Event Notification Report for July 25, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/24/2002 - 07/25/2002
** EVENT NUMBERS **
37917 39011 39072 39073 39086 39087 39088
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|General Information or Other |Event Number: 37917 |
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| REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE:
04/13/2001|
|LICENSEE: FLORIDA TESTING AND ENVIRONMENTAL |NOTIFICATION TIME:
14:55[EDT]|
| CITY: LAKELAND REGION: 2 |EVENT DATE: 04/13/2001|
| COUNTY: STATE: FL |EVENT TIME: 14:00[EDT]|
|LICENSE#: 2058-L AGREEMENT: Y |LAST UPDATE DATE: 07/22/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MIKE ERNSTES R2 |
| |ERIC LEEDS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: EAKINS | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| STOLEN HUMBOLDT NUCLEAR GAUGE |
| |
| The device was stolen from a job site in Valrico, Florida, from a truck |
| after the chain had been cut. The theft was reported to the police |
| department, and a reward will be offered by the licensee. The device was a |
| Humboldt (model #5001, serial #1287) containing Cs-137/Am-241(8/40 |
| millicuries). |
| |
| ***** UPDATE RECEIVED AT 1728 ON 07/22/02 FROM CHARLIE ADAMS TO LEIGH |
| TROCINE ***** |
| |
| A member of the public discovered the stolen Humboldt soil moisture density |
| gauge (model #5001, serial #1287) today in Plant City, Florida (between |
| Tampa and Orlando near Lakeland) not far off of Interstate 4. The gauge was |
| originally stolen on 04/13/01, and a Deputy at the site reported that the |
| gauge looked like it had been at the discovery site for a long time. It was |
| reported that the gauge appeared to be in the case and did not appear |
| damaged. Representatives from the Hillsborough County Sheriff's Office are |
| currently guarding the device at the discovery site, and a Florida Bureau of |
| Radiation Control representative is en route to the scene. |
| |
| (Call the NRC operations officer for a Florida Bureau of Radiation Control |
| contact telephone number.) |
| |
| The NRC operations officer notified the R2DO (Charlie Payne) and NMSS EO |
| (Eric Leeds). |
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.
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39011 |
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| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 06/22/2002|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 17:02[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/21/2002|
+------------------------------------------------+EVENT TIME: 01:00[CDT]|
| NRC NOTIFIED BY: TRACY ALDRICH |LAST UPDATE DATE: 07/24/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROGER LANKSBURY R3 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
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EVENT TEXT
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| SHIFT SECURITY STAFFING BELOW SECURITY PLAN LEVEL |
| |
| A security guard failed a random drug test and was immediately removed from |
| duties. This placed the site below the minimum security level for |
| approximately 1 hour. (Contact the HOO for more details.) |
| |
| ***** RETRACTION RECEIVED AT 1805 EDT ON 07/24/02 FROM JAY GERONDALE TO |
| LEIGH TROCINE ***** |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On 06/22/02, PBNP provided a courtesy notification regarding a situation |
| where for a brief period of time security shift staffing fell below the |
| minimum staffing levels specified in the PBNP security plan. The purpose of |
| this notification was for information only and not because the licensee had |
| determined the event to be reportable in accordance with either 10 CFR 73.71 |
| or 10 CFR 26.73. Further, the situation did not result in violation of |
| security plan requirements since the security plan provides an allowable |
| period of time for call in of replacement personnel when unanticipated |
| absences occur. Replacement personnel were called in and reported for duty |
| well within the period of time specified in the security plan." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Chris Miller). |
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|General Information or Other |Event Number: 39072 |
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| REP ORG: ARIZONA RADIATION REGULATORY AGENCY |NOTIFICATION DATE:
07/19/2002|
|LICENSEE: ARIZONA HEART HOSPITAL |NOTIFICATION TIME: 11:30[EDT]|
| CITY: PHOENIX REGION: 4 |EVENT DATE: 07/17/2002|
| COUNTY: STATE: AZ |EVENT TIME: 14:30[MST]|
|LICENSE#: 07-443 AGREEMENT: Y |LAST UPDATE DATE: 07/19/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL R4 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: AUBREY V. GODWIN | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT: EQUIPMENT FAILURE |
| |
| |
| "On July 17, 2002, the Arizona Radiation Regulatory Agency was notified by |
| the Licensee that a Novoste Beta-Cath system utilizing 55mCi (2.04GBq) of |
| Strontium-90 had failed to retract after completing treatment of a patient. |
| Within seconds of determining that a failure had occurred, the Licensee |
| implemented emergency withdrawal procedures and successfully removed the |
| source without causing a misadministration. The patient was surveyed and |
| confirmed that all treatment radioactive material had been removed. |
| |
| "Initial examination by the Licensee did not determine a probable cause of |
| the failure of the return of the source to the shielded condition. The |
| entire system is being returned to the manufacturer for evaluation. Georgia |
| is aware of this event. |
| |
| "Agency continues to investigate this event. |
| "No press coverage is occurring or expected for this event. |
| |
| "First Notice: 02-9 |
| |
| "The State of Georgia and the U.S. NRC, is being notified of this event." |
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|General Information or Other |Event Number: 39073 |
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| REP ORG: IOWA RADIATION PROTECTION |NOTIFICATION DATE: 07/19/2002|
|LICENSEE: STORK-TWIN CITY TESTING CORPORATION |NOTIFICATION TIME:
12:03[EDT]|
| CITY: OSCEOLA REGION: 3 |EVENT DATE: 07/17/2002|
| COUNTY: STATE: IA |EVENT TIME: 09:00[CDT]|
|LICENSE#: 0282-2-77-IR1 AGREEMENT: Y |LAST UPDATE DATE: 07/19/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MONTE PHILLIPS R3 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GEORGE JOHNS | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| BROKEN RADIOGRAPHER CAMERA |
| |
| "As a result of one of our cameras had a source jammed because the camera |
| fell from a ladder it was sitting on during an exposure, we are submitting |
| the following response. |
| |
| |
| "Project Information: |
| |
| "Date: July 17, 2002 at approx. 9:00 A.M. |
| Rural water tower, south of Osceola, Iowa approx. 4 miles |
| Jobsite- down a dead-end road, in a field |
| Source S.N. 04016B 40.5 curies |
| Contractor: Phoenix Fabricators & Erectors, Inc. |
| |
| "Stork-Twin City Testing Corporation was at a temporary project site |
| performing radiographic testing when the camera fell off a ladder the camera |
| was sitting on (approx. 3 feet to the ground). The source would not crank |
| back into it's shielded position. I asked him, if they had resecured the |
| area and his response was that they had and that they had also informed the |
| contractor at the site of this incident. I told him, I was on my way and |
| arrived at the site approx. one hour later. I loaded my truck with lead |
| shielding and tools that might be needed to free up the source. Arriving at |
| the project site, I surveyed the guide tube from a distance and found that |
| the source was approx. 1 foot from the camera. They had the crank apart, so |
| you could pull on the cable, in which I had them do prior to my arrival, but |
| they said it would not move, I then tried this myself. I pushed on the cable |
| and then pulled it and the source went in the camera to it safe position. We |
| surveyed the camera and the guide tube and confirmed it was secured in the |
| camera. We then unconnected the control cable and checked the source end |
| with a nogo gauge and found it to be OK, we also cranked the cable out and |
| checked it for any bends or other damage and found it to be OK. We removed |
| the bent guide tube and replaced it with a good tube. We then cranked the |
| source out and made sure everything was functioning properly. |
| |
| "We then had an onsite safety meeting, which concluded that this would be |
| avoided in the future, by tying the camera to a stationary object so the |
| camera cannot fall to the ground and bend the guide tube. |
| |
| "There was no over exposure to the public (contractor's personnel) or to the |
| radiographers during this incident and the radiographers performed their |
| duties in a satisfactory manner, concerning the safety for all and the |
| following of our accident procedures." |
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|General Information or Other |Event Number: 39086 |
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| REP ORG: ROSEMOUNT NUCLEAR INSTRUMENTS, INC |NOTIFICATION DATE:
07/24/2002|
|LICENSEE: ROSEMOUNT NUCLEAR INSTRUMENTS, INC |NOTIFICATION TIME:
11:42[EDT]|
| CITY: EDEN PRAIRIE REGION: 3 |EVENT DATE: 07/24/2002|
| COUNTY: STATE: MN |EVENT TIME: [CDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/24/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHRIS MILLER R3 |
| |RICHARD CONTE R1 |
+------------------------------------------------+VERN HODGE NRR |
| NRC NOTIFIED BY: GERALD HANSON | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| NOTIFICATION UNDER 10 CFR PART 21 FOR HIGH LINE PRESSURE CORRECTION
|
| METHODOLOGY (INACCURATE TECHNICAL ADVICE RELATED TO ROSEMOUNT
TRANSMITTERS) |
| |
| The following text is a portion of a facsimile received from Rosemount |
| Nuclear Instruments, Inc.: |
| |
| "Pursuant to 10 CFR Part 21, Paragraph 21.21(b), Rosemount Nuclear |
| Instruments, Inc. (RNII) is writing to inform you of an instance in which |
| RNII provided inaccurate technical advice related to high line pressure |
| correction of Rosemount transmitters to one customer. The technical advice |
| was transmitted to Rochester Gas and Electric via letters sent to this |
| customer in April 1991. The letters were intended to provide supplemental |
| guidance to the published RNII product manuals for calibration of pressure |
| transmitters with high line pressure applied. The result of implementation |
| of the technical guidance in these letters would be to improperly correct |
| for the effect of line pressure on transmitter output. A recent |
| communication between RNII and this customer alerted RNII to the inaccurate |
| supplemental technical guidance. RNII has subsequently corrected this |
| advice. The standard procedure for correcting for high line pressure |
| contained in RNII's product manuals is accurate." |
| |
| "[...]" |
| |
| "2.0 Identification of items supplied:" |
| |
| "Model 1152 and Model 1154 Pressure Transmitters are specifically addressed |
| in the communications to the customer. The concept of high line pressure |
| correction is applicable to all RNII pressure transmitter models." |
| |
| "[...]" |
| |
| "4.0 Nature of the failure and potential safety hazard:" |
| |
| "This notification relates to an instance in which RNII provided incorrect, |
| application specific supplemental line pressure correction advice to a |
| single customer. This incorrect advice was contained in letters sent to |
| Rochester Gas and Electric in April 1991. The high line pressure correction |
| procedures provided in RNII pressure transmitter product manuals are not |
| affected and are accurate." |
| |
| "RNII does not have sufficient information relative to the applications to |
| determine the safety significance of this situation." |
| |
| "5.0 The corrective action which is taken, the name of the individual or |
| organization responsible for that action, and the length of time taken to |
| complete that action:" |
| |
| "Corrective Action:" |
| |
| "RNII has contacted the affected customer, and through a series of verbal |
| and electronic communications, provided the correct supplemental technical |
| information relative to high line pressure effect for the application in |
| question. RNII will follow up these communications with a formal detailed |
| letter to this customer. Completion Date: 31 July 2002." |
| |
| "Internal RNII Corrective Actions:" |
| |
| "1. The customer provided RNII with copies of the information originally |
| supplied by RNII regarding the supplemental high line pressure correction |
| advice. RNII reviewed this information along with the current request for |
| clarification of the supplemental high line pressure correction for a |
| specific application." |
| |
| "2. Transmitter testing was performed to establish additional assurance |
| that the current technical advice given to the customer was correct." |
| |
| "3. Other customer correspondence files were reviewed to look for |
| occurrences of incorrect supplemental technical information. No occurrences |
| were identified." |
| |
| "4. Training of appropriate RNII personnel reinforcing the importance of |
| providing accurate supplemental technical information will be performed. |
| Completion Date: 2 August 2002." |
| |
| "5. Current administrative procedures and controls will be reviewed to |
| provide confidence that supplemental technical information being transmitted |
| to customers is accurate. Following this review, further corrective action |
| will be initiated and implemented if appropriate. Completion Date: 16 |
| August 2002." |
| |
| "6.0 Any advice related to the potential failure of the item:" |
| |
| "This notification specifically addresses detailed, supplemental technical |
| information provided to one customer. There should not be any potential |
| failure concern relative to hardware, and RNII's pressure product manuals |
| are unaffected." |
| |
| (Call the NRC operations officer for contact information.) |
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|Power Reactor |Event Number: 39087 |
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| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 07/24/2002|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 15:14[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 07/24/2002|
+------------------------------------------------+EVENT TIME: 12:26[EDT]|
| NRC NOTIFIED BY: BRUCE SHICK |LAST UPDATE DATE: 07/24/2002|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION REGARDING A DISCHARGE OF APPROXIMATELY 13 GALLONS
OF |
| FUEL OIL TO THE CHESAPEAKE BAY |
| |
| Approximately 13 gallons of #2 fuel oil was released to the Chesapeake Bay |
| via the storm drain when the 1B diesel generator fuel oil day tank was |
| overfilled during the calibration of the level switches. The control room |
| was notified at 1226, and the release has been secured at 1355. The spill |
| mitigation plan and ERPIP were both implemented, and the boom is in place at |
| the outfall to catch any residual. |
| |
| The licensee notified the Maryland Department of the Environment, National |
| Response Center, and NRC resident inspector. |
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|Power Reactor |Event Number: 39088 |
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| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 07/24/2002|
| UNIT: [1] [] [] STATE: MD |NOTIFICATION TIME: 17:47[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 07/24/2002|
+------------------------------------------------+EVENT TIME: 16:28[EDT]|
| NRC NOTIFIED BY: CHARLES MORGAN |LAST UPDATE DATE: 07/24/2002|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE 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 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| MANUAL REACTOR TRIP DUE TO DECREASING OIL LEVEL AND INCREASING THRUST
|
| BEARING TEMPERATURE ON ONE OF FOUR REACTOR COOLANT PUMPS |
| |
| Indications of lowering oil level were observed on the 11A reactor coolant |
| pump. While the licensee was investigating whether or not the indications |
| were valid, thrust bearing temperature began to increase. As a result, |
| operators manually tripped the reactor from 100% power at 1628, and |
| operators subsequently secured the 11A reactor coolant pump. All control |
| rods fully inserted, and all systems function as required in response to the |
| manual reactor trip. None of the primary or secondary relief valves lifted, |
| and there were no emergency core cooling system injections and engineered |
| safety feature actuations. |
| |
| The unit is currently stable in Mode 3 (Hot Standby). Normal charging and |
| letdown, pressurizer heaters and sprays, and the remaining three reactor |
| coolant pumps are currently being utilized for primary system level, |
| pressure, and transport control. Water is currently being supplied to the |
| steam generators via normal condensate and feedwater, and secondary steam is |
| being dumped to the condenser. The auxiliary feedwater system remains in |
| standby. Containment parameters remain normal, and offsite power is |
| available. All emergency core cooling systems and engineered safety |
| features are operable and available with the exception of the 1B emergency |
| diesel generator, which was removed from of service for planned maintenance |
| this morning. |
| |
| The licensee notified the NRC resident inspector. |
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