| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/15/2012 - 02/16/2012 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 47423 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: HALEY AND ALDRICH, INC.
Region: 1
City: BOSTON State: MA
County:
License #: 20-8251
Agreement: Y
Docket:
NRC Notified By: TONY CARPENITO
HQ OPS Officer: JOHN KNOKE | Notification Date: 11/09/2011
Notification Time: 14:16 [ET]
Event Date: 11/09/2011
Event Time: [EST]
Last Update Date: 02/15/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RICHARD CONTE (R1DO)
ANDREW PERSINKO (FSME)
| Event Text AGREEMENT STATE REPORT - DAMAGED SOURCE ROD ON MOISTURE DENSITY GAUGE
The following information was provided by the state via email:
"On 11/9/11 [EST], the licensee reported to the Agency [Massachusetts Radiation Control Program] that a portable moisture density gauge had been damaged by a construction vehicle at a temporary job site. The source rod was bent and extended outside of the shielded gauge body so that it could not be returned to the closed position. The extended rod was left within the measuring hole so that the surrounding soil could provide shielding. A 15-plus-foot radius area was segregated around the damaged gauge. The licensee's radiation safety officer and radiation safety consultant were en route to the site to conduct and oversee the source recovery operation at the time of this report.
"The Agency [Massachusetts Radiation Control Program] considers this event to be open and ongoing.
"Manufacturer: Humboldt Scientific Inc, 5001 Series; Isotopes: Cs-137/ .011 Ci; Am-241/ .044 Ci."
* * * UPDATE ON 1/26/2012 AT 1307 EST FROM TONY CARPENITO TO MARK ABRAMOVITZ * * *
The following report was received via e-mail:
"The consultant and licensee submitted follow-up reports. An authorized gauge user was attending to the gauge and could not get the attention of the driver of the vehicle being driven in reverse just before gauge damage occurred. The source rod retracted into the gauge body successfully and the gauge was returned in its transport case to the licensee's facility on 11/9/11. A post-retrieval survey determined no residual contamination in the area. Personnel dosimeters worn during retrieval indicated minimal personnel exposure. The licensee presented employees retraining related to construction site safety on 11/10/11. Leak test results indicated no sealed source leakage. The gauge was returned to manufacturer for repairs.
Manufacturer : Humboldt Scientific, inc.
Model Number : 5001 EZ
Serial Number : 3544
Cesium-137 Source Serial Number : 9433GQ
Americium-241 Be Source Serial Number : NJ03832
"The Agency considers this event to be CLOSED."
Notified the R1DO (Dentel) and FSME (McIntosh).
* * * UPDATE ON 2/15/12 AT 0921 EST FROM ANTHONY CARPENITO TO MARK ABRAMOVITZ * * *
The following information was received via e-mail:
"The Cesium-137 source is an AEA Technology/QSA Model CDC.805, Capsule Type X8.
"The Americium-241 source is an AEA Technology/QSA Model AMN.V997, Capsule Type X1.
"The Agency still considers this event to be CLOSED."
Notified FSME (McIntosh) and R1DO (Powell). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 47545 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JAMES PRY
HQ OPS Officer: JOHN KNOKE | Notification Date: 12/21/2011
Notification Time: 21:37 [ET]
Event Date: 12/21/2011
Event Time: 13:59 [EST]
Last Update Date: 02/15/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
PATTY PELKE (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text GROUNDWATER LEVEL MAY EXCEED DESIGN ASSUMPTIONS
"On December 21, 2011, at 1359 hours EST, it was determined that the test instruction for the weekly groundwater level readings contained non-conservative acceptance criteria. The test instruction acceptance criteria for groundwater level exceeds the initial assumptions used in the Updated Safety Analysis Report (USAR) Chapter 15 accident analysis for 'Postulated Radioactive Releases due to Liquid Containing Tank Failures.' The issue was identified during the conduct of a prompt functionality assessment evaluating the plant underdrain system performance and to ensure all USAR described functions were being met.
"The test instruction acceptance criteria is less than 575 feet. The calculation supporting the Chapter 15 accident analysis assumes an initial groundwater elevation of 568 feet in order to accumulate a sufficient volume of groundwater to dilute the tank inventory prior to exiting the underdrain system. The accumulation volume results in hold up time allowing for mixing and radioactive decay. With the degraded performance of the underdrain system pumps and high precipitation, the groundwater level had risen above 568 feet but was still less than 575 feet. A preliminary engineering evaluation has determined that significant margin exists in the calculation. A calculation revision is being pursued in parallel with this notification.
"Compensatory actions involving the repair of 1 permanent non-safety pump and installation of temporary pumps were previously initiated and the groundwater levels are decreasing. Restoration of the remaining permanent plant pumps continues.
"The NRC Resident Inspector has been notified."
* * * RETRACTION ON 2/15/12 AT 1315 EST FROM LLOYD ZERR TO ERIC SIMPSON * * *
"The calculation supporting the USAR Chapter 15 accident analysis was reviewed and subsequently revised. The revised calculation verifies and initial groundwater elevation of 575 feet is consistent with the preliminary assessment that substantial margin existed in the calculation for the underdrain system. Because the condition reported in Event Number 47545 was not an event or condition that results in the nuclear power plant being in an unanalyzed condition that degrades safety, the condition is not reportable, and this notification is retracted. The evaluation for this condition is documented in condition report 2011-07169."
The NRC Resident Inspector and R3DO (Passehl) were notified. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 47582 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: RUSS LONG
HQ OPS Officer: JOHN KNOKE | Notification Date: 01/10/2012
Notification Time: 04:49 [ET]
Event Date: 01/10/2012
Event Time: 04:36 [EST]
Last Update Date: 02/15/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JAMES TRAPP (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 25 | Power Operation | 0 | Hot Standby | Event Text EXCESSIVE LEAKAGE FROM RCP SEAL RETURN
"Plant shutdown from 100% due to increased leakage from 21 RCP [Reactor Coolant Pump] seal return was commenced at 0100 EST. A manual reactor trip was actuated in accordance with plant procedures at 25% power. Auxiliary feedwater pump was placed in service prior to the reactor trip, per plant procedures. Decay heat is being removed via the condenser steam dumps. All offsite power sources are available. All equipment operated as expected."
The licensee has notified the NRC Resident Inspector and other government agencies.
* * * RETRACTION FROM CHARLES ROKES TO HOWIE CROUCH AT 0940 EST ON 2/15/12 * * *
"Subsequent review concluded the condition did not meet reporting criteria. A normal plant shutdown was initiated in accordance with plant procedures for a known problem with the 21 RCP # 1 seal whose seal leakoff rate had reached an administrative alarm limit. Shutdown was not required by the Technical Specifications. On January 10, 2012, at 0100 hours [EST] a plant shutdown commenced per plant operating procedure 2-POP-2.1. At 0436 hours, the reactor was manually tripped in accordance with procedure 2-POP-3.1. This event is not reportable as the reactor trip was part of a normal shutdown for corrective maintenance."
The licensee has notified the NRC Resident Inspector. Notified R1DO (Powell). |
| Agreement State | Event Number: 47659 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: BP PRODUCTS NORTH AMERICA INC.
Region: 4
City: TEXAS CITY State: TX
County:
License #: L00254
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: VINCE KLCO | Notification Date: 02/11/2012
Notification Time: 10:32 [ET]
Event Date: 02/09/2012
Event Time: 18:00 [CST]
Last Update Date: 02/15/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4DO)
PAUL MICHALAK (FSME)
| Event Text AGREEMENT STATE REPORT - INDUSTRIAL GAUGE STUCK SHUTTER
The following information was received by email:
"On February 10, 2012, the Agency [Texas Department of State Health Services] was notified by the licensee that the shutter on an Ohmart model SH-LG 2 nuclear gauge containing 8.5 curies of Cesium-137 was found to be stuck in the open position. Open is the normal position for the shutter and the failure does not pose any additional exposure risk. The licensee is trying to lubricate the operating arm in an effort to free the shutter. The licensee has contacted the manufacturer for assistance. Additional information will be provided in accordance with SA-300."
Texas Incident: I-8932 |
| Agreement State | Event Number: 47661 | Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: WAYPOINT ENTERPRISES, INC.
Region: 1
City: TUCKERTON State: NJ
County:
License #: RAD110001-507
Agreement: Y
Docket:
NRC Notified By: JENNY GOODMAN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/13/2012
Notification Time: 16:44 [ET]
Event Date: 02/13/2012
Event Time: [EST]
Last Update Date: 02/13/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY POWELL (R1DO)
PAUL MICHALAK (FSME)
| Event Text AGREEMENT STATE REPORT - CRUSHED TROXLER GAUGE
The following information was received via facsimile:
A dump truck ran over a Model 3440 Troxler portable gauge on the shoulder of the NJ Garden State Parkway at mile marker 54. The Troxler portable gauge was a model 3440 containing 8 mCi Cs-137 and 40 mCi Am-241.
* * * UPDATE ON 2/15/12 AT 11:45 FROM JAMES McCULLOUGH TO KARL DIEDERICH VIA E-MAIL * * *
"NJDEP RMP [New Jersey Department of Environmental Protection Radioactive Materials Program] staff responded to investigate the incident and observe the licensee's actions to recover the damaged device. Staff performed radiation area surveys and wipe tests to assess the situation. The licensee hired a consulting physicist who was observed (at about 9PM) while the device was recovered, shielded, and prepared for transport back to the licensee's office storage location."
Notified R1DO (Powell) and FSME EO (Giantelli). |
| Power Reactor | Event Number: 47664 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN LAUDENBACH
HQ OPS Officer: ERIC SIMPSON | Notification Date: 02/15/2012
Notification Time: 12:25 [ET]
Event Date: 02/15/2012
Event Time: 08:25 [CST]
Last Update Date: 02/15/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DAVE PASSEHL (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO INADVERTENT MANUAL SIREN ACTIVATION
"At 0825 CDT on 2/15/2012, the Monticello Nuclear Power Generating Plant (MNGP) received a report from the Sherburne County Sheriff Dispatcher that there had been an inadvertent manual initiation of Emergency Preparedness sirens in the county while performing siren testing. All plant conditions/parameters are normal. A total of 48 emergency sirens were on for approximately one minute before being secured. All sirens are currently functional. "
"Sherburne County and the site NRC Resident Inspector have been notified"
The licensee also notified the Wright County offices. |
| Power Reactor | Event Number: 47665 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DON TAYLOR
HQ OPS Officer: KARL DIEDERICH | Notification Date: 02/15/2012
Notification Time: 15:33 [ET]
Event Date: 02/15/2012
Event Time: 12:44 [EST]
Last Update Date: 02/15/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
BINOY DESAI (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 | Event Text OFFSITE NOTIFICATION OF SEWAGE SYSTEM RELEASE
"At 12:44 on 2/15/2012, the Virginia Department of Environmental Quality was notified of a sewage system release that had the potential to reach state waters. On 2/14/2012, it was identified that water was flowing from a manhole cover near the North Anna training building. Further review identified the training building sewage lift station had lost power and that the water line in the manhole discharges to the lift station. It was estimated that approximately 120-200 gallons of untreated water reached the ground around the manhole before power was restored to the lift station. Upon further investigation, the station could not confirm whether untreated water reached Lake Anna."
The NRC Resident Inspector has been notified. | |