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
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|General Information or Other |Event Number: 38901 |
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| 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 |
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| NRC NOTIFIED BY: TIM G. BONZER | |
| HQ OPS OFFICER: GERRY WAIG | |
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|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 38906 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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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