Event Notification Report for March 15, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/14/2002 - 03/15/2002
** EVENT NUMBERS **
38766 38767 38768 38769
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38766 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: GEORGIA RADIOACTIVE MATERIAL PGM |NOTIFICATION DATE:
03/14/2002|
|LICENSEE: ATC ASSOCIATES |NOTIFICATION TIME: 07:54[EST]|
| CITY: LOGANVILLE REGION: 2 |EVENT DATE: 03/10/2002|
| COUNTY: STATE: GA |EVENT TIME: [EST]|
|LICENSE#: GA 665-1 AGREEMENT: Y |LAST UPDATE DATE: 03/14/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK LESSER R2 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: LIZ SEALE | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING A STOLEN MOISTURE DENSITY GAUGE
|
| |
| "A construction trailer [located at the Home Depot construction site in |
| Loganville, GA] was broken into during the night of 3/10/02. A moisture |
| density gauge along with other equipment was stolen. Police [and FBI] were |
| notified and investigated. The gauge was a CPN Model MC-1, serial number: |
| M17077782." |
| |
| The moisture density gauge contained two sources; 10 mCi Cs-137 and 50 mCi |
| Am-241. Georgia Event Report ID No. GA-2002-07. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 38767 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE:
03/14/2002|
| RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 09:51[EST]|
| COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 03/13/2002|
| COMMERCIAL LWR FUEL |EVENT TIME: 12:30[EST]|
| |LAST UPDATE DATE: 03/14/2002|
| CITY: COLUMBIA REGION: 2 +-----------------------------+
| COUNTY: RICHLAND STATE: SC |PERSON ORGANIZATION |
|LICENSE#: SNM-1107 AGREEMENT: Y |MARK LESSER R2 |
| DOCKET: 07001151 |FRED BROWN NMSS |
+------------------------------------------------+NADER MAMISH IRO |
| NRC NOTIFIED BY: DAVID WILLIAMS | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24 HOUR NRC 91-01 REPORT INVOLVING OIL CONTAMINATION ON ADU BULK
CONTAINER |
| |
| |
| "Westinghouse Electric Company, Commercial Fuel Fabrication Facility, |
| Columbia SC, low enriched (less than or equal to 5.0 wt.% U-235) PWR fuel |
| fabricator for commercial light water reactors, License: SNM-1107. |
| |
| "Time and Date of Event: Approxirnatcly 12:30 hours, Wednesday, March 13, |
| 2002. |
| |
| "Reason for Notification: When an empty bulk container was returned to the |
| bulk blending room after having been emptied on the erbia production line, |
| an operator noticed a film of oil on the outside of the container and its |
| feeder valve, and on an horizontal structural plate of the container. |
| |
| "Summary of Process: UO2 powder is blended in 1750 kg bulk containers in the |
| bulk blending room (a moderation control (Modcon) area) prior to being used |
| on a pellet line. After blending, the bulk containers are taken to a |
| production line, and placed into a second Modcon area for processing. After |
| processing, the empty containers are returned to the bulk blending room. |
| |
| "As Found Condition; a summary of the as found conditions is as follows: The |
| Nuclear Criticality Safety (NCS) function was immediately notified, and an |
| NCS engineer went immediately to the floor to evaluate the situation. The |
| bulk container was empty. A film of oil was found on the side of the |
| container and its feeder valve, and on a horizontal structural plate of the |
| container. The total quantity of oil is estimated to be no more than a few |
| ounces. The container was inspected, and found to apparently be intact, that |
| is, the integrity intact and the gaskets in place and firmly secured. |
| |
| "Double Contingency Protection: Double contingency protection for the ADU |
| bulk container(s) is based on moderation control, that is, (1) prevent |
| greater than 20.48 liters of water equivalent from becoming available to a |
| bulk container, and (2) prevent greater than 20.48 liters of water |
| equivalent entering a container. It was determined double contingency |
| protection was lost because of the failure of controls to prevent moderating |
| material from coming in contact with a bulk Container without prior written |
| authorization, It is also noted that at no time was greater than the safety |
| limit of moderator involved. Therefore the incident requires 24-hour |
| notification in accordance with Westinghouse Operating License (SNM-1107), |
| paragraph 3.7.3 (c.5). |
| |
| "Summary of Activity: The NCS engineer made the preliminary determination |
| that the incident was significant because moderator had come into contact |
| with a bulk container. The container was removed from service. No additional |
| immediate corrective action was required for the affected container because |
| it was empty. The feeder valve was removed, and the gasket and interior of |
| the container and feeder valve were inspected for oil contamination. None |
| was found. |
| |
| "Conclusion: There was a loss of double contingency protection. At no time |
| was greater than a safe limit of moderator involved. At no time was |
| criticality possible. At no rime was there any risk to the health or safety |
| of any employee or member of the public. No exposure to hazardous material |
| was involved. The Incident Review Committee (IRC) determined that this is a |
| safety significant incident in accordance with governing procedures. A |
| causal analysis will be performed." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38768 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/14/2002|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 14:42[EST]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 02/28/2002|
+------------------------------------------------+EVENT TIME: 17:52[CST]|
| NRC NOTIFIED BY: JAMES WALLACE, JR |LAST UPDATE DATE: 03/14/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK LESSER R2 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID ACTUATION OF TWO DIESEL GENERATORS DURING TESTING |
| |
| "This is a verbal report in accordance with 10 CFR 50.73(a)(2)(iv)(A). It is |
| not considered a Licensee Event Report. This event occurred with Unit 2 at |
| full power while performing scheduled testing of the common accident signal |
| logic. On February 28, 2002, at 1752 hours, an invalid signal caused the |
| automatic actuation of the B and D Emergency Diesel Generators (EDGs). The |
| EDGs functioned successfully. They were not required to tie to their |
| respective 4kV shutdown boards because their boards were energized. The |
| Reactor Protection System did not actuate. No other systems listed in 10CFR |
| 50.73(a)(2)(iv)(B) were affected." |
| |
| The licensee stated that the inadvertent actuation resulted from a |
| surveillance test procedural compliance issue. |
| |
| The licensee will contact the NRC Resident. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38769 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/14/2002|
| UNIT: [] [] [3] STATE: AL |NOTIFICATION TIME: 14:42[EST]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/06/2002|
+------------------------------------------------+EVENT TIME: 21:03[CST]|
| NRC NOTIFIED BY: JAMES WALLACE JR |LAST UPDATE DATE: 03/14/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK LESSER R2 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 94 Power Operation |94 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID EMERGENCY DIESEL GENERATOR ACTUATION DURING TESTING |
| |
| "This is a verbal report in accordance with 10 CFR 50.73(a) (2)(iv)(A). It |
| is not considered a Licensee Event Report. This event occurred with Unit 3 |
| at 94 percent power while performing scheduled testing of the common |
| accident signal logic. On March 6, 2002, at 2103 hours, an invalid signal |
| caused the automatic actuation of the 3B Emergency Diesel Generator (EDG). |
| The EDG functioned successfully, it was not required to tie to its |
| respective 4kV shutdown board by design because the board was energized. The |
| Reactor Protection System did not actuate. No other systems listed in 10CFR |
| 50.73(a)(2)(iv)(B) were affected." |
| |
| The licensee stated that the inadvertent actuation resulted from an |
| insulator finger dislodging from an electrical contact during surveillance |
| testing. |
| |
| The licensee will notify the NRC Resident. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021