| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/15/2004 - 04/16/2004 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 40566 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RONALD FRY
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/04/2004
Notification Time: 10:51 [ET]
Event Date: 03/04/2004
Event Time: 05:20 [EST]
Last Update Date: 04/15/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
TODD JACKSON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text RCIC STEAM SUPPLY FAILED LLRT
"Appendix J Local Leak Rate Testing [LLRT] of the RCIC Steam Supply failed the Combined Main Steam Isolation Valves leakage limit of 300 scfh. The Combined MSIV leakage limit includes MSIV'S, MSL Drains, HPCI Steam Supply and RCIC Steam Supply. The volume between RCIC Steam Supply valves could not be pressurized therefore, the Minimum Pathway leakage limit is considered to be exceeded.
"This is also considered a failure of the Primary Containment Air Leakage Minimum Pathway leakage limit of 1.0 La.
"The identified degraded condition is reportable as a condition of the nuclear power plant, including its principle safety barriers being seriously degraded per 10CFR50.72(b)(3)(ii) requiring an 8-hr ENS notification."
The RCIC Steam Supply line was tested successfully approximately two years ago during the last refueling outage. The licensee will inform the NRC Resident Inspector.
******RETRACTED ON 4/14/2004 AT 1610 EST FROM FRY TO HEISSERER*****
"At the time the original 8-hour ENS notification was made, it was declared that the Appendix J Local Leak Rate Test of the RCIC Steam Supply had failed the combined Main Steam Isolation Valves Minimum Pathway leakage limit of 300 scfh. The combined MSIV leakage limit includes MSIVs, MSL Drains, HPCI Steam Supply and the RCIC Steam Supply. The volume between the inboard and outboard RCIC Steam Supply valves could not be pressurized, therefore the Minimum Pathway leakage limit was considered to be exceeded.
"Subsequent to this event, during performance of an additional Local Leak Rate Test of the RCIC Steam Supply Penetration, it was demonstrated that the as-found Appendix J and combined MSIV Minimum Pathway leakage and the Primary Containment Air Leakage Minimum Pathway of 1.0 La were not exceeded as previously reported.
"The original Local Leak Rate Test was performed between the combination of two parallel inboard valves and the outboard valve. The subsequent test determined that the outboard isolation valve did not exceed Minimum Pathway criteria. The majority of the leakage was from the smaller inboard RCIC warm-up line isolation valve of the three RCIC Steam Supply valves. The post-maintenance test of the penetration measured leakage that was within acceptable limits.
"As such, the condition of the nuclear power plant, including its principle barriers, was not significantly degraded."
The NRC Resident Inspector has been notified.
Notified R1DO (B. McDermott). |
| Other Nuclear Material | Event Number: 40653 | Rep Org: PROFESSIONAL INSPECTION AND TESTING
Licensee: PROFESSIONAL INSPECTION AND TESTING SERVICES INC
Region: 1
City: CHAMBERSBURG State: PA
County:
License #: 37-28744-01
Agreement: N
Docket:
NRC Notified By: RICK CURTIS
HQ OPS Officer: BILL GOTT | Notification Date: 04/07/2004
Notification Time: 13:51 [ET]
Event Date: 04/07/2004
Event Time: [EDT]
Last Update Date: 04/15/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
LAWRENCE DOERFLEIN (R1)
ROBERT PIERSON (NMSS)
| Event Text LOST OR STOLEN TROXLER GAUGE
The licensee reported that on Friday 4/2/04 the driver and the company's truck which contained a Troxler Moisture Density Gauge Model: 03430, S/N: 023850 with a Cs-137 and Am-241:Be source, S/N: 75-5183 did not return to the company's Temple Hills, MD office. On the same day, the licensee reported this to the Prince George's County, MD Police Department and swore a warrant for the unauthorized use of the vehicle. The vehicle was found on 4/6/04 in the Prince George's County impound lot. The licensee asked the lot attendant to look inside the vehicle for the gauge. The gauge was not there. The licensee also conducted a search of all of its storage locations to verify that the gauge had not been turned in, but they did not find the gauge. The licensee continues to search for the employee.
* * * * UPDATE FROM R. CURTIS TO M. RIPLEY 1930 ET 04/15/03 * * * *
The licensee reported a call from the Prince George's County, MD police stating that the gauge carrying case had been located in Hyattsville, MD and that the Haz Mat Team was responding to perform a radiological survey. The details of the gauge's discovery were not provided. The licensee subsequently reported that the Haz Mat Team from the Glendale, MD fire department responded and determined that the gauge was found inside its case and that the gauge appeared to be intact. The licensee will pick up the gauge at the Glendale, MD fire department on 4/16/04.
Notified R1 DO (McDermott) and NMSS EO (B. Pierson) |
| General Information or Other | Event Number: 40668 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: NITON LLC
Region: 1
City: BILLERICA State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/12/2004
Notification Time: 09:17 [ET]
Event Date: 02/12/2004
Event Time: [EDT]
Last Update Date: 04/12/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LAWRENCE DOERFLEIN (R1)
DALE POWERS (R4)
TOM ESSIG (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING SAFETY EQUIPMENT FAILURE
On 2/12/04, a Niton XRF Portable Analyzer (model Xli 800 - S/N 5089) shutter failed to close when the device was placed in the off mode. The incident occurred at the Pearl Harbor Naval Shipyard in Honolulu, HI and did not involve any significant radiation exposures to personnel. The device was packaged with temporary shielding and returned to Niton for evaluation.
Niton determined that the shutter malfunction was the result of a loose set screw which connects the shutter to the motor. A component change to the Xli 800 series models was made that involves upgrading to a nylock set screw. This was the first instance of this type of failure. Instruments returned to Niton for resourcing or software upgrade will be modified in this manner to prevent shutter failure.
This particular device contains a 30 millicurie Americium-241 source and is used for rapid identification and chemistry of metal alloy composition. |
| General Information or Other | Event Number: 40669 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: COOPERHEAT - MQS
Region: 4
City: MONROE State: LA
County:
License #: LA-9808-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: BILL GOTT | Notification Date: 04/12/2004
Notification Time: 15:38 [ET]
Event Date: 01/09/2004
Event Time: [CDT]
Last Update Date: 04/12/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DALE POWERS (R4)
TOM ESSIG (NMSS)
| Event Text AGREEMENT STATE REPORT OF OVEREXPOSURE
The following facsimile was received from the Louisiana Radiation Protection Division:
"Cooperheat reported an over exposure to the assistant radiographer, on January 20, 2004. The radiographer received a dose of 9,347 mR due [to] failure to properly survey the radiography camera on January 9, 2004. The other radiographer received a dose of 4,974 mR. Both employees are not allowed to perform radiographic operations until after January 1, 2005. The radiographer was suspended 5 days without pay and the other radiographer was suspended 7 days without pay. Both employees are required to perform the 40 hour radiation safety training again before resuming radiographic operations. The employees were utilizing an Amersham camera model 660B with serial number B4293. The source was a 37.2 curie source of Ir-192 model number 424-9 with serial number 12680B." |
| Fuel Cycle Facility | Event Number: 40676 | Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PIKETON State: OH
County: PIKE
License #: GDP-2
Agreement: N
Docket: 0707002
NRC Notified By: GARY SALYERS
HQ OPS Officer: MIKE RIPLEY | Notification Date: 04/15/2004
Notification Time: 12:37 [ET]
Event Date: 04/15/2004
Event Time: 10:30 [EDT]
Last Update Date: 04/15/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
STEPHEN CAHILL (R2)
TOM ESSIG (NMSS)
| Event Text HAZARDOUS MATERIAL SPILL
"On 4/15/04 at approximately 0315 hours, an 18 inch expansion joint on a exterior overhead steam supply line ruptured during routine utilities valving operations. The asbestos insulating the expansion joint was released to the ground resulting in a hazardous material spill of approximately 1 - 2 pounds of friable asbestos.
"At 1030 hours, The Plant Shift Superintendent notified the National Response Center that a Reportable Quantity (RQ) of hazardous material (friable asbestos) was released to the ground. No material left the immediate area and clean-up of the 1 to 2 pounds of asbestos is currently in [progress]. UE2-RA-RE1030, Appendix D, section P requires a 4 hour NRC event when other government agencies are notified."
The licensee notified NRC Region II. The Ohio EPA and the local Department of Energy office were also notified. | |