| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/04/2008 - 04/07/2008 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43853 | Rep Org: INVENSYS PROCESS SYSTEMS
Licensee: INVENSYS PROCESS SYSTEMS
Region: 1
City: FOXBORO State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID GOLDEN
HQ OPS Officer: JASON KOZAL | Notification Date: 12/19/2007
Notification Time: 14:41 [ET]
Event Date: 11/02/2007
Event Time: [EST]
Last Update Date: 04/04/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
JAMES TRAPP (R1)
ERIC DUNCAN (R3)
THOMAS FARNHOLTZ (R4)
PART 21 GROUP ()
SCOTT SHAEFFER (R2)
VERN HODGE E-MAIL (NRR)
| Event Text PART 21 NOTIFICATION - FAILURE TO FULLY COMPLY WITH THE REQUIREMENTS FOR DEDICATION OF COMMERCIAL GRADE ITEMS
"In accordance with 10CFR21, this letter is to inform you that Invensys Systems, Inc. (d/b/a Invensys Process Systems (IPS)) has identified a failure to fully comply with the requirements for Dedication of Commercial Grade Items (e.g. fuses, resistors, capacitors, etc.) provided to some of our nuclear customers. These parts, certified as safety-related basic components, were not subject to verification of functional performance characteristics as part of the Dedication process and therefore if not installed and tested in their intended application could represent a potential safety hazard.
"This condition was identified during the NUPIC (Nuclear Procurement Issues Committee) joint audit of our Foxboro, Massachusetts facility and immediate notification was provided to the member utilities through their web-based system. This Failure to Comply was confirmed on 11/2/07 and, based on our records, has been determined to be limited to the customers, orders and parts identified in [the report].
"Invensys has taken immediate corrective action to rectify the situation in that these parts are no longer provided as safety-related and we will be providing separate notification to each of the nuclear customers listed in [the report]. It should be noted that the subject materials were all controlled and provided in accordance with the approved IPS procedures which include requirements for inspections verifying the appropriate manufacturer, part number, markings and other physical characteristics. If these items have been properly installed in the intended Foxboro equipment, functional performance is typically verified through subsequent component or system-level testing."
The following customers are effected by this issue: American Electric Power, Arizona Public Service, Dominion Nuclear, Entergy, Exelon, First Energy, Indiana Michigan Power Co., NPPD, OPPD, Constellation, Union Electric, and Wolf Creek.
* * * UPDATE ON 4/4/2008 AT 1633 FROM DAVID GOLDEN TO MARK ABRAMOVITZ * * *
An updated list of parts and affected utilities was distributed. The affected utilities will be notified next week. The affected utilities are:
Ameren UE
American Electric Power
Amergen Energy Co LLC
Arizona Public Service
Arkansas Power & Light
Baltimore Gas & Electric
Commonwealth Edison
Connecticut Yankee Atomic
Consolidated Edison Company of New York
Detroit Edison
Dominion Nuclear
Duquesne Light
Edison Material Supply LLC
Entergy (Operations & Vermont Yankee)
Exelon Nuclear
Nine Mile Point Nuclear Station
First Energy Corp
Florida Power & Light (and FPL Seabrook)
Georgia Power
Gina Nuclear Power Plant
GPU Nuclear
Indiana Michigan Power Company
Iowa Public Power District
Maine Yankee Atomic Power
Nebraska Public Power District
New York Power Authority
Northern States Power Company
Nuclear Management Company
Omaha Public Power District
Pacific Gas & Electric Company
PECO Energy Company
Philadelphia Electric Company
Portland General Electric Company
Progress Energy (Carolinas & Florida)
Southern California Edison
Toledo Edison
TVA
Virginia Power Company
Westinghouse Electric
Wisconsin Public Service Corp.
Wolf Creek Nuclear Operating
Notified the R1DO (Hansell), R2DO (Evans), R3DO (Skokowski), R4DO (Lantz), NRR (Hodge and Thorpe via e-mail), and FSME (Jankovich via e-mail). |
| General Information or Other | Event Number: 44113 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: TIGUE CONSTRUCTION COMPANY, INC.
Region: 4
City: GLENWOOD State: AR
County:
License #: ARK-0867
Agreement: Y
Docket:
NRC Notified By: STEVE MACK
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/01/2008
Notification Time: 10:52 [ET]
Event Date: 03/31/2008
Event Time: 15:30 [CDT]
Last Update Date: 04/01/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RYAN LANTZ (R4)
GREG MORELL (FSME)
ILTAB (via email) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The following information was received from the State of Arkansas via email (quotations omitted for readability):
The Arkansas Department of Health, Radioactive Materials Program, is reporting that one of their licensees, Tigue Construction Company, Inc., has a Troxler moisture/density gauge that is stolen/missing from a pickup truck some time during the day in or near Brinkley, Arkansas. The licensee became aware of the missing gauge at 15:30 on March 31, 2008 after loading the gauge in the truck at the office in Glenwood, Arkansas that morning. The licensee has stated that the gauge, transport case and chains are missing. The licensee made one stop in Little Rock and observed that gauge in the truck during that stop. The licensee has filed a police report with the Brinkley Police Department.
The Troxler gauge is a Model 3440, S/N 27381, and contains 40 milliCuries of Am-241:Be and 8 milliCuries of Cesium-137.
The Arkansas Department of Health prepared a press release on the event.
The licensee verbally indicated that the gauge was properly secured in the truck at the time. The Arkansas Department of Health is investigating the circumstances surrounding this event.
Arkansas Department of Health notified Brinkley Police Department, Monroe County Sheriff's Office, Arkansas Department of Emergency Management (Arkansas State Police, Arkansas Highway Patrol), State of Mississippi, State of Tennessee [and] NRC Region IV.
Arkansas has assigned Event Report ID No: AR-03-08-01
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| General Information or Other | Event Number: 44116 | Rep Org: NV DIV OF RAD HEALTH
Licensee: APEX TESTING COMPANY
Region: 4
City: LAS VEGAS State: NV
County: CLARK
License #: 00-11-0598-01
Agreement: Y
Docket:
NRC Notified By: KAREN BECKLEY
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/02/2008
Notification Time: 15:21 [ET]
Event Date: 04/02/2008
Event Time: 04:30 [PDT]
Last Update Date: 04/02/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RYAN LANTZ (R4)
GREG MORELL (FSME)
ILTAB via email ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT INVOLVING STOLEN TROXLER MOISTURE DENSITY GAUGE
On 04/02/08 at 0400 PDT, the Authorized Gauge User checked out a Troxler Model #3440, S/N 30441, from his company and was enroute to the jobsite when he received a call that the job was cancelled. He went home to have breakfast at 0430 PDT. At 0500 PDT, he found that the chains securing the device for transport had been cut and the gauge was missing from the transport vehicle parked at the users home.
The gauge contains two sources: 9 mCi Cs-137 and 44 mCi Am-241:Be. The last leak test was performed on 03/04/08. The licensee notified the Nevada Highway Patrol and Las Vegas Metro Police of the theft. A contributing factor to the theft may have been the lack of two tangible barriers securing the gauge.
NV Event Report ID No.: NV-NV080002
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| Other Nuclear Material | Event Number: 44117 | Rep Org: PONZE I&M ENGINEERING LAB, INC.
Licensee: PONZE I&M ENGINEERING LAB, INC.
Region: 1
City: COTO LAUREL State: PR
County:
License #: 52-24908-02
Agreement: N
Docket:
NRC Notified By: JOSE IRIZARRY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/03/2008
Notification Time: 08:23 [ET]
Event Date: 04/03/2008
Event Time: [EDT]
Last Update Date: 04/05/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
SAM HANSELL (R1)
GREG MORELL (FSME)
ILTAB (via e-mail) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text STOLEN CPN MOISTURE DENSITY GAUGE
The licensee Radiation Safety Officer reported that a company pick-up truck, that had a moisture density gauge stored in the bed, was stolen from in front of the apartment complex of the Authorized User. The apartment was located in Guaynabo, Puerto Rico, which is remotely located from the licensee home office located in Coto Laurel, Puerto Rico.
The gauge is a CPN Model MC-1DRP, S/N 60703285, which contains 10 mCi of Cs-137 and 50 mCi of Am: Be. The gauge was last leak checked on October 15, 2007. The gauge was secured to the truck in a metal case mounted to the chassis of the truck and secured with the gauge lock, the gauge case lock and two locks on the metal storage case.
The stolen truck was a white 1996 Ford Ranger pick-up with Puerto Rican tag number 557-167.
The licensee notified the Puerto Rico State Police of the theft of the truck and gauge.
* * * UPDATE FROM JOSE IRIZARRY TO HOWIE CROUCH ON 04/05/08 @ 0809 HRS EDT * * *
Mr. Jose Irizarry, RSO for Ponze, reported that at 0430 EDT he was notified by Puerto Rico State Police that they had recovered the moisture density gauge in San Juan, Puerto Rico. The gauge was still locked in its storage container and was returned to the Authorized User.
Notified R1DO (Hansell), FSME (White) and ILTAB (via e-mail).
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| General Information or Other | Event Number: 44119 | Rep Org: SHAW AREVA MOX SERVICES, LLC
Licensee: ENERGY & PROCESS CORPORATION
Region: 1
City: AIKEN State: SC
County:
License #:
Agreement: Y
Docket: 070-0309
NRC Notified By: DAVID STINSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/04/2008
Notification Time: 14:30 [ET]
Event Date: 02/06/2008
Event Time: [EDT]
Last Update Date: 04/04/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
SAM HANSELL (R1)
CAROLYN EVANS (R2)
JOHN JANKOVICH (FSME)
| Event Text PART 21 - REINFORCING BARS BELOW ACI STANDARDS
"The purpose of this letter is to inform the NRC Operations Center that Shaw AREVA MOX Services, LLC (MOX Services) has identified a deviation associated with reinforcing bar supplied by Energy and Process Corporation (E&P).
"The condition involves reinforcing bars (rebar) supplied by E&P that have a bend radius below the minimum specified by ACI Standard 315-99 and ACI Standard 349-97. The condition was initially observed on 06 February 2008. The extent of condition determination found that a significant portion of bent rebar in all sizes failed to meet the minimum bend radius specified by ACI Standard 315-99 and ACI Standard 349-97. Based on this finding, it was concluded that a similar nonconforming population could be present embedded in those areas of the plant where concrete had already been poured.
"MOX Services has determined that the IROFS [Item Relied On For Safety] function of the BMF structure was not diminished by the rebar installed in concrete poured to date and that a substantial safety hazard would not result in the MFFF [Mixed Oxide Fuel Fabrication Facility] if the deviation had not been discovered. For industry awareness, we have conservatively chosen to report this deviation under the provisions of 10 CFR 21.21(d)(3)(i)." |
| Power Reactor | Event Number: 44120 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN GARECHT
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/04/2008
Notification Time: 17:39 [ET]
Event Date: 04/04/2008
Event Time: 12:59 [EDT]
Last Update Date: 04/04/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
SAM HANSELL (R1)
|
| 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 ACCIDENT MITIGATION - COMMON CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM
"Salem Unit 1 was placed in a configuration that affected the ability to mitigate the consequences of an accident due to an inadvertent actuation of the common control room emergency air conditioning system (CREACS). CREACS was actuated as a result of an invalid Control Room air intake duct radiation monitor initiated on April 4, 2008 at 1259 hours. Salem Unit-2 is currently defueled. Salem Unit 1 is in Mode 1 at 100% power. Unit 1 has two shutdown LCOs in effect. The first is for the CREACS system, which is shared between Unit 1 & 2, being aligned for single train operation with the Unit 2 CREACS train out of service per LCO 3.7.6. The second shutdown LCO is for two outside air intake dampers being inoperable for scheduled maintenance. With Unit 2 having an invalid Radiation Monitor signal, the CREACS system actuates in accident pressurized mode. This mode of actuation starts the CREACS fans, isolates the Control Room Envelope from the normal control room ventilation system and aligns the two sets of CREACS outside air intake dampers. With a Unit 2 Radiation Monitor signal, the Unit 2 CREACS intake dampers close and the Unit 1 CREACS intake dampers open. These damper positions are locked in until manually reset. With only one train of CREACS operable, the dose analysis indicates that the requirements of General Design Criterion (GDC) 19 can only be met during the worst case design basis accident if the Unit 1 CREACS intake dampers are closed and the Unit 2 CREACS intake dampers open. Therefore, until the CREACS intake dampers were reset and realigned, Salem Unit 1 would not have been able to mitigate the consequences of an accident and is reportable in accordance with 10CFR50.72(b)(3)(v)(D). The CREACS system actuation was reset after the failed radiation monitor (1R1B ch II) was removed from service and the dampers were re-aligned to their pre actuation alignment at 1316 hours, restoring Salem Unit 1 to within the assumptions of the dose analysis. Total duration in the condition was 17 minutes.
"The only piece of major equipment out of service on Salem Unit 1 is the 15 Service water pump which is out of service for scheduled maintenance."
The Licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44121 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: DAVID BALFOUR
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/06/2008
Notification Time: 14:13 [ET]
Event Date: 04/06/2008
Event Time: 13:17 [EDT]
Last Update Date: 04/06/2008 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
SAM HANSELL (R1)
THEODORE QUAY (NRR)
JIM DYER (NRR)
JEFFREY CRUZ (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text UNUSUAL EVENT FROM REACTOR COOLANT SYSTEM LEAKAGE
Millstone unit 2 entered a refueling outage on 4/6/2008. The plant was in the process of placing shutdown cooling in service when at 1236 a 10-15 gpm leak was detected by decreasing pressurizer level. The release path was determined to be from the Reactor Coolant System (RCS) to the Refueling Water Storage Tank (RWST). Pressurizer level is stable and RWST level is rising slowly. Two charging pumps are available for RCS makeup. Decay heat is being removed with Atmospheric Dump Valves. The vent line on the RWST does not contain a radiation monitor and this is an potential unmonitored radiation release path.
The Unusual Event was declared at 1317. The leak was terminated at 1320. Monitoring of the potential release path commenced at 1610.
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 4/6/2008 AT 1910 FROM WAYNE GAMMON TO MARK ABRAMOVITZ * * *
"The leak path has been isolated by closing the two air operated ECCS recirc header stops 2-SI-659/660."
The Unusual Event was terminated at 1856 and the NRC exited "monitoring mode" at 1920.
Notified IRD (Cruz), NRR EO (Quay), and R1DO (Hansell).
EPA Incident Report Number: 867171
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44122 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES SHAW
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/07/2008
Notification Time: 05:11 [ET]
Event Date: 04/07/2008
Event Time: 04:30 [EDT]
Last Update Date: 04/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICHARD SKOKOWSKI (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER MAY BECOME INHABITABLE DUE TO SCHEDULED MAINTENANCE
"At 04:30 hours on Monday, April 7, 2008, the Cook Nuclear Plant (CNP) removed the Technical Support Center [TSC] Heating Ventilation Air Conditioning [HVAC] System from service for planned maintenance. The TSC HVAC system will remain out of service for period of approximately three days.
"Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary based upon results of procedurally required monitoring of TSC radiological conditions.
"This notification is being made in accordance with NUREG 1022 as a potential unavailability of an emergency response facility in accordance with 10 CFR 50.72 (b)(3)(xiii).
"The licensee notified the NRC Resident Inspector. The licensee will supplement this notification upon returning the TSC HVAC system to normal operational status." | |