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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39082 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|General Information or Other |Event Number: 39134 |
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| 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
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| 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. |
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|General Information or Other |Event Number: 39137 |
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| 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
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| 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." |
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|General Information or Other |Event Number: 39138 |
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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." |
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|Power Reactor |Event Number: 39140 |
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| 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
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| 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. |
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|Power Reactor |Event Number: 39142 |
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| 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
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| 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. |
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