Event Notification Report for July 3, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/02/2002 - 07/03/2002
** EVENT NUMBERS **
38934 39034 39035 39036 39037
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 38934 |
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| FACILITY: COLUMBIA GENERATING STATIREGION: 4 |NOTIFICATION DATE: 05/21/2002|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 18:59[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE: 05/03/2002|
+------------------------------------------------+EVENT TIME: 15:40[PDT]|
| NRC NOTIFIED BY: BOB BROWNLEE |LAST UPDATE DATE: 07/02/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA SMITH R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| UNANALYZED CONDITION THAT SIGNIFICANTLY DEGRADED PLANT SAFETY |
| |
| On May 3, 2002, approximately 20 gallons of water was spilled on the floor |
| of the cable spreading room (CSR). Some of the water leaked down into rooms |
| below the CSR floor, resulting in an electrical ground on the on the 125-VAC |
| Division 2 battery bus S1-2. The S1-2 bus remained operable. It has since |
| been determined that the pathway for leakage through the floor of the CSR |
| was cracks in the concrete due to abandoned concrete anchors, and through |
| shrinkage cracks in the reinforced concrete floor slab. Shrinkage cracks |
| are also located in the 525' elevation floor above the Control Room. These |
| two floors are considered essential fire rated assemblies and are required |
| to be "leak tight". These floors have not had a qualified paint/sealant |
| applied that would render them "leaktight". Other floors that are fire |
| rated assemblies are believed to have had the appropriate paint/sealant |
| applied, but this is being verified. Should a fire system actuate, or |
| develop a leak in either the CSR or the room above the Control Room, there |
| is the potential for leakage through the floors to impact Division 1 or 2 |
| safety-related equipment in the rooms below. A barrier impairment has been |
| initiated for the CSR on May 6, 2002 and for the 525' elevation above the |
| Control Room on May 7, 2002 with compensatory action to include these areas |
| on an hourly fire/flood tour. With the hourly fire/flood tours in place, the |
| floors of the CSR and the room above the Control Room have been declared |
| "operable but degraded" per formal assessment of operability, and no longer |
| represent an unanalyzed condition that significantly degrades plant safety. |
| The cracks associated with the abandoned anchor bolts have been sealed. |
| Hourly fire/flood tours remain in effect until both floors have been |
| properly sealed. |
| |
| The NRC Resident Inspector has been notified of this event. |
| |
| * * * RETRACTED AT 1600 EDT ON 7/2/02 BY BOB BROWNLEE TO FANGIE JONES * * * |
| |
| |
| The licensee is retracting this event notification. It was originally |
| postulated that due to the prevalence of unsealed concrete cracks, a design |
| basis flooding scenario would create a significant amount of water leakage |
| into critical equipment rooms below the floors. After further evaluation it |
| has been concluded that flooding events in either room would result in |
| minimal leakage into rooms below, and therefore this condition can not be |
| characterized as an unanalyzed condition that significantly degrades plant |
| safety. The CSR floor and the room above the Control Room are "operable but |
| degraded." Hourly fire/flood tours will remain in effect until both floors |
| have been properly sealed. The cracks responsible for the observed leakage |
| for this event have been sealed. Columbia Generating Station will submit a |
| voluntary Licensee Event Report on this issue due to its generic interest to |
| both the NRC staff and the nuclear industry. |
| |
| The licensee notified the NRC Resident Inspector. The R4DO (Dale Powers) |
| has been notified. |
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|Power Reactor |Event Number: 39034 |
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| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 07/02/2002|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 10:47[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 05/19/2002|
+------------------------------------------------+EVENT TIME: 11:00[CDT]|
| NRC NOTIFIED BY: CLARE BLEAU |LAST UPDATE DATE: 07/02/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRUCE JORGENSEN R3 |
|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
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 21 Power Operation |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| RADIATION MONITOR DECLARED INOPERABLE |
| |
| While operating in Mode 1, in the process of a controlled shutdown to |
| perform an elective repair of a condenser tube leak, Division "A" Refuel |
| Pool Radiation Monitor lost power resulting in a Group 3A Primary |
| Containment Isolation System (PCIS) actuation. The Group 3A isolation |
| function as designed. Radiation levels in the area of the monitor were |
| normal and the actuation was considered invalid. |
| |
| The Radiation Monitor was declared inoperable for maintenance. The monitor |
| was declared operable at 1049 CST on 05/20/02 at which time the Group III |
| isolation was also reset. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Other Nuclear Material |Event Number: 39035 |
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| REP ORG: US ARMY |NOTIFICATION DATE: 07/02/2002|
|LICENSEE: US ARMY |NOTIFICATION TIME: 10:42[EDT]|
| CITY: ABERDEEN REGION: 1 |EVENT DATE: 07/01/2002|
| COUNTY: STATE: MD |EVENT TIME: 19:30[EDT]|
|LICENSE#: 1930563-01 AGREEMENT: Y |LAST UPDATE DATE: 07/02/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |PETER ESSELGROTH R1 |
| |FRED BROWN NMSS |
+------------------------------------------------+DALE POWERS R4 |
| NRC NOTIFIED BY: JOYCE KUYKENDALL | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| US ARMY LICENSE VIOLATION INVOLVING A CHEMICAL AGENT DETECTOR |
| |
| The US Army reported that License Item 15 was violated when a technician |
| attempted to disassemble the cell assembly of a chemical agent detector at |
| Fort Richardson. The cell assembly contains a radiological source of 300 |
| microcuries of AM-241. The model number is M43A1. An investigation was |
| initiated by the US Army to review this event. At this time there were no |
| known personnel contaminations or radiological overexposures. |
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|Other Nuclear Material |Event Number: 39036 |
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| REP ORG: ADAMS CONSTRUCTION COMPANY |NOTIFICATION DATE: 07/02/2002|
|LICENSEE: ADAMS CONSTRUCTION COMPANY |NOTIFICATION TIME: 11:00[EDT]|
| CITY: SOUTH BOSTON REGION: 2 |EVENT DATE: 07/01/2002|
| COUNTY: STATE: VA |EVENT TIME: 15:40[EDT]|
|LICENSE#: 45-1788701 AGREEMENT: N |LAST UPDATE DATE: 07/02/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LEONARD WERT R2 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RON ROBSON | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
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EVENT TEXT
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| DAMAGED TROXLER MOISTURE DENSITY GAUGE |
| |
| Adams Construction Company reported that an asphalt roller ran over part of |
| a Troxler moisture density gauge, model number 4640B, serial number 1752. |
| The source remained intact and was not leaking. The gauge was transported |
| to the asphalt plant located in South Boston, VA. The gauge will be |
| examined by Troxler for evaluation and repair. The gauge contained a source |
| of 8 millicuries of CS-137. |
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|Other Nuclear Material |Event Number: 39037 |
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| REP ORG: POWER RESOURCES |NOTIFICATION DATE: 07/02/2002|
|LICENSEE: POWER RESOURCES |NOTIFICATION TIME: 13:34[EDT]|
| CITY: GLENROCK REGION: 4 |EVENT DATE: 07/01/2002|
| COUNTY: STATE: WY |EVENT TIME: [MDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/02/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BILL JOHNSON R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BILL KEARNEY | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
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EVENT TEXT
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| MONITOR WELL EXCEEDED TWO OF ITS THREE UPPER CONTROL LIMITS |
| |
| Monitor well FM6 in the F well field exceeded two of its three upper control |
| limits (UCLs). A confirmation sample was collected on July 1, 2002. |
| |
| Date 7/1/02 |
| Chloride (UCL 18 mg/l) 40 mg/l |
| Conductivity (UCL 1121 umhos/cm) 793 umhos/cm |
| Bicarbonate (UCL 230 mg/l) 233 mg/l |
| Uranium (UCL 0.1 mg/l) 0.1 mg/l |
| |
| The licensee notified NRC Project Manager (Rick Weller). |
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