Event Notification Report for June 27, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/26/2002 - 06/27/2002 ** EVENT NUMBERS ** 39010 39014 39015 39020 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39010 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 06/22/2002| | UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 18:27[EDT]| | RXTYPE: [1] GE-4 |EVENT DATE: 06/22/2002| +------------------------------------------------+EVENT TIME: 14:16[EDT]| | NRC NOTIFIED BY: CHRISTOPHER SERATA |LAST UPDATE DATE: 06/26/2002| | HQ OPS OFFICER: RICH LAURA +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |JAMES TRAPP R1 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 A/R Y 100 Power Operation |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC SCRAM AT HOPE CREEK DUE TO TURBINE TRIP | | | | "Immediately following the RPS actuation, the success of the SCRAM was | | evaluated. Initially, the Rod Worth Minimizer indicated that some control | | rods were not fully inserted and control rod 22-31 indicated full out on the | | Full Core Display. Alternate Rod Insertion (ARI) was initiated as per | | established operating procedures. The STA observed all Control Rods except | | 22-31 to be fully inserted on the Core Monitoring System before ARI was | | initiated, indicating the reactor was shutdown without ARI. The indicated | | position of CR 22-31 did not change immediately following the SCRAM, but | | changed over time consistent with a known problem with its | | position-indicating probe. | | | | "Both Reactor Recirculation Pumps tripped as expected from the turbine trip | | above 30% power (End-of-Cycle Recirculation Pump Trip function), and remain | | out of service. The Reactor is presently shutdown. Reactor pressure is 700 | | psig and slowly lowering and reactor level is 32 and stable (normal band | | 30-39). Efforts are underway to stabilize and normalize reactor coolant and | | metal temperatures to allow the restarting of a Reactor Recirculation | | Pump." | | | | The NRC resident inspector was notified by the licensee. | | | | | | * * * UPDATE ON 6/26/02 @ 1530 BY REG 1 TO GOULD * * * | | | | This update is to clarify the above event report by including the first | | paragraph which was originally inadvertently omitted from the NRC write-up. | | The paragraph is included below. | | | | "This 4 hour report s being made pursuant to 10CFR50.72(b)(2)(iv)(B) for | | actuation of the Hope Creek Reactor Protection System (RPS) with the plant | | critical. At 14:16 hours the Hope Creek Reactor RPS actuated, resulting in | | a Reactor SCRAM. Preliminarily the RPS actuation appears to have been | | caused by a Main Turbine trip from high moisture separator level that was | | caused by a trip of the B Secondary Condensate Pump and automatic | | intermediate runback of the Reactor Recirculation Pumps. Follow-up | | investigation will be performed to validate this information." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39014 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MA RADIATION CONTROL PROGRAM |NOTIFICATION DATE: 06/24/2002| |LICENSEE: AEA TECHNOLOGY QSA INC. |NOTIFICATION TIME: 12:42[EDT]| | CITY: BURLINGTON REGION: 1 |EVENT DATE: 06/24/2002| | COUNTY: STATE: MA |EVENT TIME: 10:35[EDT]| |LICENSE#: 12-8361 AGREEMENT: Y |LAST UPDATE DATE: 06/24/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |JAMES TRAPP R1 | | |FRANT NMSS | +------------------------------------------------+DAVIDSON IAT | | NRC NOTIFIED BY: GALLAGHAR |JOSEPH HOLONICH IRO | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AEA Technology QSA, Inc. (AEA) called to notify the State of the report to | | their office of the receipt of a package of very low activity Pu-242/Am-243 | | (12 Bq each) by Knolls Atomic Power Laboratory. AEA was notified by Knolls | | Atomic that the package, received by them on 12/6/01 or 12/7/01, was opened | | on or around 5/20/02, at which time the inner container appeared to have | | been opened, and all contents were absent. | | | | The State Agency was informed by the licensee they received the shipment | | from England on 12/5/01, checked the outer cardboard container for damage, | | and resent the shipment to their customer, Knolls Atomic Power Laboratory in | | New York. The package was received 12/6/01 or 12/7/01. At Knolls, the | | radiation safety staff received the shipment and confirmed the outer package | | was undamaged and delivered it to the end user in the Chemistry Department. | | The user opened the package on or around 5/20/02. Knolls Atomic informed | | AEA they believe the seal on the inner plastic container was intact, but | | that the final container, a flame-sealed glass container, appeared to have | | been opened and the contents removed, in addition, AEA was informed that | | the Federal Bureau of Investigation (FBI) was notified. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39015 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 06/24/2002| | UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 14:35[EDT]| | RXTYPE: [1] GE-4 |EVENT DATE: 06/24/2002| +------------------------------------------------+EVENT TIME: 12:45[CDT]| | NRC NOTIFIED BY: STEPANEK |LAST UPDATE DATE: 06/26/2002| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANNE MARIE STONE R3 | |10 CFR SECTION: | | |DDDD 73.71(b)(1) SAFEGUARDS REPORTS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | MINIMUM SECURITY PERSONNEL STAFFING REQUIREMENTS NOT MET | | | | | | Compensatory measures taken upon discovery. | | | | The NRC Resident Inspector will be informed. | | | | Refer to the HOO for additional details. | | | | | | * * * UPDATE ON 6/26/02 BY ROWLAND TO GOULD * * * RETRACTION | | | | The licensee is retracting this event and classifying it as a loggable event | | and not a reportable one. | | | | The NRC resident inspector was notified. | | | | Reg 3 RDO(Stone) was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39020 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 06/26/2002| | UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 14:04[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/26/2002| +------------------------------------------------+EVENT TIME: 10:02[EDT]| | NRC NOTIFIED BY: FERNSLER |LAST UPDATE DATE: 06/26/2002| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MICHAEL MODES R1 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A SUPERVISOR PERSONNEL WAS DETERMINED TO BE UNDER THE INFLUENCE OF ALCOHOL | | | | Employees access was terminated. | | | | The NRC Resident Inspector was notified. | | | | Contact the HOO for additional information. | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021