Event Notification Report for May 9, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/08/2002 - 05/09/2002 ** EVENT NUMBERS ** 38901 38906 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 38901 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: COLORADO DEPT OF HEALTH |NOTIFICATION DATE: 05/06/2002| |LICENSEE: |NOTIFICATION TIME: 13:58[EDT]| | CITY: DENVER REGION: 4 |EVENT DATE: 04/03/2002| | COUNTY: ARAPAHOE STATE: CO |EVENT TIME: [MDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 05/06/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MARK SHAFFER R4 | | |DOUG BROADDUS NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: TIM G. BONZER | | | HQ OPS OFFICER: GERRY WAIG | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OCCUPATIONAL RADIATION EXPOSURE EXCEEDED ANNUAL LIMIT | | | | On April 3, 2002, it was identified that a radiographer had received a total | | occupational exposure of 5.227 Rem Total Effective Dose Equivalent for the | | monitoring period of January 1, 2001 through December 31, 2001. | | | | While compiling Occupational Exposure Reports it was determined that the | | dose received by a radiographer was in excess of the limits allowed by RH | | 4.6.1.1.1. The Corporate Radiation Safety Department then notified the | | Denver Lab Manager of the findings. Exposure records have been reviewed to | | verify the accuracy of the reported exposure. It has been determined that | | the reported total is accurate as stated. | | | | The radiographer received an exposure of 5.227 Rem Deep Dose Equivalent, and | | 5.157 Rem Shallow Dose Equivalent for the period of January 1, 2001 through | | December 31, 2001. | | | | Throughout the monitoring period the radiographer worked at various | | jobsites. The isotope utilized to perform the radiography was Iridium 192. | | Varying curie strengths from 10 curies to 100 curies were used throughout | | the year. | | | | The root cause of the excessive exposure was due to a lack of attention paid | | to the cumulative exposure total by the Radiation Safety personnel and by | | the Radiographer. On August 1, 2001 CONAM Inspection switched to a new | | dosimetry processor. The result was two dosimetry reports, neither having a | | cumulative total for the year. The radiographer failed to notify his | | Radiation Safety Officer of the amount of his total exposure and his | | proximity to the annual limit. Additionally, the Radiation Safety Officer | | and the Corporate Radiation Safety Department failed to identify the | | radiographers proximity to the annual limit and remove him from radiographic | | activities. | | | | The following corrective actions and program enhancements have been made. | | The Corporate Radiation Safety Department has added a staff member to assist | | with the oversight of the radiation safety program All monthly exposures in | | excess of 420 mR now require an ALARA review. All monthly dosimetry reports | | are reviewed by the lab and by the corporate radiation safety departments to | | prevent this type of incident. CONAM Inspection intends to utilize our | | current dosimetry company for the remainder of the monitoring period | | eliminating the dual reports. The entire radiography staff has been informed | | of this incident. They have also been instructed of their responsibility to | | prevent this type of incident. The Radiation Safety Officer has been | | retrained on his responsibility to ensure that all employees are maintaining | | their exposure ALARA. When the results from the June monitoring period | | become available, any employee in excess of 2.5 Rem TEDE will be removed | | from radiographic activities. Additionally, an employee receiving in excess | | of 4 Rem will be removed from radiographic activities for the remainder of | | the monitoring year. The corrective actions are in place as of the date of | | this letter. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38906 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 05/08/2002| | UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 18:43[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 05/08/2002| +------------------------------------------------+EVENT TIME: 17:07[CDT]| | NRC NOTIFIED BY: GILMORE |LAST UPDATE DATE: 05/08/2002| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 A Y 100 Power Operation |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 100% POWER ON STEAM GENERATOR LOW/LOW LEVEL SIGNAL | | | | A channel operational test of Tavg, delta T, and pressurizer pressure for | | protection set two was being performed by I&C technicians. While swapping | | steam generator level channels, they placed the "D" feedwater reg valve in | | manual per procedure. The feedwater reg valve failed closed and they | | attempted to manually open the valve, but there was no response. When they | | put the controller in automatic, the valve started to reopen, but the | | response was not fast enough and the reactor tripped on steam generator | | lo-lo level. The auxiliary feedwater actuated as designed and all rods | | fully inserted. No relief valves lifted. The licensee is investigating the | | cause of the valve malfunction. | | | | The NRC Resident Inspector was notified and the licensee will issue a press | | release. | +------------------------------------------------------------------------------+
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