [PA DEP Bureau of Radiation Protection] of a failure of a collimator block. This event is reportable per 10 CFR 30.50(b)(2).
"On August 25, 2017, the licensee identified a failure of the collimator block attached to the shutter assembly on one of its Thermo Measure Tech Model 5204 gauges containing 4 curies of Cesium-137. The gauge was immediately removed from service. A licensed service provider was contacted and the broken shutter mechanism was removed and replaced with a spare. The shutter mechanism was then tested and confirmed as operating properly. Survey results indicated no abnormal amounts of radiation in the area before or after the repair work. All regulatory precautions were taken and no overexposures occurred.
"The cause of the event was equipment failure. The Department will perform a reactive inspection. A service provider has already corrected the problem. More information will be provided upon receipt."
PA Event Report ID No.: PA170013 |
| Agreement State | Event Number: 52991 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: IPSCO KOPPEL TUBULARS, LLC
Region: 1
City: AMBRIDGE State: PA
County:
License #: PA-1050
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: VINCE KLCO | Notification Date: 09/25/2017
Notification Time: 14:04 [ET]
Event Date: 09/24/2017
Event Time: [EDT]
Last Update Date: 09/25/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK / BROKEN SHUTTER
The following information was received from the Commonwealth of Pennsylvania via email:
"Notifications: On September 25, 2017, the licensee informed the Department [PA DEP Bureau of Radiation Protection] of a failure of an electronic component of a fixed gauge. It is reportable per 10 CFR 30.50(b)(2)(i).
"Event Description: The electronic component of the automatic shutter on an IMS Model 5301-01 gauge containing approximately 20 curies of Cesium-137 failed to close on its own. The licensee immediately notified the RSO, as per their emergency procedure, who was able to remotely log in to the computer software system and bypass the automatic mode to close the shutter. The gauge is housed in a secure and entry restricted enclosure and instructions have been given to all operators to ensure that the shutter is closed while not in use. The manufacturer, IMS, was notified and is scheduled to make repairs on September 26, 2017. All regulatory precautions were taken and no overexposures have occurred.
"Cause of the Event: Equipment failure.
"ACTIONS: The Department will perform a reactive inspection. The manufacturer has already been scheduled to correct the problem. More information will be provided upon receipt."
PA Event Report ID No.: PA170014 |
| Agreement State | Event Number: 52993 | Rep Org: KALISPELL REGIONAL MEDICAL CENTER
Licensee: KALISPELL REGIONAL MEDICAL CENTER
Region: 4
City: KALISPELL State: MT
County:
License #: 25-15463-01
Agreement: N
Docket: 3009152
NRC Notified By: ANDRE VANTERPOOL
HQ OPS Officer: VINCE KLCO | Notification Date: 09/26/2017
Notification Time: 15:39 [ET]
Event Date: 05/01/2017
Event Time: [MDT]
Last Update Date: 09/27/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
DAVID PROULX (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text MEDICAL EVENT WRITTEN DOSE DIRECTIVE IS DIFFERENT THAN PRESCRIBED DOSE
An endocrinologist specified a therapy dose of 20 milliCuries of I-131. An authorized dose directive was incorrectly written for 30 milliCuries of I-131. The patient was administered the initially determined dose of 20 milliCuries of I-131. Medical personnel determined that there was no impact on the patient.
Hospital supervision notified the on-site Authorized User, the Radiation Safety Officer and the Medical Physicist.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
* * * UPDATE AT 1345 EDT ON 9/27/17 FROM ANDRE VANTERPOOL TO RICHARD L. SMITH * * *
The actual event date was May 1, 2017, and the discovery date was September 25, 2017, at approximately 1500 MDT.
Notified R4DO (Proulx) and NMSS Events Notification (via email). |
| Power Reactor | Event Number: 52998 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: SHANNON GAYDOS
HQ OPS Officer: JEFF HERRERA | Notification Date: 10/03/2017
Notification Time: 15:52 [ET]
Event Date: 10/02/2017
Event Time: 11:15 [CDT]
Last Update Date: 10/03/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
RAY KELLAR (R4DO)
PART 21/50.55 REACTO (EMAI)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 96 | Power Operation | 96 | Power Operation | Event Text INITIAL PART 21 NOTIFICATION - CAMERON MODEL 752B DIFFERENTIAL PRESSURE TRANSMITTERS
"This report is made per 10 CFR Part 21.21(d)(3)(i) on the identification of a defect or a failure to comply.
"By the letter dated August 31, 2017, Westinghouse notified Callaway Plant that they were unable to complete a 10 CFR 21.21(a) evaluation for a product advisory which was issued by Cameron Measurement Systems for a concern with the Model 752B transmitter product line. The product advisory identified the potential for instability in the transmitter output signal under certain grounding conditions. Callaway was supplied transmitters that could be affected under Westinghouse part numbers 8765D64G03, 8765D64G04, and 8765D64G05. The Westinghouse notification letter served as the transfer of reporting responsibilities for this concern from Westinghouse to Callaway in accordance with 10 CFR 21.21(b).
"The 10 CFR Part 21 evaluation is based on the technical information provided by Westinghouse. The notification letter describes that shifts up to 10-20 percent of instrument scale (1.6-3.2mA) can be observed within the transmitter output under the grounding conditions such as those introduced by the original equipment manufacturer during testing. Westinghouse evaluations concluded that such instabilities would be self-revealing within plant applications for which the transmitter output signal was supplied to a Westinghouse 7300 system, assuming the transmitter stanchion was grounded. Not all transmitters within this product line were subject to this concern.
"On 10/02/2017 Callaway personnel completed the 10 CFR Part 21 evaluation. Of the transmitters identified above, only one is currently installed at Callaway in location BNLT0930, Refueling Water Storage Tank Protection A Level Transmitter. No instabilities (oscillations) have been observed in this transmitter but plans are being made to replace the transmitter.
"If one of the susceptible transmitters were installed for RCS flow application (low flow reactor trip function), the allowed sensor drift to accommodate changes in transmitter performance would be required to be limited to 1percent of instrument span per an 18-month operating period. Current margin available within the set point uncertainty analysis for this Reactor Trip function is 0.62 percent of instrument span. The observed shift in output of 10-20 percent of instrument span would thus exceed the available margin for this protective function. Therefore, the safety function for this device could not be assured for all transmitter configurations. This condition could create a substantial safety hazard due to the loss of safety function of a basic component which meets the criteria of major degradation of essential safety-related equipment.
"For the situation at Callaway, no other reporting criteria apply since there is no evidence that the installed transmitter BNLT0930 is susceptible to the concerns noted in the product advisory.
"The NRC Resident Inspector has been notified of this issue." |
| Power Reactor | Event Number: 52999 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: BRUCE HUGO
HQ OPS Officer: JEFF HERRERA | Notification Date: 10/03/2017
Notification Time: 16:58 [ET]
Event Date: 10/03/2017
Event Time: 08:00 [PDT]
Last Update Date: 10/03/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RAY KELLAR (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text SECONDARY CONTAINMENT INOPERABLE DUE TO UNEXPECTED ISOLATION OF EXHAUST VALVE
"On October 3, 2017, at 0800 PDT, Reactor Building (Secondary Containment) pressure momentarily rose above the Technical Specification (TS) limit. Secondary Containment was declared inoperable and TS Action Statement 3.6.4.1.A was entered. The pressure rise was due to unexpected isolation of an exhaust valve in the Reactor Building ventilation system during electrical switchgear inspections. The cause of the closure is still under investigation.
"The Control Room operators reopened the Reactor Building exhaust valve and pressure returned to within limits automatically. Secondary Containment was declared operable at 0802 PDT and TS Action Statement 3.6.4.1.A was exited.
"This condition is being reported under 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D) for an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material and accident mitigation."
The NRC Resident Inspector has been notified. | |