Event Notification Report for December 20, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/19/2002 - 12/20/2002
** EVENT NUMBERS **
39457 39460 39461 39463 39464
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|General Information or Other |Event Number: 39457 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 12/17/2002|
|LICENSEE: SCHLUMBERGER |NOTIFICATION TIME: 18:00[EST]|
| CITY: DALLAS FT WORTH APT REGION: 4 |EVENT DATE: 12/15/2002|
| COUNTY: STATE: TX |EVENT TIME: [CST]|
|LICENSE#: L01833 AGREEMENT: Y |LAST UPDATE DATE: 12/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL email R4 |
| |ROBERT PIERSON email NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| PACKAGE AT DALLAS FORT WORTH (DFW) AIRPORT EXCEEDS RADIATION LIMITS BASED ON |
| LABELING |
| |
| "The package exceeded the package limits based on the labeling and the |
| container. Radiation readings were about 17 mR/hr. at one meter. The limit |
| was 10 mR/hr. at one meter. A yellow Ill and Yellow II label provided |
| inconsistent radiation information. The package was held at a cargo bay by |
| US Customs. The TDH/BRC responded to a call for assistance to survey the |
| package and help determine its contents. The inspector responded on site |
| performed a survey and notified the Licensee's RSO. The Licensee planned to |
| send a representative to repackage and relabel the package prior to the |
| package being released for shipment to Houston, TX. The information provided |
| is preliminary and based on telephone conversations with involved parties." |
| |
| The package was air cargo on an international flight being shipped from |
| Schumberger in Singapore to Schlumberger in Houston, TX. |
| |
| The Texas Department of Health, Bureau of Radiation Control has notified NRC |
| R4, US Customs, DFW, and the licensee. |
| |
| The Texas Department of Health, Bureau of Radiation Control incident number |
| is I-7962 |
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|Power Reactor |Event Number: 39460 |
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| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 12/19/2002|
| UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 05:42[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 12/19/2002|
+------------------------------------------------+EVENT TIME: 03:59[CST]|
| NRC NOTIFIED BY: JAMES CRABILL |LAST UPDATE DATE: 12/19/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA HOWELL R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR TRIP DUE TO MAIN TURBINE GENERATOR TRIP |
| |
| "Main Turbine Generator and Reactor trip from 100% power. All control rods |
| inserted. Plant is stable in Mode 3, Hot Standby. No release in |
| progress." |
| |
| The Licensee has notified the NRC Resident Inspector and the State of |
| Arkansas. |
| |
| The Licensee indicated that no ECCS actuation occurred, the electrical grid |
| is stable with all Emergency Diesel Generators available, and that there is |
| no primary to secondary Steam Generator leakage. |
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|Other Nuclear Material |Event Number: 39461 |
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| REP ORG: OK DEQ RAD MANAGEMENT |NOTIFICATION DATE: 12/19/2002|
|LICENSEE: |NOTIFICATION TIME: 10:38[EST]|
| CITY: Oklahoma City REGION: 4 |EVENT DATE: 12/17/2002|
| COUNTY: Kingfisher STATE: OK |EVENT TIME: 10:00[CST]|
|LICENSE#: OK-15794-01 AGREEMENT: Y |LAST UPDATE DATE: 12/19/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MIKE BRODERICK | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE |
| |
| At 1038 EST on 12/19/02, Oklahoma Department of Environmental Quality |
| notified us that on 12/17/02 at 1000 CST, an Oklahoma Department of |
| Transportation (ODOT) Troxler Moisture Density gauge was damaged in an |
| accident. The accident occurred when a subcontractor's water tank truck |
| backed over an ODOT pickup truck and the gauge that was resting on the |
| Standard Block. The gauge was damaged, but the sealed sources were |
| contained in shielding and were not ruptured. The gauge, S/N 27829, contains |
| an 8 millicurie Cs-137 source and a 40 millicurie Am-241/Be source. The |
| gauge will be shipped to Troxler for repair or disposal. |
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|Power Reactor |Event Number: 39463 |
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| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 12/19/2002|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 17:49[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/19/2002|
+------------------------------------------------+EVENT TIME: 14:30[EST]|
| NRC NOTIFIED BY: WOODBURY |LAST UPDATE DATE: 12/19/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PAUL FREDRICKSON R2 |
|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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| REACTOR CORE ISOLATION COOLING(RCIC) SYSTEM OPERATION FROM THE REMOTE S/D |
| PANEL MAY NOT BE AVAILABLE FOR SAFE SHUTDOWN OF THE UNIT. |
| |
| On December 19, 2002, during an engineering review of the impact of |
| electrical faults on the ability of systems required to safely shutdown the |
| facility in the event of a fire, it was determined that Reactor Core |
| Isolation Cooling (RCIC) system operation from the remote shutdown panel |
| (RSDP) may not be available for safe shutdown of the unit. |
| |
| A postulated fire that results in an electrical short of the Division 2 |
| 125/250 VDC distribution system to ground may cause a voltage control device |
| to fail integral to a RSDP instrument power supply inverter. If the |
| inverter fails as a result of the ground, no power supply would be available |
| for automatic or manual control of the RCIC turbine at the RSDP. In |
| addition, loss of the same inverter would also result in the loss of |
| reactor, drywell and suppression pool monitoring instruments at the remote |
| shutdown panel. |
| |
| The current fire safe shutdown analysis credits only the RCIC system for |
| post-fire inventory control during a worst case main control room fire. |
| This analysis requires RCIC to be operational from the RSDP. With this |
| postulated loss of RCIC RSDP capability during a main control room fire, |
| this event is reportable under 10CFR50.72(b)(3)(ii). |
| |
| There were no actual safety consequences associated with this reportable |
| event since there was no fire in the control room. The design basis fire in |
| the control room assumes an all encompassing fire which is unlikely and |
| would more likely be limited to a single panel. |
| |
| An Alternate Safe Shutdown impairment has been established in accordance |
| with station requirements. Compensatory measures consist of calibrating a |
| spare inverter for installation and expediting installation of a plant |
| modification to remove the postulated failure mechanism. |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 39464 |
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| FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 12/19/2002|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 22:09[EST]|
| RXTYPE: [1] CE |EVENT DATE: 12/19/2002|
+------------------------------------------------+EVENT TIME: [CST]|
| NRC NOTIFIED BY: ERICK MATZKE |LAST UPDATE DATE: 12/19/2002|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA HOWELL 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| 8-HOUR NOTIFICATION FOR UNANALYZED CONDITION |
| |
| "During a review of the Fort Calhoun Station fire protection program, it was |
| discovered that for a potential fire in two fire areas in the plant the |
| protected train of reactor inventory control would not be free of fire |
| damage. During a postulated fire in either one of two fire areas the |
| charging pump credited for maintaining hot shutdown reactor coolant |
| inventory may be affected by a fire in one of the areas. This represents a |
| technical noncompliance with 10CFR50 Appendix R section III.G.2 and does not |
| affect current plant operation. As a compensatory measure, the plant is |
| instituting hourly fire watches in the affected fire areas." |
| |
| The licensee notified the Resident Inspector |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021