Event Notification Report for August 8, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/07/2003 - 08/08/2003 ** EVENT NUMBERS ** 40020 40049 40050 40051 40052 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 40020 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: NC DIV OF RADIATION PROTECTION |NOTIFICATION DATE: 07/25/2003| |LICENSEE: REX HEALTHCARE |NOTIFICATION TIME: 13:09[EDT]| | CITY: RALEIGH REGION: 2 |EVENT DATE: 07/14/2003| | COUNTY: STATE: NC |EVENT TIME: [EDT]| |LICENSE#: 092-0160-1 AGREEMENT: Y |LAST UPDATE DATE: 08/07/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |ANNE BOLAND R2 | | |FRED BROWN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: SHARN M. JEFFRIES | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING MISSING IODINE-125 SEEDS | | | | On 7/22/03 Rex Healthcare personnel discovered that five (5) I-125 seeds | | (activity 0.384 milliCuries/ea for a total of 1.9 milliCuries) were missing. | | The licensee conducted a search of the area between 7/22 and 7/24/03 with | | negative results. | | | | NC Incident No.: 03-32 | | | | *****UPDATE ON 8/7/03 AT 1405 FROM JEFFRIES TO LAURA***** | | | | At 10:30 EDT on 8/7/03, the licensee found the 5 missing I-125 seeds in the | | hospital. The seeds were found contained in a loading apparatus between two | | autoclave valves. The licensee is doing an additional review to evaluate any | | potential radiological exposures. | | | | Notified NMSS (D. Broaddus) and R2DO (S. Cahill). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 40049 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 08/06/2003| | UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 19:12[EDT]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/06/2003| +------------------------------------------------+EVENT TIME: 16:30[EDT]| | NRC NOTIFIED BY: GEORGE STOROLIS |LAST UPDATE DATE: 08/07/2003| | HQ OPS OFFICER: BILL GOTT +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CLIFFORD ANDERSON R1 | |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 | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNANALYZED CONDITION | | | | "On 8/06/2003 at 1630 hours, the Beaver Valley Power Station (BVPS) Unit 2 | | control room was notified by Engineering that the manual operator actions | | specified in Unit 2 post-fire procedures are not adequate for defeating a | | potential fire-induced spurious operation of the Power Operated Relief | | Valves (PORVs). The procedure step de-energizes the PORVs by opening | | breakers at the d-c distribution panel. This action alone would not be | | sufficient to prevent a cable-to-cable hot short from re-energizing the | | circuit since the de-energized circuit is routed in cable trays with other | | energized circuits in the affected fire areas. Preliminary reviews have | | identified the following potentially affected fire areas: | | | | CB-1 Control Building Instrumentation and Relay Area | | CB-2 Control Building Cable Spreading Room | | CB-3 Control Building Main Control Room | | CB-6 Control Building West Communication Room | | CT-1 Cable Tunnel | | CV-1 Cable Vault and Rod Control Area | | SB-1 Emergency Switchgear Room (Orange) | | RC-1 Reactor Containment | | | | "An hourly roving fire watch patrol has been established for the affected | | fire areas as compensatory measures, with the exception of the Main Control | | Room and the Reactor Containment area, until the condition is fully | | evaluated and resolved. The Main Control Room is continuously manned and | | does not require an hourly fire watch patrol. The Reactor Containment area | | is not accessible during normal power operations and, as such, compensatory | | measures for this area will include a once-per-shift verification of remote | | instrumentation by operations personnel to confirm that there are no | | abnormal conditions or indications for this area. | | | | "This condition was discovered during the review of manual operator actions | | for fire-induced spurious operations to confirm the safe shutdown circuit | | analysis is consistent with the manual actions identified in the | | procedures. | | | | "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii) as an | | unanalyzed condition that significantly degraded plant safety since the | | failure to assure the PORVs remain in the closed position could result in | | the failure to meet the fire protection safe shutdown criteria. BVPS Unit 2 | | was licensed to the NUREG 0800 Standard Review Plan 9.5.1 "Fire Protection | | Program", and License Condition 2.F requires compliance to the provisions of | | the approved fire protection program as described in the Final Safety | | Analysis Report. UFSAR Section 9.5A.1.2.1.6 states that the safe shutdown | | capability should not be adversely affected by a fire in any plant area | | which results in spurious actuation of the redundant valves in any one | | high-low pressure interface line. Even though there is a very low | | likelihood of multiple shorts causing a spurious PORV actuation in an | | ungrounded DC circuit, the existing actions to prevent re-energizing the | | circuit and causing a spurious actuation of the PORVs is not consistent with | | the NRC guidance for high-low pressure interface valves. | | | | "The NRC resident inspector has been notified." | | | | * * * UPDATE ON 8/7/03 AT 1726 EDT FROM D. SOMMERS TO E. THOMAS * * * | | | | "On 8/07/03 at 1515, the following additional areas were identified as being | | potentially affected by this condition: | | | | CV-2 Cable vault and Rod Control Area (East) | | CV-3 Cable vault and Rod Control Area (Elev 755'6") | | SB-2 Emergency Switchgear Room (Purple) | | SB-3 Service Bldg. Cable Tray Area | | ASP Alternative Shutdown Panel Room | | | | "Interim compensatory measures in the form of hourly roving watch patrols | | have been expanded to include the above noted areas until the condition is | | fully evaluated and resolved. | | | | "The NRC Resident Inspector has been notified." | | | | Notified the Region 1 Duty Officer (C. Anderson) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 40050 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 08/07/2003| | UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 13:07[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 08/07/2003| +------------------------------------------------+EVENT TIME: 11:31[EDT]| | NRC NOTIFIED BY: DAVID NOYES |LAST UPDATE DATE: 08/07/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CLIFFORD ANDERSON R1 | |10 CFR SECTION: |DAVID SKEEN NRR | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |TIM MCGINTY IRO | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION | | | | "At approximately 1131 [EDT] on August 7, 2003, an error during prompt alert | | notification system testing resulted in all sirens in the town of Duxbury, | | Massachusetts to wail for 15 to 20 seconds. Appropriate state and local | | authorities have been notified. Investigation into the cause is | | continuing." | | | | The NRC Resident Inspector has been notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 40051 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: DEPARTMENT OF THE NAVY |NOTIFICATION DATE: 08/07/2003| |LICENSEE: DEPARTMENT OF THE NAVY |NOTIFICATION TIME: 13:35[EDT]| | CITY: ARLINGTON REGION: 2 |EVENT DATE: 06/03/2003| | COUNTY: STATE: VA |EVENT TIME: [EDT]| |LICENSE#: 45-23645-01NA AGREEMENT: N |LAST UPDATE DATE: 08/07/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |STEPHEN CAHILL R2 | | |JACK WHITTEN R4 | +------------------------------------------------+DOUG BROADDUS NMSS | | NRC NOTIFIED BY: CAPT DAVE FARRAND | | | HQ OPS OFFICER: BILL GOTT | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |ISAF 30.50(b)(2) SAFETY EQUIPMENT FAILUR| | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RADIOGRAPHIC EXPOSURE DEVICE FAILURE | | | | "Description of the equipment problem. On June 3, 2003, gamma radiography | | operations using an AEA Technology/QSA Model 660A exposure device in a | | permanent radiography facility at Shore Intermediate Maintenance Activity | | were being performed under the authority of Naval Radioactive Materials | | Permit (NRMP) No. 0465918--A1NP. On the tenth exposure of the day the | | radiographer attempted to retract the radiographic source into the | | radiographic exposure device. The radiographer placed the drive cable brake | | in the "off" position and rapidly cranked the source in the retract | | direction. The number of turns coming in matched the number of turns going | | out. The permanent facility gamma alarm shut off, however the radiographer | | did not hear the locking slide mechanism engage which is normally heard | | clearly when retracting the source. When attempting to re-expose the source | | as required by the operating procedure, the source did expose again. The | | Radiation Safety Officer was present and directed the radiographer to | | retract the source again. As with the first attempt to retract the source, | | the slide bar did not click in the safe position. Again and the gamma alarm | | shut off. The Radiation Safety Officer entered the permanent facility with, | | an operating survey meter. The locking slide bar indicated green (safe) but | | it was not locked in that position. The Radiation Safety Officer approached | | the device and observed a reading of approximately 8 millirem/hour on the | | front of the device and 10 millirem/hour on the back of the device. She | | exited the permanent facility and discussed the situation with the | | radiographer. The Radiation Safety Officer then directed the radiographer | | to maintain control of the crank assembly handle and she entered the | | permanent facility with a survey meter and pushed the slide bar to the red | | (expose) position. The Radiation Safety officer exited the permanent | | facility and instructed the radiographer to retract the source to the fully | | locked position. The retraction was successful and the slide bar was heard | | to click to the fully green (safe) position. The Radiation Safety Officer | | checked her self-indicating pocket dosimeters which both indicated zero | | exposure. | | | | "The source was transferred to an AEA 650L source changer on June 4, 2003. | | A "dummy" source was installed in the exposure device and the locking slide | | bar was placed in various positions to experiment and recreate the scenario. | | Frequently during these tests, the radiographers were not able to lock the | | slide into place without unlocking the drive cable crank assembly and | | applying minimal pressure towards the expose position. This is considered a | | neutral position and not an exposed position. With minimal pressure the | | slide bar mechanism easily locked into the exposed position. | | | | "Cause of each incident. The cause of the incident appears to be twofold. | | Primarily the compression springs for the posi-lock may have been | | excessively worn. Secondarily, the Shore Intermediate Maintenance Activity, | | San Diego operating procedure did not call for them to unlock the crank | | assembly cable lock prior to rotating the selector ring to the operate | | position and pushing the posi-lock slide bar from the green (retracted) | | position to the red (operate) position as stated in the most recent AEA | | exposure device manual. We believe that the faulty springs were the main | | factor as the posi-lock slide bar can be pushed to the red position with the | | crank assembly cable lock in the "on" position but that procedure may have | | contributed to the excessive wear on the compression springs. | | | | "Name of the manufacturer and model number of equipment involved in the | | incident. The equipment involved in the incident was manufactured by AEA | | Technology/QSA and consisted of a Model 660A exposure device, serial number | | A4450 with a 13.6 curie Ir-192 source. | | | | "Place, date and time of the incident. The incident occurred at Shore | | Intermediate Maintenance Activity, San Diego, California in a permanent | | facility on June 3, 2003. | | | | "Actions taken to establish normal operations. The Radiation Safety Officer | | entered the permanent facility and manually pushed the locking slide bar to | | the unlocked (red) position. The Radiation Safety Officer exited the | | permanent facility and instructed the radiographer to attempt to retract the | | source. The source was successfully retracted to the fully locked position | | and the locking slide bar was heard to lock. | | | | "Corrective actions taken or planned to prevent recurrence. Shore | | Intermediate Maintenance Facility, San Diego replaced the compression | | springs for the posi-lock assembly on the exposure device. Additionally, | | they have changed their operating procedure to unlock the crank assembly | | cable lock prior to rotating the selector ring to the operate position and | | pushing the posi-lock slide bar from the green (retracted) position to the | | red (operate) position." | | | | The licensee notified R2 (Diaz). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 40052 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 08/07/2003| | UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 16:49[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 08/07/2003| +------------------------------------------------+EVENT TIME: 09:15[EDT]| | NRC NOTIFIED BY: DAVID NOYES |LAST UPDATE DATE: 08/07/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CLIFFORD ANDERSON R1 | |10 CFR SECTION: | | |ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS COMM/ASMT/RESPONSE | | | | At 0915 EDT on 8/7/03, during testing of the Prompt Alert Notification | | Sirens, 44 of 112 (39 percent) of the sirens were found to be inoperable due | | to a failed radio repeater. The repeater was repaired, and all sirens | | declared fully operable at 1010 EDT on 8/7/03. | | | | The NRC Resident Inspector was informed of this event. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021