Event Notification Report for September 20, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/19/2000 - 09/20/2000
** EVENT NUMBERS **
37248 37292 37346 37347 37348 37349 37350 37351 37352 37353
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37248 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 08/23/2000|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 05:14[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 08/23/2000|
+------------------------------------------------+EVENT TIME: 02:30[CDT]|
| NRC NOTIFIED BY: MIKE HAUNER |LAST UPDATE DATE: 09/19/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH RIVER WATER SUPPLY SYSTEMS WERE DECLARED INOPERABLE. |
| |
| At 0230 the River Water Supply (RWS) instrument air system failed resulting |
| in an invalid low RWS pit level alarm. Operators restored system air |
| pressure at 0243. The loss of instrument air pressure also resulted in the |
| loss of automatic traveling screen control and the screen high differential |
| level alarm function. Because both of the automatic traveling screen wash |
| systems were inoperable, both RWS systems were declared inoperable for the |
| 13 minute duration. Failure of both systems resulted in a loss of safety |
| function (supplies water to the Residual Heat Removal Service Water Pumps |
| and the Emergency Service Water System). The licensee entered the applicable |
| Technical Specifications for the loss of the RWS system. A new air dryer |
| was installed recently and when the operator cycled the power supply to the |
| air dryer it hung up. This caused the Instrument Air blockage. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| * * * UPDATE 1102 FROM BRIAN VOSS TAKEN BY STRANSKY * * * |
| |
| The licensee made the following corrections to the event report: (1) the |
| operator cycled the power supply to the compressor after it stopped, not |
| before, as noted above; and (2) there was no instrument air blockage, as |
| stated above. Notified R3DO (Hiland). |
| |
| * * * RETRACTION 1600 9/19/2000 FROM KARRICK TAKEN BY STRANSKY * * * |
| |
| "The DAEC is retracting event reports 37248 (8/24/00) and 37292 (9/5/00) |
| that involved a loss of the River Water Supply (RWS) System's instrument |
| air. These two 10CFR50.72(b)(2(ii) reports (an event or condition alone that |
| could have prevented safety function fulfillment) were based on the initial |
| determination that both loops of RWS System were inoperable, due, in part, |
| to a Precaution and Limitation (P&L) contained in the system's Operating |
| Instruction (OI-410). The loss of air had impacted a portion of the RWS |
| screen wash support system. The P&L provides guidance on the screen wash |
| subsystem's impact on RWS System operability. Follow-up engineering |
| assessment has concluded that a loss of instrument air, by design, does not |
| prevent the RWS system from fulfilling its intended safety function. The RWS |
| system would have been capable of fulfilling its intended safety function |
| during both events. |
| |
| "Technical Specification (TS) Bases 3.7.2 defines RWS subsystem operability |
| as having, 'an OPERABLE UHS, one OPERABLE pump, and an OPERABLE flow path |
| capable of taking suction from the intake structure and transferring the |
| water to the RHRSW/ESW Stilling Basin in the pump house.' For both of the |
| events, the only question regarding operability was that of the OPERABLE |
| flowpath. The follow-up engineering assessment concluded that the flowpath |
| remained operable. Actual river water flow, as indicated in the control |
| room, was not impacted by the loss of instrument air throughout the (short) |
| duration of these events. Also, there is no question regarding past or |
| historical operability because the cause of the loss of air was related to |
| air system modifications, which were in process at the time or the events. |
| |
| "Therefore, there was no event or condition alone that could have prevented |
| safety function fulfillment. Once discovered, the appropriate TS action |
| statements were entered. No TS 3.0.3. entry was made (or required to be |
| made). There were no Operations or Conditions Prohibited by TS. No other |
| reporting criteria apply to these events. These events are considered |
| not-reportable under 10CFR50.72 or 10CFR50.73." |
| |
| Notified R3DO (Burgess). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37292 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 09/05/2000|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 20:15[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 09/05/2000|
+------------------------------------------------+EVENT TIME: 18:10[CDT]|
| NRC NOTIFIED BY: TIM ALLEN |LAST UPDATE DATE: 09/19/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SHEAR R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH TRAINS OF RIVER WATER SUPPLY SYSTEM DECLARED INOPERABLE |
| |
| The licensee had a failure of the river water instrument air system at 1810 |
| CDT, resulting in the loss of the automatic traveling screen control and the |
| high screen differential level alarm function. With both automatic screen |
| wash functions inoperable, both river water supply systems were declared |
| inoperable. The systems were returned to operable at 1820 CDT when the |
| alternate air dryer was placed in service, the problem being the air dryer |
| that had been in service stopped passing air. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * RETRACTION 1600 9/19/2000 FROM KARRICK TAKEN BY STRANSKY * * * |
| |
| "The DAEC is retracting event reports 37248 (8/24/00) and 37292 (9/5/00) |
| that involved a loss of the River Water Supply (RWS) System's instrument |
| air. These two 10CFR50.72(b)(2(ii) reports (an event or condition alone that |
| could have prevented safety function fulfillment) were based on the initial |
| determination that both loops of RWS System were inoperable, due, in part, |
| to a Precaution and Limitation (P&L) contained in the system's Operating |
| Instruction (OI-410). The loss of air had impacted a portion of the RWS |
| screen wash support system. The P&L provides guidance on the screen wash |
| subsystem's impact on RWS System operability. Follow-up engineering |
| assessment has concluded that a loss of instrument air, by design, does not |
| prevent the RWS system from fulfilling its intended safety function. The RWS |
| system would have been capable of fulfilling its intended safety function |
| during both events. |
| |
| "Technical Specification (TS) Bases 3.7.2 defines RWS subsystem operability |
| as having, 'an OPERABLE UHS, one OPERABLE pump, and an OPERABLE flow path |
| capable of taking suction from the intake structure and transferring the |
| water to the RHRSW/ESW Stilling Basin in the pump house.' For both of the |
| events, the only question regarding operability was that of the OPERABLE |
| flowpath. The follow-up engineering assessment concluded that the flowpath |
| remained operable. Actual river water flow, as indicated in the control |
| room, was not impacted by the loss of instrument air throughout the (short) |
| duration of these events. Also, there is no question regarding past or |
| historical operability because the cause of the loss of air was related to |
| air system modifications, which were in process at the time or the events. |
| |
| "Therefore, there was no event or condition alone that could have prevented |
| safety function fulfillment. Once discovered, the appropriate TS action |
| statements were entered. No TS 3.0.3. entry was made (or required to be |
| made). There were no Operations or Conditions Prohibited by TS. No other |
| reporting criteria apply to these events. These events are considered |
| not-reportable under 10CFR50.72 or 10CFR50.73." |
| |
| Notified R3DO (Burgess). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37346 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/19/2000|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 01:26[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/18/2000|
+------------------------------------------------+EVENT TIME: 22:30[CDT]|
| NRC NOTIFIED BY: BRIAN GRANT |LAST UPDATE DATE: 09/19/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Refueling |0 Refueling |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEGRADED WHILE SHUTDOWN - FAILED CONTAINMENT LEAK RATE TEST |
| |
| System Engineering reports the local leak rate test results for 3A Feedwater |
| Header Inboard and Outboard Drywell Check Valves (3-0220-58A & 3-0220-62A) |
| are indeterminate due to excessive leakage. This exceeds the containment |
| pathway leakage values allowed by Technical Specifications Primary |
| Containment Leakage Rate Testing Program. |
| |
| The licensee will notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37347 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/19/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 11:23[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 09/15/2000|
+------------------------------------------------+EVENT TIME: 04:46[CDT]|
| NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 09/19/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JEFF SHACKELFORD R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ESF ACTUATION - CONTROL ROOM FILTRATION SYSTEM (CREFS) |
| |
| On 9/15/00, at 0446 the CREFS initiated due to receiving an actuation signal |
| based on control building high gas activity. All automatic actions were |
| verified to have occurred. It was determined that the control building high |
| gas activity was caused by a temperature inversion and not an actual plant |
| condition (i.e., radiological release). The control building high gas |
| activity alarm cleared at 0450 and at 0459 CREFS was returned to a normal |
| standby lineup. |
| |
| It was originally believed that this condition was not reportable due to it |
| being an invalid actuation. Further review of this condition has determined |
| that the condition was the result of a valid signal caused by an |
| environmental condition. |
| |
| Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37348 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 09/19/2000|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 15:07[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 09/19/2000|
+------------------------------------------------+EVENT TIME: 13:00[EDT]|
| NRC NOTIFIED BY: NICK LAVATO |LAST UPDATE DATE: 09/19/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM RULAND R1 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LICENSEE 24-HOUR REPORT |
| |
| "While 12 Pretreated Water Storage Tank (PTWST) was removed from service for |
| planned maintenance, the Diesel Driven Fire Pump was also removed from |
| service to realign its suction flowpath to 11 PTWST on 7/6/00. Per the |
| Technical Requirements Manual, this nonconformance requires that a Special |
| Report be submitted to the NRC, by telephone, within 24 hours." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37349 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 09/19/2000|
|LICENSEE: QUALITY TESTING AND ENGINEERING, INC.|NOTIFICATION TIME: 15:32[EDT]|
| CITY: MESQUITE REGION: 4 |EVENT DATE: 01/14/2000|
| COUNTY: STATE: TX |EVENT TIME: [CDT]|
|LICENSE#: L05222-001 AGREEMENT: Y |LAST UPDATE DATE: 09/19/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JEFF SHACKELFORD R4 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JAMES OGDEN (FAX) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE |
| |
| "Troxler Model 4640: Serial No. 240, with the following source: 8 |
| millicuries Cs-137; Serial No. 50-3271. Stolen January 14, 2000, from a |
| parked vehicle at a Kroger store at 525 North Galloway, Mesquite, Texas. |
| Gauge was stolen between 6 and 7 p.m. while the driver/operator stopped |
| enroute to the company storage facility. Texas Licensee is (QTE) Quality |
| Testing and Engineering, Inc. (L05222-001) of Dallas, Texas. Mesquite Police |
| Department was notified. The gauge has not been recovered." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37350 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 09/19/2000|
|LICENSEE: TOLUNAY WONG ENGINEERS, INC. |NOTIFICATION TIME: 15:32[EDT]|
| CITY: HOUSTON REGION: 4 |EVENT DATE: 08/01/2000|
| COUNTY: STATE: TX |EVENT TIME: [CDT]|
|LICENSE#: L04848-001 AGREEMENT: Y |LAST UPDATE DATE: 09/19/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JEFF SHACKELFORD R4 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JAMES OGDEN (FAX) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE |
| |
| "Troxler Model 3430: Serial No. 26131, with the following sources: 8 |
| millicuries Cs-137; Serial No. 75-9150 and 40 millicuries Am-241/Be; Serial |
| No. 47-22513. Stolen from an unauthorized storage location - 16545 Loch |
| Katrine Land, Houston, Texas (residence of the driver/operator) on July |
| 31-August 1, 2000. A police report was made with the Houston Police |
| Department. Texas Licensee is Tolunay Wong Engineers, Inc. (L04848-001) of |
| Houston, Texas. Steel cables securing the gauge in the truck were cut. The |
| gauge was stolen during the hours of darkness. The gauge has not been |
| recovered." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37351 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 09/19/2000|
|LICENSEE: RABA-KISTNER |NOTIFICATION TIME: 15:32[EDT]|
| CITY: AUSTIN REGION: 4 |EVENT DATE: 09/14/2000|
| COUNTY: STATE: TX |EVENT TIME: [CDT]|
|LICENSE#: L01571-002 AGREEMENT: Y |LAST UPDATE DATE: 09/19/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JEFF SHACKELFORD R4 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JAMES OGDEN (FAX) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - LOST/STOLEN TROXLER GAUGE |
| |
| "Troxler Model 3411B: Serial No. 12037, with the following sources: assayed |
| 5.4 millicurie Cs-137; Serial No. 40-9359 and assayed 39 millicuries |
| Am-241/Be; Serial No. 47-7153. The gauge was stolen or lost on the job site |
| September 14, 2000. The gauge was placed in the back of a company pickup |
| without a case and was not secured. The driver/operator remembers placing |
| the tailgate in the up/closed position. The driver had a short conversation |
| away from the truck and then departed the worksite. While driving along |
| RM620 between Texas Highway 183 and Interstate Highway 35 (Austin, Texas), |
| he noticed his tailgate was in the down/open position and immediately |
| stopped. The gauge was gone. It is not known if the gauge was stolen from |
| the worksite or lost along the highway. The gauge was not found by a company |
| search of the route taken by the driver. A police report was filed with the |
| Austin Police Department. Texas Licensee is Raba-Kistner (L01571-002) of |
| Austin, Texas. The gauge was unsecured and not under direct surveillance at |
| the time of the loss The gauge has not been recovered." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37352 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 09/19/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 16:53[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 09/19/2000|
+------------------------------------------------+EVENT TIME: 14:00[EDT]|
| NRC NOTIFIED BY: KEVIN McLAUGHLIN |LAST UPDATE DATE: 09/19/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM RULAND R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 50, APPENDIX R ISSUE |
| |
| "During part of the Appendix R safe shutdown circuit review, it was |
| discovered that a fire in the screenhouse could cause grounds to |
| undervoltage cable L785 for bus 17 that could blow the control circuit fuses |
| for 'B' D/G, preventing it from starting. The 'A' D/G would not be available |
| for a fire in the screenhouse since it does not have an isolation breaker |
| located outside the screenhouse to isolate the 'A' D/G from bus 18. |
| Consequently, neither D/G would operate without repairs to place the 'B' D/G |
| to local and replace the blown fuses." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37353 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 09/19/2000|
|LICENSEE: TRANSALTA CENTRALIA MINING, LLC |NOTIFICATION TIME: 20:02[EDT]|
| CITY: CENTRALIA REGION: 4 |EVENT DATE: 09/13/2000|
| COUNTY: STATE: WA |EVENT TIME: [PDT]|
|LICENSE#: WN-I0241-1 AGREEMENT: Y |LAST UPDATE DATE: 09/19/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JEFF SHACKELFORD R4 |
| |JOHN GREEVES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TERRY FRAZEE (EMAIL) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - SOURCE DETACHED FROM DRIVE ROD |
| |
| "The licensee notified the WA Department of Health, Division of Radiation |
| Protection (WDOH), of a mechanical failure involving a Ronan Engineering |
| Company Model SA-4 gauging device. The device is specifically licensed for |
| density process measurements and uses a Cesium 137 sealed source, Amersham |
| Model CDC.711M not to exceed 74 gigabecquerels (2 curies). The source is |
| normally mounted at the end of a source rod, approximately six feet long. |
| In this particular model version, the source rod consists of two |
| screw-together extensions (approximately two and a half feet each) which |
| screw into the same diameter source holder (approximately half a foot long). |
| When operating, the rod with source is lowered through the shielded storage |
| position, into the integral and enclosed dry well tube. When not in |
| operation, the rod with source can be raised to place the source into a safe |
| position inside the main shielding. An authorized user realized that a |
| problem existed when attempting to withdraw the source to the safe position. |
| Apparently the rod did not have a normal feel when it was raised. |
| Preliminary indication was the source had separated from the source rod and |
| fallen to the bottom of the insertion dry well. The licensee's RSO and its |
| health physics consultant surveyed the area and determined there wasn't a |
| dose rate problem since the process slurry was still providing ample |
| shielding. The slurry was maintained in-place and the area adjacent to the |
| dry-well access point was posted as a restricted area. |
| |
| "The recovery operation took place on September 18, with WDOH staff actively |
| overseeing the operation. The health physics consultant determined the |
| upper source rod section appeared simply to have come unscrewed from the |
| lower sections, apparently from the vibration of the slurry separator on |
| which the gauge was mounted. However, it was necessary to remove the device |
| from it's bracket and up-end it to allow the source to slide back to the top |
| of the device. Once the end was visible the parts were screwed back |
| together and the unit re-installed. It was also determined that the source |
| holder was partially unscrewed from the middle rod section as well. Both |
| connections were coated with "lock-tight" and tightened. |
| |
| "Radiation readings increased from background to about 50 mR/hr in the |
| general area during the recovery operation. Contact reading on the dry well |
| near the estimated source position was greater than 5 R per hour. Actual |
| recovery working time was about 20 minutes. Both individuals involved |
| received an indicated 25 millirem exposure on their pocket dosimeters. |
| |
| "The health physics consultant indicated that this source rod was of an |
| older style for this particular Ronan device. The three other devices of |
| this model at the licensee's facility were checked and appeared not to be |
| in |
| danger of separating. The licensee plans on upgrading to a newer style rod |
| during an up-coming maintenance shutdown. The recovery operation was |
| successfully completed." |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021