Event Notification Report for June 14, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/13/2002 - 06/14/2002
** EVENT NUMBERS **
38974 38979 38987 38988 38989 38990
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|General Information or Other |Event Number: 38974 |
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| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE:
06/10/2002|
|LICENSEE: UCLA HARBOR MEDICAL CENTER |NOTIFICATION TIME: 12:40[EDT]|
| CITY: REGION: 4 |EVENT DATE: 06/10/2002|
| COUNTY: LOS ANGELAS STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: 0359-19 AGREEMENT: Y |LAST UPDATE DATE: 06/10/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANTHONY GODY R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT GREGER | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT OF MEDICAL MISADMINISTRATION |
| |
| "Patient who was suppose to receive 32 millicuries I-131 was given 120 |
| millicuries I-131. As patient's thyroid was to be ablated anyway, no ill |
| effects to patient. The doctor gave her the wrong dose." |
| |
| The cause of the misadministration is being reviewed at the time of the |
| report. |
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|General Information or Other |Event Number: 38979 |
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| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE:
06/11/2002|
|LICENSEE: THE BOEING COMPANY |NOTIFICATION TIME: 19:50[EDT]|
| CITY: ANAHEIM REGION: 4 |EVENT DATE: 06/11/2002|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: 0065-30 AGREEMENT: Y |LAST UPDATE DATE: 06/11/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANTHONY GODY R4 |
| |THOMAS ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT GREGER | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT FROM CA REGARDING POTENTIAL PERSONNEL
OVEREXPOSURE |
| |
| The California state radiation safety officer called in a potential 20.2202 |
| personnel overexposure incident that occurred at The Boeing Company in |
| Anaheim, California. The licensee utilizes irradiator facilities large |
| enough for an individual to enter. The individual's dosimeter was read by |
| the personnel monitoring vendor (i.e., Landauer) as 94 Rem DDE, 94 Rem LDE |
| and 112 Rem SDE. The dosimetry was worn during the period of April 1 to |
| April 30, 2002. The licensee commenced an investigation to determine the |
| validity of the high and unexpected reading. The licensee will conduct an |
| interview with the individual and also the State indicated a blood test will |
| most likely be performed. The State indicated the badge received a "static" |
| exposure, and it will probably turn out to be a dosimeter-only exposure. |
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|Power Reactor |Event Number: 38987 |
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| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 06/13/2002|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 00:57[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 06/12/2002|
+------------------------------------------------+EVENT TIME: 23:41[EDT]|
| NRC NOTIFIED BY: BRUCE SHICK |LAST UPDATE DATE: 06/13/2002|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: |FEMA, DOE, USDA, HHS FAX |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |EPA, DOT (via NRC) FAX |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION REGARDING A RELEASE OF RAW SEWAGE TO THE
CHESAPEAKE |
| BAY |
| |
| The licensee reported that an air leak caused a level detector in a large |
| inlet pumping well to fail low. As a result, the sump pumps stopped and did |
| not restart when actual level reached the high level setpoint. The inlet |
| sump of the onsite sewage treatment plant subsequently overflowed, and raw |
| sewage was released to the Chesapeake Bay. |
| |
| The licensee estimates that the quantity of raw sewage involved was between |
| 2,500 and 7,200 gallons. Additional calculations are currently being |
| performed. The level detector malfunctioned has since been repaired. |
| |
| The licensee notified the NRC resident inspector and local county and plans |
| to notify the Maryland Department of Environmental Protection. |
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|Power Reactor |Event Number: 38988 |
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| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/13/2002|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 13:02[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/13/2002|
+------------------------------------------------+EVENT TIME: 11:20[EDT]|
| NRC NOTIFIED BY: MYERS |LAST UPDATE DATE: 06/13/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: |TERRY REIS EO |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION MADE TO LOCAL FIRE DEPARTMENT FOR ASSISTANCE
|
| |
| |
| A fire in the owner controlled area 1/2 mile outside the protected area |
| occurred at their training facility and a call for offsite assistance was |
| made. The fire turned out to be a lot of black smoke coming from a burned |
| out fan motor in the training facilities ventilation system. Everything was |
| under control within a half hour and the licensee logged out of their |
| procedures at 1237. |
| |
| The NRC Resident Inspector was notified along with state and local agencies. |
| A press release may be made. |
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|Power Reactor |Event Number: 38989 |
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| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 06/13/2002|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 14:30[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/13/2002|
+------------------------------------------------+EVENT TIME: 12:30[CDT]|
| NRC NOTIFIED BY: DOUG HOBSON |LAST UPDATE DATE: 06/13/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| LOSS OF EMERGENCY NOTIFICATION NETWORK (ENN) TO STATES OF ALABAMA AND
|
| GEORGIA |
| |
| "The ENN (Emergency Communications Equipment) [was] declared inoperable at |
| 1230 central on 13 June 2002 due to [the] inability to communicate with the |
| states of Alabama and Georgia. Action has been initiated to correct [the] |
| problem. All other communication equipment is available including the |
| designated backup capability provided by the Southern Link Radio System." |
| |
| The licensee will inform the states of Alabama and Georgia and the NRC |
| Resident Inspector. |
| |
| |
| * * * UPDATE ON 6/13/2002 @ 1723 BY HOBSON TO GOULD * * * |
| |
| At 1414 CDT they restored capability to contact one state agency in both |
| Alabama and Georgia. |
| |
| The NRC Resident Inspector will be informed |
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|Power Reactor |Event Number: 38990 |
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| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 06/13/2002|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 16:50[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/13/2002|
+------------------------------------------------+EVENT TIME: 12:00[EDT]|
| NRC NOTIFIED BY: MOSS |LAST UPDATE DATE: 06/13/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KERRY LANDIS R2 |
|10 CFR SECTION: | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| LICENSEE NOTED THAT A 4160 VOLT BUS MAY NOT HAVE BEEN ADEQUATELY
PROTECTED |
| FROM A POTENTIAL MODERATE ENERGY SPRAY INTERACTION |
| |
| During a plant walk down as a corrective action for a previous issue, it was |
| noted that 4160 volt vital bus 2ETA may not have been adequately protected |
| from a potential moderate energy spray interaction. It was noted that a |
| section of fire protection system piping was identified as a potential |
| source for moderate energy spray onto 2ETA. Engineering performed a review |
| of both the spray distances assumed in the moderate energy spray criteria |
| and the requirement to postulate moderate energy cracks in piping at every |
| weld location. The fire protection system in question is low pressure, low |
| temperature. This review concluded that a moderate energy pipe rupture |
| (crack) in the fire protection system piping could lead to a loss of the |
| vital 4160 volt bus 2ETA. A concurrent single failure of the opposite |
| train vital 4160 volt bus (2ETB) could prevent the fulfillment of safety |
| function of systems or structures. UFSAR section 3.6 describes the |
| requirements for protection against dynamic effects associated with the |
| postulated rupture of piping. Specifically the general design requirements |
| for postulated piping breaks other than reactor coolant system requires that |
| the design be of a nature that to mitigate the consequences of the break so |
| that the reactor can be shutdown safely and eventually maintained in a cold |
| shutdown condition. Maintenance has placed a spray deflector on the |
| affected area of piping to preclude postulated spray interaction with 2ETA. |
| Engineering has reviewed the other safety related 4160 volt bus on Unit 2 |
| and both safety related 4160 volt buses on Unit 1 and determined that they |
| do not have any spray interaction issues. The root cause of this issue is |
| still under investigation. |
| |
| |
| The NRC Resident Inspector, States and local agencies will be notified. |
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