Event Notification Report for August 22, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/21/2002 - 08/22/2002 ** EVENT NUMBERS ** 39082 39134 39137 39138 39140 39142 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39082 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 07/22/2002| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 19:14[EDT]| | RXTYPE: [1] GE-4 |EVENT DATE: 07/22/2002| +------------------------------------------------+EVENT TIME: 17:10[EDT]| | NRC NOTIFIED BY: GENE DORMAN |LAST UPDATE DATE: 08/21/2002| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE R1 | |10 CFR SECTION: | | |AIND 50.72(b)(3)(v)(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 +------------------------------------------------------------------------------+ | DISCOVERY OF A HIGH PRESSURE COOLANT INJECTION (HPCI) FLOW CONTROLLER | | INDICATION OF 500 GPM DURING RESTORATION FROM A CORE SPRAY SYSTEM | | SURVEILLANCE TEST AND WITH THE HPCI SYSTEM IN STANDBY | | | | The following text is a portion of a facsimile received from the licensee: | | | | "During restoration from surveillance testing on the 'B' core spray system, | | the flow controller for the HPCI system (23FI-108-1) was observed to be | | reading 500 gpm with the HPCI system in standby. The HPCI system was | | declared inoperable, and [Technical Specification] 3.5.C.1.b was entered | | requiring [either] restoration of 'B' core spray or HPCI to operable status | | within 24 hours or [commencement of a unit] shutdown. 'B' core spray was | | restored to operability at 1732, and the plant exited [Technical | | Specification] 3.5.C.1.b and entered [Technical Specification] 3.5.C.1.a | | placing the plant in a [7-day limiting condition for operation (LCO)]." | | | | "Since no actuations occurred and [since] no shutdown was initiated, this is | | only reportable under 10CFR50.72(b)(3) criteria, specifically 10 CFR | | 50.72(b)(3)(v)(D). This is based on the guidance in NUREG 1022, Rev. 2. | | Since HPCI is a single train system, even though [technical specifications] | | allow a 7-day LCO, declaring HPCI [inoperable] is reportable." | | | | "The only unusual/not understood thing associated with this is the flow | | indication of 500 gpm. There were no actuations required so all equipment | | functioned and continues to function as expected. There are no radiological | | releases associated with this event." | | | | The licensee plans to notify the NRC resident inspector. | | | | | | ****RETRACTION ON 08/21/02 AT 0959 ET BY RICH PLASSE TAKEN BY | | MACKINNON***** | | | | "During troubleshooting, it was noted that manipulation of terminal screws | | on one of the components caused a step output change similar in magnitude to | | that observed on the indicator. Components were replaced and the instrument | | calibrations re-performed, with the resulting indication returning to | | normal. A review of plant data indicated that an intermittent indication | | problem was evident in the instrument loop after April 30, 2002, when | | maintenance had been performed that included the replacement of several | | instrument loop components. Thus, it appears that the intermittent problem | | began as a result of this maintenance activity. | | | | "Based on the review of both calibration information as well as satisfactory | | performance of the two HPCI System surveillances during the affected time | | frames (including when HPCI was in the "faulted condition"), it was | | determined that the observed condition had no impact on the capability of | | the HPCI System to perform its safety function, and thus the system remained | | operable. Therefore, the above referenced notification is being retracted". | | NRC R1DO (Cliff Anderson) notified. | | | | | | The NRC Resident Inspector was notified of this Retraction by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39134 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MA RADIATION CONTROL PROGRAM |NOTIFICATION DATE: 08/16/2002| |LICENSEE: BRISTOL-MYERS SQUIBB MEDICAL IMAGING |NOTIFICATION TIME: 11:02[EDT]| | CITY: BILLERICA REGION: 1 |EVENT DATE: 08/14/2002| | COUNTY: STATE: MA |EVENT TIME: [EDT]| |LICENSE#: 60-0088 AGREEMENT: Y |LAST UPDATE DATE: 08/16/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |GLENN MEYER R1 | | |C.W. (BILL) REAMER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KENATH TRAEGDE | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT - PERSONNEL OVER EXPOSURE | | | | "Cyclotron chemistry technician received 4.56 rem TEDE in one week. The | | worker's exposure for the calendar year is now 5.79 rem. The cause of the | | additional exposure is related to work performed directly with cyclotron | | target material. This exposure was incurred over a period of one week. The | | details of the event are under investigation." | | | | The exposure took place the week of July 28 to August 4, 2002. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39137 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 08/19/2002| |LICENSEE: URS CORPORATION |NOTIFICATION TIME: 16:33[EDT]| | CITY: CENTRALIA REGION: 4 |EVENT DATE: 08/19/2002| | COUNTY: STATE: WA |EVENT TIME: [PDT]| |LICENSE#: WN-I0172-1 AGREEMENT: Y |LAST UPDATE DATE: 08/19/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |WILLIAM JOHNSON R4 | | |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: TERRY C. FRAZEE (e-mail) | | | HQ OPS OFFICER: MIKE NORRIS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING THEFT OF MOISTURE/DENSITY GAUGE | | | | "The licensee reported the theft of a Campbell Pacific Nuclear | | moisture/density gauge (model MC-1DRP, serial number MD01005902). The gauge | | contained a 1.85 GBq (50 [millicuries]) Am-Be source and a 0.37 GBq (10 | | [millicuries]) Cs-137 source. An authorized user had been working at a | | temporary job site for two weeks. On Sunday, August 18 at 8:00 p.m. the | | authorized user parked his pick-up truck in the parking lot of a local motel | | in Centralia. The gauge was in back under the locked canopy, but visible. | | The gauge box was locked but not secured within the bed of the truck. When | | the authorized user went out to his truck at 6:00 a.m. on Monday the 19th | | the gauge was gone. The back window of the canopy had been forced open. | | Nothing else was missing from the truck (not much else of value was in the | | truck). The theft was reported to the Centralia police and to the licensee's | | RSO. The RSO notified the Department." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39138 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: ALABAMA RADIATION CONTROL |NOTIFICATION DATE: 08/19/2002| |LICENSEE: UNIVERSITY OF SOUTHERN ALABAMA |NOTIFICATION TIME: 16:47[EDT]| | CITY: MOBILE REGION: 2 |EVENT DATE: 06/28/2002| | COUNTY: STATE: AL |EVENT TIME: [CDT]| |LICENSE#: 582 AGREEMENT: Y |LAST UPDATE DATE: 08/19/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MARK LESSER R2 | | |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JIM McNEES (fax) | | | HQ OPS OFFICER: MIKE NORRIS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING 2 MEDICAL MISADMINISTRATIONS | | | | "Alabama licensee identifies two misadministrations from previous year. | | | | "By telephone notification on June 28, 2002 the University of South Alabama | | (Alabama Radioactive Material License No. 582) notified the State of Alabama | | that during their annual Quality Management Program review they identified | | two possible misadministrations of Iodine-131 from the previous year. | | | | "By letter dated July 8, 2002, and received by the State of Alabama on July | | 11, 2002, the University of South Alabama confirmed that a review of the | | records revealed that: | | | | "A. On April 3,2002, a patient was given 3.9 [millicuries] of iodine-131 for | | a total body diagnostic scan when 3.0 [millicuries] had been prescribed by | | the authorized user. The administered dose exceeded the prescribed dose by | | 30%; and | | | | "B. On August 7,2001, a patient was administered 0.702 [millicuries] of | | iodine-131 for a whole body diagnostic scan when 0.500 [millicuries] had | | been prescribed by the authorized user. The administered dose exceeded the | | prescribed dose by 40%. | | | | "In both cases the patients attending physician concluded that these doses | | had 'no clinical significance to either patient and therefore no untoward | | effects.' He ordered that this not be reported to the patients. | | | | "According to the licensee, these events occurred because the nuclear | | medicine staff was operating under a window wider than the 20% maximum | | deviation allowed in the 420-3-26-.07(2)(m)1.b of the Alabama Rules for | | Control of Radiation. The licensee stated that the nuclear medicine | | department had been using criteria from an article published in the Journal | | of Nuclear Medicine which 'quoted NRC regulations with a greater | | tolerance.' | | | | "The licensees corrective action was to notify nuclear medicine staff | | members both verbally and in writing of the current Alabama regulations. The | | State of Alabama considers the licensee's actions to be appropriate and the | | matter closed." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39140 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 08/21/2002| | UNIT: [1] [] [] STATE: AL |NOTIFICATION TIME: 08:59[EDT]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/21/2002| +------------------------------------------------+EVENT TIME: 07:30[CDT]| | NRC NOTIFIED BY: PETE WEBB |LAST UPDATE DATE: 08/21/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNUSUAL EVENT |KEN BARR R2 | |10 CFR SECTION: |JOSEPH HOLONICH IRO | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |TERRY REIS NRR | | |KEN CIBOCH FEMA | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO FIRE AFFECTING EMERGENCY CORE COOLING SYSTEM | | | | | | Loss of "A" Train Service Water as a result of a fire on the "1C" Service | | Water pump. The "1C" pump tripped and the "1A" Service Water was out of | | service for maintenance. Fire was out at 0724 CDT. Actions being taken to | | restore the "A" Train Service Water. The "1B" Service Water pump remained | | running during the entire event. System pressure remained at required | | value. | | | | The Fire Protection System for the "1C" Service Water pump actuated and | | extinguished the fire. When the fire brigade arrived the fire was already | | out. The licensee did not need offsite help for the fire. "B" Train | | Service Water is operating. | | The licensee notified State and local officials of the declaration of an | | Unusual Event. | | | | The NRC Resident Inspector was notified of this event by the licensee. | | | | | | ****UPDATE AT 0931 ET ON 08/21/02 BY BOB VANDERBYE TAKEN BY MACKINNON**** | | | | Unusual event has been terminated at 0814 CT as a result that there was no | | fire and the plant is stable. No fire was seen but a large arc was seen when | | the "1C" Service Water pump tripped. State and Local officials will be | | notified by the licensee that the Unusual event was terminated at 0814 CT. | | R2DO (Ken Barr), NRR EO (Terry Reis), & FEMA (Ken Ciboch) notified. | | | | The NRC Resident Inspector will be notified by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39142 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 08/21/2002| | UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 21:03[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 08/21/2002| +------------------------------------------------+EVENT TIME: 14:00[CDT]| | NRC NOTIFIED BY: EURMAN HENSON |LAST UPDATE DATE: 08/21/2002| | HQ OPS OFFICER: MIKE NORRIS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |WILLIAM JOHNSON R4 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNANALYZED CONDITION REGARDING RCS BORATION REQUIREMENTS | | | | "On August 21, 2002, with Callaway Plant in Mode 1 at 100 % power, it was | | determined that a potential unanalyzed condition had existed regarding | | Reactor Coolant System (RCS) boration requirements when in Mode 3 below the | | P-11 setpoint of 1970 psig RCS pressure. During an extent of condition | | review, a concern had been identified regarding the Westinghouse analysis of | | Steam Line Breaks in Mode 3 below P-11. In order to conclude that acceptable | | core performance results would be obtained for a lower Mode 3 Steam Line | | Break, the Westinghouse analyses assumes that the plant is borated to cold | | shutdown conditions prior to blocking P-11. Discussions with Westinghouse | | confirmed this requirement was applicable to Callaway. Callaway Plant | | procedures did not specifically require that the plant be maintained at Cold | | Shutdown boron concentrations with P-11 blocked. A historical review | | documented that the Callaway Plant shutdown twice within the last three | | years. During these shutdowns, the plant maneuvered through Mode 3 below | | P-11 once during each plant shutdown and once during each plant startup. | | | | "A review of historical data is being conducted for those periods to | | establish actual boron concentrations versus calculated requirements for | | past conditions. Preliminary reviews for three of those periods have been | | completed and document actual boron concentrations of 1397 ppm or greater. | | | | "This condition is being reported as an unanalyzed condition until | | historical reviews determine otherwise. Compensatory actions taken included | | determining a boron concentration that would satisfy accident analysis | | requirements for present plant conditions and revising Callaway Plant | | procedures to require boration to specified boron concentrations for Mode 3 | | operation with P-11 blocked." | | | | P-11(Pressurizer SI Block Permissive) enables BLOCK switches to allow the | | operator to block low Pressurizer pressure SI. | | | | The NRC Resident Inspector has been notified. The Licensee has discussed | | this condition with Wolf Creek. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021