| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/02/2012 - 03/05/2012 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 47693 | Rep Org: ROSEMOUNT NUCLEAR
Licensee: ROSEMOUNT NUCLEAR
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DUYEN PHAM
HQ OPS Officer: VINCE KLCO | Notification Date: 02/23/2012
Notification Time: 11:08 [ET]
Event Date: 02/16/2012
Event Time: [CST]
Last Update Date: 03/05/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
MEL GRAY (R1DO)
MIKE ERNSTES (R2DO)
PATTY PELKE (R3DO)
RICK DEESE (R4DO)
PART 21 GRP - EMAIL ()
| Event Text PART 21 REPORT - ROSEMOUNT PRESSURE TRANSMITTERS WITH NONZERO BASED CALIBRATIONS
The following information was received by facsimile:
"During the course of qualification testing to replace certain diodes identified for obsolescence, RNII [Rosemount Nuclear Instruments, Inc.] has determined that Model 1154 Series H range code 4-8 pressure transmitters with a significantly elevated or suppressed 4 mA point may not meet the published steam pressure/temperature accuracy specification.
"The out of tolerance condition observed during steam pressure/temperature qualification testing is not related to the replacement diode changes. It is an inherent performance characteristic related to large zero elevation or suppression. The steam pressure/temperature accuracy specification will be revised to account for nonzero based calibrations with a significantly elevated or suppressed 4 mA point.
"This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification.
"RNII recommends that users review the application where 1154 Series H range code 4-8 pressure transmitters are used to determine if there are safety considerations related to the revised steam pressure/temperature specification."
Rosemount Nuclear has provided instruments to the following list of domestic U.S. customers: Alabama Power; American Electric Power; Arizona Public Service/Pinnacle West; Bechtel Power; Constellation Energy; Dominion Nuclear Connecticut/Dominion Generation; Duke Energy; ECFS MCS; Edison Material Supply; Electro Mechanics; Entergy; Exelon Generation; Florida Power and Light; FPL Energy; Georgia Power; Northern States Power-Minnesota DBA XCEL Energy; Pacific Gas and Electric; Progress Energy Florida; Progress Energy Carolinas; PSEG Nuclear; South Carolina Electric and Gas; Southern California Edison; Southern Nuclear Operating Company; STP Nuclear Operating; Tennessee Valley Authority; TXU/Luminant; Westinghouse Electric. |
| Agreement State | Event Number: 47702 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: EASTMAN CHEMICAL COMPANY
Region: 1
City: KINGSPORT State: TN
County:
License #: R-82007-H15
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/28/2012
Notification Time: 13:09 [ET]
Event Date: 10/19/2010
Event Time: 16:30 [EST]
Last Update Date: 02/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - SOURCE CARRIER ON OHMART GAUGE FAILED TO RETRACT
The following was received from the State of Tennessee via facsimile:
"On 10/19/10, it was discovered that the source carrier on Ohmart gauge, Model SHLM-C, could not retract from the well pipe back into the source holder. An Ohmart technician attempted to repair the gauge without success. A visual inspection confirmed that the process materials had leaked into the well pipe around the source carrier preventing retraction of the source. A remediation team was called to retrieve the source carrier. The gauge contained Cesium-137, two sealed sources of 63 milliCuries each."
Event Report ID No.: TN-10-143 |
| Agreement State | Event Number: 47703 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: SAINT THOMAS HOSPITAL
Region: 1
City: NASHVILLE State: TN
County:
License #: R-19190-H14
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/28/2012
Notification Time: 13:09 [ET]
Event Date: 08/10/2009
Event Time: [EST]
Last Update Date: 02/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - EFFLUENT CONCENTRATIONS EXCEEDED REGULATORY LIMITS
The following was received from the State of Tennessee via facsimile:
"A pharmacy technician noted that the exhaust fan connected to the I-131 glove box was not working. Maintenance was contacted and found a broken fan belt which was repaired the same day. Up to 35% of the air exhaust of the I-131 vapor was not available for dilution. On 8/28/09, it was noted the effluent concentration of I-131 was over the limit of state regulations. It was immediately reported to the Radiation Safety Officer. An investigation revealed a bolus of I-131 was released through the ventilation system. Minor release in the room but the continuous air concentration in the pharmacist's breathing zone remained under regulatory limits. Surveys of the room revealed three locations of fixed contamination which were covered with cardboard and allowed to decay to background. All staff bioassays were below detectable limits."
Event Report ID No.: TN-09-110 |
| Agreement State | Event Number: 47704 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: EASTMAN CHEMICAL COMPANY
Region: 1
City: KINGSPORT State: TN
County:
License #: R-82007-H10
Agreement: Y
Docket:
NRC Notified By: DERA SHULTS
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/28/2012
Notification Time: 13:09 [ET]
Event Date: 01/19/2010
Event Time: [EST]
Last Update Date: 02/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - PROCESS GAUGE SHUTTER STUCK IN OPEN POSITION
The following was received from the State of Tennessee via facsimile:
"On January 19, 2010, during performance of routine shutter check, it was discovered that the shutter on an Ohmart Model SH-F2 source was stuck in the open position. In an attempt to open the shutter by hand, the shutter handle separated from the top of the housing. Two bolts attaching the handle were sheared off. The gauge was manufactured in 12/04 and is located on a column which is part of a polymer manufacturing process. The gauge contains 150 milliCuries of Cesium-137. Ohmart technicians were called to repair the shutter. No individuals were exposed to the excessive levels of radiation."
Event Report ID No.: TN-10-006 |
| Fuel Cycle Facility | Event Number: 47712 | Facility: B&W NUCLEAR OPERATING GROUP, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: KENNY KIRBY
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/01/2012
Notification Time: 12:12 [ET]
Event Date: 03/01/2012
Event Time: 09:15 [EST]
Last Update Date: 03/01/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
| Person (Organization):
MARK FRANKE (R2DO)
JAMES RUBENSTONE (NMSS)
FUEL GROUP via email ()
| Event Text EXTERNAL RADIATION LEVELS EXCEEDED PART 20 LIMITS DURING SHIPMENT
"Evaluation of LTC [Lynchburg Technology Center] AmBe Shipment issues for 03/01/12 receipt.
"The conditions for reporting under the requirements of 10 CFR 20 1906(d) have been met. QWI 14.1.10 Classification & Notification Criteria for Unusual Incidents Radiation Protection section - for shipments, bases reporting requirements on receipt of a shipment with radiation or contamination levels in excess of 10 CFR 20.1906(d). This requirement was exceeded and an NRC report is required. The truck cab sleeping area (normally occupied space) dose rate of 3.4 mRem/hr is greater than the allowable limit of 2.0 mRem/hr. The private carrier personnel state that they do not have dosimetry.
"Immediate Actions Taken: Digital photographs have been taken, confirmatory surveys (with other instruments) were taken, additional spot surveys were taken, the shipper has been notified, and an evaluation of the regulations has been made."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 47715 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHUCK GUALDONI
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/03/2012
Notification Time: 13:45 [ET]
Event Date: 03/03/2012
Event Time: 09:58 [EST]
Last Update Date: 03/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MARC FERDAS (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 OIL SHEEN IN HUDSON RIVER
"Indian Point Unit 3 is at 100% power. At approximately 0958 EST on 3/3/2012, an oil sheen was observed in the discharge canal and Hudson River. The size of sheen in river was about 10 square feet and the source of the sheen is not known at this time. Oil is suspected, but not yet confirmed. There is no adverse impact on the plant. All required notifications have been made, including the New York State Department of Environmental Conservation, Westchester County Department of Health, and the U.S. Coast Guard National Response Center."
The licensee has notified the NRC Resident Inspector. |
| Part 21 | Event Number: 47716 | Rep Org: ROSEMOUNT NUCLEAR
Licensee: ROSEMOUNT NUCLEAR
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DUYEN PHAM
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/02/2012
Notification Time: 16:51 [ET]
Event Date: 02/16/2012
Event Time: [CST]
Last Update Date: 03/05/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
LAWRENCE DOERFLEIN (R1DO)
MARK FRANKE (R2DO)
MARK RING (R3DO)
JACK WHITTEN (R4DO)
PART 21 GROUP-EMAIL ()
| Event Text PART 21 REPORT - RESISTANCE CHANGE AFFECTING ROSEMONT PRESSURE TRANSMITTERS
The following information was received by facsimile:
"During the course of qualification testing to replace certain diodes identified for obsolescence, an out of tolerance condition during steam pressure/temperature testing was observed on a test pressure transmitter in the qualification program. Through investigation into the out of tolerance condition, it was determined that the condition was not related to the replacement diode, but rather the result of the magnitude of a resistance change made to the transmitter temperature compensation circuitry during a final factory acceptance test. A brief description of the final acceptance test follows.
"During pressure transmitter final processing, a test is conducted on Model 1164 Series H pressure transmitters to assess the effects of ambient temperature changes on the 4mA to 20mA analog output. The temperature test is performed on each transmitter to verify the transmitter accuracy performance over normal operating temperatures from 40 F to 200 F. If the transmitter does not meet the acceptance criteria for the test, changes can be made to the compensating resistor values to optimize performance in the normal operating temperature range. If the resistance adjustment is too large, it has been determined that the accuracy of the pressure transmitter relative to the published steam pressure/temperature profile and accuracy specification may be exceeded during a steam pressure/temperature event.
"The magnitude of output shift during steam pressure/temperature conditions, that is attributable to the resistance changes made in final processing, is predictable based on the specific amount of resistance added or subtracted during the compensation process for each transmitter. Accordingly, RNII [Rosemount Nuclear Instruments, Inc] has reviewed the production records for the potentially affected transmitters and a revised steam pressure/temperature accuracy specification has been established for each shipped pressure transmitter. The revised steam pressure/temperature accuracy specification has been listed by serial number.
"This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification. Also note that for certain calibrations with large zero elevation and suppressions as defined in RMII's Part 21 Notification, dated February 23, 2012 (included as Attachment B), an alternate steam pressure/temperature accuracy specification is also provided for pressure transmitters that are affected by both notifications. All other 1154 Series H published specifications remain unchanged.
"On February 23, 2012, it was concluded that a substantial safety hazard may exist. RMII does not have sufficient information to determine the potential safety impact In plant applications. As a result, a notification about the potential substantial safety hazard is being made in accordance with 10 CFR Part 21 to customers who purchased affected 1154 Series H pressure transmitters.
"The manufacturing rework procedure 01153-3000 has been updated to limit the amount of acceptable resistance that may be added or subtracted during final testing. A revised steam pressure/temperature accuracy specification for each pressure transmitter impacted by this notification has been determined.
"RMII recommends that users review the application where 1154 Series H pressure transmitters are used to determine if there are safety considerations related to the revised steam pressure/temperature accuracy specification."
The United States nuclear sites associated with this Part 21 are: Farley, D.C. Cook, Palo Verde, ANO-1, Calvert Cliffs, Point Beach, Oconee, Catawba, Waterford 3, Braidwood, La Salle, Davis Besse, Crystal River 3, Vogtle, Millstone, Diablo Canyon, Salem, Hope Creek, San Onofre, South Texas, Watts Bar, Comanche Peak, and Wolf Creek. | |