Event Notification Report for October 27, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/26/2000 - 10/27/2000
** EVENT NUMBERS **
37457 37458 37459 37460 37461
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|General Information or Other |Event Number: 37457 |
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| REP ORG: NATIONAL RESPONSE CENTER |NOTIFICATION DATE: 10/26/2000|
|LICENSEE: UNKNOWN |NOTIFICATION TIME: 00:25[EDT]|
| CITY: MISHAWAKA REGION: 3 |EVENT DATE: 10/25/2000|
| COUNTY: ST. JOSEPH STATE: IN |EVENT TIME: 20:10[CST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 10/26/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANTON VEGEL R3 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+GEOFFREY WRIGHT R3 |
| NRC NOTIFIED BY: CREWS |CINDY PEDERSON R3 |
| HQ OPS OFFICER: STEVE SANDIN |LARRY CAMPER NMSS |
+------------------------------------------------+CHARLES MILLER IRO |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| RECOVERY OF TROXLER MOISTURE DENSITY GAUGE FROM THE LOADING DOCK OF A |
| DEPARTMENT STORE. |
| |
| AT 2010 LOCAL TIME ON 10/25/00 A TROXLER MOISTURE DENSITY GAUGE [MODEL 3430, |
| S/N 29119] CONTAINING BOTH A CESIUM-137 AND AMERICIUM-241 SOURCE WAS |
| DISCOVERED ON THE LOADING DOCK OF A DEPARTMENT STORE LOCATED IN MISHAWAKA, |
| IN. THE RESPONDING FIRE DEPARTMENT CONTACTED THE SOUTH BEND FIRE DEPARTMENT |
| FOR HAZMAT (RADIOLOGICAL) ASSISTANCE. A PRELIMINARY RAD SURVEY SHOWED |
| APPROXIMATELY 2mR/HR CONTACT. THE INDIANA STATE DEPARTMENT OF HEALTH WAS |
| INFORMED. THE CONDITION OF THE TROXLER TRANSPORT CASE SUGGESTS THAT IT MAY |
| HAVE BEEN STOLEN. FIRE STATION #3 IN MISHAWAKA HAS TAKEN CUSTODY OF THE |
| TROXLER AND IS STORING THE DEVICE IN A LOCKED SECURE AREA. THE INITIAL |
| REPORT FROM THE NATIONAL RESPONSE CENTER INDICATED THAT 75 MEMBERS OF THE |
| PUBLIC WERE EVACUATED. REGION 3 WILL FOLLOWUP IN THE MORNING. SEVERAL |
| FEDERAL AND STATE AGENCIES WERE INFORMED BY THE STATE OF INDIANA AND THE |
| NATIONAL RESPONSE CENTER. |
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|Power Reactor |Event Number: 37458 |
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| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 10/26/2000|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 15:54[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/26/2000|
+------------------------------------------------+EVENT TIME: 14:05[CDT]|
| NRC NOTIFIED BY: JERRY GOSMAN |LAST UPDATE DATE: 10/26/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANTON VEGEL R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| SINGLE FAILURE RESULTING IN BOTH SAFEGUARDS TRAINS BECOMING INOPERABLE |
| |
| Prairie Island has three safeguard vertical cooling (service) water pumps. |
| These pumps are equipped with an air/vacuum valve that acts to expel air |
| from the pump upon starting. A ball float closes off the valve opening |
| after the air is expelled, and is held closed by pump developed head. It |
| was postulated that the air/vacuum valve could fail to close and the flow of |
| water out of the valve could cause flooding. Plant evaluation determined |
| that documentation does not exist that conclusively demonstrates that the |
| failure cannot occur or that the resultant flooding does not affect the |
| opposite safeguards train pump. Since the operability determination is |
| indeterminate, both trains of safeguards pumps were declared inoperable. A |
| single failure resulting in both safeguards trains becoming inoperable is |
| outside the plant design basis. |
| |
| Compensatory actions are being put into place to restore operability of the |
| safeguards pumps. The initial actions are to station a qualified individual |
| in the safeguard pump area. The qualified individual will observe any start |
| of a safeguard pump and ensure no failure of the air/vacuum valve has |
| occurred. If a failure occurs such that flooding is an immediate concern, |
| the qualified individual will contact the Control Room to secure the pump. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|General Information or Other |Event Number: 37459 |
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| REP ORG: GEORGIA RADIOACTIVE MATERIAL PGM |NOTIFICATION DATE: 10/26/2000|
|LICENSEE: UNKNOWN |NOTIFICATION TIME: 16:03[EDT]|
| CITY: EAST POINT REGION: 2 |EVENT DATE: 10/24/2000|
| COUNTY: STATE: GA |EVENT TIME: 12:00[EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 10/26/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANNE BOLAND R2 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM HILL | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| STRONTIUM-90 SOURCE FOUND IN SCRAP METAL. |
| |
| Environmental Radiation Program (ERP) personnel were notified by South |
| Carolina DHEC of a shipment of scrap metal returning to Newell Recycling; |
| East Point, Georgia; from SMI Steel in Caycese, South Carolina. October 25, |
| 2000 ERP staff surveyed the exterior of the truck and located the area with |
| elevated radiation levels in the front left corner of the trailer. |
| Personnel from Newell and the ERP began unloading scrap until a Sr-90 source |
| was located lying on the floor of the trailer. The source was removed, |
| bagged up and isolated approximately 30 yards away from the trailer in |
| another trailer that could be locked and secured as a temporary storage area |
| until remedial actions can be taken by Newell. Source markings were as |
| follows 3F1L, 100mCi, SR-90, 3M1389, 7-84. Note: Based on the information on |
| the source, the Registry of Radioactive Sealed Sources and Devices registry |
| number for this source is NR-460-S-921-S. |
| |
| Initial radiation measurements on the outside of the trailer in the area of |
| the front corner were as high as 300 micro-R/hour. Levels in the immediate |
| area of the source inside the trailer were greater than 3R/hour (beta/gamma) |
| unshielded and in contact with the source. After isolating the source, the |
| remaining scrap metal was surveyed by ERP personnel using Ludlum Micro-R |
| Meter and Eberline ESP-2 with HP-260 probe. No radiation levels above |
| background were noted. General radiation levels inside the trailer ranged |
| from 5 to 15 micro-R/hour while background radiation levels outside of the |
| trailer were 15 to 20 micro-R/hour. 26 smears were taken on various pieces |
| of scrap removed from the trailer and the floor in the vicinity of where the |
| source was found. No removable or fixed contamination was noted once the |
| source had been removed and isolated |
| |
| State of Georgia event number is GA-2000-20I. |
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|Power Reactor |Event Number: 37460 |
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| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 10/26/2000|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 16:40[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/26/2000|
+------------------------------------------------+EVENT TIME: 14:45[CDT]|
| NRC NOTIFIED BY: K . EHRHARDT |LAST UPDATE DATE: 10/26/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GREG PICK R4 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| KAOWOOL ISSUE |
| |
| During a plant walkdown to identify specific raceway configurations as part |
| of their plan to address Kaowool issues, a condition was found that may |
| affect both divisions of ESF switchgear room coolers. This condition is |
| conservatively being reported pursuant to 10CFR50.72(b)(1)(ii). These |
| areas were already under fire watch in accordance with their fire protection |
| program, as a precautionary response to issuance of SECY-99-0204 - Kaowool. |
| Fire detection and fires suppression are available in the affected area. |
| |
| |
| The NRC Resident Inspector will be informed of the event by the Licensee. |
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|Power Reactor |Event Number: 37461 |
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| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/26/2000|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 18:57[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/26/2000|
+------------------------------------------------+EVENT TIME: 14:15[CDT]|
| NRC NOTIFIED BY: MACLENNAN |LAST UPDATE DATE: 10/26/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANTON VEGEL R3 |
|10 CFR SECTION: | |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N Refueling |0 Refueling |
|2 N Y 95 Power Operation |95 Power Operation |
| | |
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EVENT TEXT
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| SAFE SHUTDOWN MAKEUP PUMP (SSMP) DECLARED INOPERABLE. |
| |
| At approximately 1415 hours on 10/26/00, the Safe Shutdown Makeup Pump |
| (SSMP) tripped unexpectedly during quarterly operability testing. At the |
| time of the trip, the in-plant operator was transferring the flow controller |
| to automatic from the manual position to obtain proper IST flows. At 1525 |
| hours, during a second attempt, the pump again tripped under the same |
| circumstances. The SSMP was run a third time, this time using the flow |
| controller in manual without transferring to automatic. On this attempt, |
| the SSMP obtained the proper pressure and flow but the local controller |
| indications remained erratic. The SSMP was declared inoperable from the time |
| of the first trip. The licensee entered Technical Specification 3.8.(j) a |
| 14 day Limiting Condition of Operation. All other Emergency Core Cooling |
| Systems for Unit 2 are fully operable. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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