Event Notification Report for October 18, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/17/2002 - 10/18/2002
** EVENT NUMBERS **
39276 39284 39285 39289 39290 39295 39296 39297 39298 39299 39300 39301
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39276 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/12/2002|
| UNIT: [1] [2] [] STATE: CA |NOTIFICATION TIME: 08:02[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/12/2002|
+------------------------------------------------+EVENT TIME: 01:30[PDT]|
| NRC NOTIFIED BY: J. BROWN |LAST UPDATE DATE: 10/17/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KRISS KENNEDY R4 |
|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 54 Power Operation |54 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ALLEGED FITNESS-FOR-DUTY QUESTIONED DUE TO SLEEPING ON WATCH. |
| |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR . |
| |
| ***** RETRACTED ON 10/17/02 AT 22:10 FROM J. BROWN TO A. COSTA ***** |
| |
| The licensee is retracting this event since proper security was maintained |
| in the Owner Controlled Area as required by the Order. |
| |
| Notified R4DO (Pick) via email. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39284 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: LOUISIANA RADIATION PROTECTION DIV |NOTIFICATION DATE: 10/14/2002|
|LICENSEE: SCHLUMBERGER TECHNOLOGY CORP |NOTIFICATION TIME: 16:27[EDT]|
| CITY: CAMERON REGION: 4 |EVENT DATE: 10/12/2002|
| COUNTY: STATE: LA |EVENT TIME: [CDT]|
|LICENSE#: LA-2783-L01 AGREEMENT: Y |LAST UPDATE DATE: 10/14/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KRISS KENNEDY R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SCOTT BLACKWELL (email) | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE - IRRETRIEVABLE WELL LOGGING SOURCE |
| |
| "Agreement State Agency: Louisiana Department of Environmental Quality |
| |
| "Event Report ID No.: LA020013 |
| |
| "License No.: LA-2783-L01 |
| |
| "Licensee: Schlumberger Technology Corp |
| |
| "Event date and Time: October 12, 2002 |
| |
| "Event Location: Miami Corp #1S in Cameron, LA |
| |
| "Event type: Irretrievable Well Logging Source |
| |
| "Notifications: Schlumberger notified the Louisiana Department of Natural |
| Resources and the Louisiana Department of Environmental Quality. |
| |
| "Event description: |
| |
| On October 9, 2002, a well logging tool was stuck down hole. The tool |
| contained a 1.7 Ci source of Cs-137 model number GSRZ with s/n 2009 and a 16 |
| Ci source of Am241Be model number NSR-L with s/n 3068. There were repeated |
| attempts to retrieve the tool. On October 12, 2002, it was decided to |
| abandon the tool. Approval was given from the state of Louisiana on October |
| 12, 2002, to abandon the tool. The approximate depth of the tool is 10,822 |
| feet. A cement plug was going to be placed above the tool, cement is going |
| to be added around the tool, and an upside down drill bit is to be used as a |
| deflection device." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39285 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 10/15/2002|
|LICENSEE: BAYLOR ALL SAINTS MED CENTER, MEDI-PH|NOTIFICATION TIME: 11:35[EDT]|
| CITY: FORT WORTH, DALLAS REGION: 4 |EVENT DATE: 09/25/2002|
| COUNTY: STATE: TX |EVENT TIME: 11:30[CDT]|
|LICENSE#: L2212, L05529 AGREEMENT: Y |LAST UPDATE DATE: 10/15/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GREG PICK R4 |
| |WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS | |
| HQ OPS OFFICER: MIKE RIPLEY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PERSONNEL CONTAMINATION AND EXCESSIVE PACKAGE LEVELS AT NUCLEAR MEDICINE |
| FACILITIES |
| |
| "A 300 millicurie multidose glass vial of technetium-99m was dropped on the |
| floor at about 11:30 am [September 25, 2002] in a hot lab area at Baylor by |
| a nuclear medicine technologist. About 40% of the vial contents spilled on |
| the tech's pants, legs, and shoes. The initial radiation reading on the |
| tech's clothing was 35.2 [millirem]/hr. An initial wipe test of the floor |
| gave a reading of 81,012 dpm. The floor was decontaminated using radiowash |
| until radiation wipe levels were at 366 dpm and the survey meter detected |
| 1.8 [millirem]/hr. The tech's clothing were placed in storage for decay. |
| |
| "An outgoing nuclear medicine ammo box was about three feet from the spill. |
| The box was labeled and had been surveyed and was ready for pickup by the |
| nuclear pharmacy, Medi-Physics. The technologist did not believe the spill |
| had contaminated the ammo box and did not perform an additional survey of |
| it. The ammo box was picked up by a courier for the nuclear pharmacy. The |
| courier picked up the ammo box by using the keypad lock to access the |
| unoccupied hot lab as was his normal routine. |
| |
| "At around 1:00pm, as the courier was leaving the Medi-Physics facility, he |
| surveyed his hands and noticed radiation readings. Both palms were |
| contaminated and so was his shirt and pants. The hands gave readings of 8340 |
| cpm's. The courier was decontaminated to approximate background levels. The |
| only package picked up and transported by the courier was the ammo box from |
| Baylor. The nuclear pharmacy contacted Baylor and notified the State. |
| |
| "The ammo box radiation readings were 2,664,800 cpm's and the main area of |
| contamination read 150 [millirem]/hr. The courier vehicle showed |
| contamination on the door handle, radio knob, steering wheel, and gear |
| shift. Radiation readings were in the range of 81,649 cpm's. The ammo box |
| was placed in storage for decay. The vehicle was quarantined, decontaminated |
| to background revels, and returned to service the following day. |
| |
| "Additional information will be provided to the Agency in the Licensee's |
| written report. An onsite investigation by the Texas Department of Health |
| Bureau of Radiation Control identified items of noncompliance with Agency |
| regulations." |
| |
| Texas Incident No. I-7938 |
| |
| Medi-Physics, Inc (doing business as Amersham Health of Dallas) Dallas, TX |
| - License No. L05529 |
| BaylorAll Saints Med Center, Ft. Worth, TX - License No. L02212 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39289 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ARIZONA RADIATION REGULATORY AGENCY |NOTIFICATION DATE: 10/15/2002|
|LICENSEE: CONSTRUCTION INSPECTION AND TESTING |NOTIFICATION TIME: 19:18[EDT]|
| CITY: TEMPE REGION: 4 |EVENT DATE: 10/15/2002|
| COUNTY: STATE: AZ |EVENT TIME: 15:25[MST]|
|LICENSE#: 7-98 AGREEMENT: Y |LAST UPDATE DATE: 10/15/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GREG PICK R4 |
| |M. WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: AZ RAD REGULATORY AGENCY | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE - LOST OR STOLEN TROXLER MOISTURE DENSITY GAUGE |
| |
| "Date: 15 October 2002 |
| |
| "Time: 3:25 p.m. MST |
| |
| "First Notice No.: 02-15 |
| |
| "Arizona Licensee: Construction Inspection and Testing |
| 2137 West 7th St. |
| Tempe, AZ 85281 |
| |
| "RSO: John Ritter |
| |
| "License No.: 7-98 |
| |
| "Description of event: The licensee reported the loss of a Troxler |
| moisture/density gauge sometime between 1030 and 1115 on 15 October after |
| the technician left a job site in the vicinity of Cactus and 151st Ave. The |
| gauge had been in the back of a pickup with the tailgate down. The gauge did |
| not have a handle lock. A search of his route for several hours failed to |
| turn up the gauge. The gauge is a Troxler Model 3400 series, serial number |
| 29519. It contains approximately 10 millicuries of cesium 137 and |
| approximately 50 millicuries of americium-beryllium. The company is offering |
| a $250 reward for information leading to the return of the gauge and truck. |
| |
| "The U.S. NRC, FBI, Mexico, and the states of Colorado, Nevada, Utah, New |
| Mexico and California are being informed of this incident." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39290 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: COLORADO DEPT OF HEALTH |NOTIFICATION DATE: 10/15/2002|
|LICENSEE: MIDWEST INSPECTION SERVICES |NOTIFICATION TIME: 19:15[EDT]|
| CITY: DENVER REGION: 4 |EVENT DATE: 10/14/2002|
| COUNTY: STATE: CO |EVENT TIME: [MDT]|
|LICENSE#: CO 902-01 AGREEMENT: Y |LAST UPDATE DATE: 10/15/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GREG PICK R4 |
| |M. WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TIM BONZER (VIA FAX) | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING INDUSTRIAL RADIOGRAPHY INCIDENT |
| |
| The following information was documented as a telecon "to file" received by |
| State of Colorado staff: |
| |
| "Received phone notification today from Jeff Conners at Midwest Inspection |
| Services concerning a source disconnect incident that happened yesterday, |
| 10/14/02. Mr. Conners reported a radiography crew, working at a field site |
| north of Denver, was unable to retract an Iridium-192 radiography source |
| back into the camera. The radiographers called Mr. Conners, who is the |
| assistant Radiation Safety Officer, for help. Mr. Conners reported that he |
| responded to the scene and was successful in connecting the source assembly |
| to the drive cable and retracting it back into the radiography camera. He |
| also responded that there were no overexposures to the radiography crew or |
| members of the public. Mr. Conners estimated his exposure for the recovery |
| operation to be about 500 millirem, based on his pocket dosimeter readings. |
| He stated that he would send a detailed written report to the Department |
| within 30 days. The corporate RSO, David Ezell, was also notified of the |
| incident." |
| |
| Contact the Headquarters Operations Officer for additional information. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39295 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 10/17/2002|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 10:27[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/17/2002|
+------------------------------------------------+EVENT TIME: 09:21[EDT]|
| NRC NOTIFIED BY: WHEELER |LAST UPDATE DATE: 10/17/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) IS OUT OF SERVICE DUE TO PLANNED |
| MAINTENANCE |
| |
| |
| At 0921 hours on 10/I7/02, the Safety Parameter Display System (SPDS) was |
| removed from service as part of preplanned work to facilitate future |
| replacement of the Emergency Response Facility Computer System (FRFCS). |
| Electrical service was also interrupted to the Technical Support Center |
| rendering that emergency response facility (ERF) unavailable for use. Work |
| should be complete by mid afternoon. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39296 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 10/17/2002|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 11:24[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 10/17/2002|
+------------------------------------------------+EVENT TIME: 05:15[CDT]|
| NRC NOTIFIED BY: PHIL WARDLOW |LAST UPDATE DATE: 10/17/2002|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS KOZAK R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 97 Power Operation |97 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONDITION WHICH COULD HAVE PREVENTED FULFILLMENT OF A SAFETY FUNCTION |
| |
| "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or |
| Condition that could have prevented fulfillment of a Safety Function needed |
| to Mitigate the Consequences of an Accident. During a post maintenance test |
| run of the 2B Diesel Generator following a planned maintenance window, the |
| Diesel Generator reactive load (VARs) was identified to be erratic, as the |
| Diesel Generator was loaded. At 05:15 CDST on 10/17, it was discovered that |
| a potentiometer in the voltage regulating circuit had erratic output. This |
| potentiometer was not worked on during the planned maintenance window. |
| Because this component failure could have prevented the Diesel Generator |
| from performing its design function, and because the 2B Diesel Generator is |
| the emergency power supply for the High Pressure Core Spray System (HPCS), |
| which is a single train safety system, it has been determined that this |
| failure could potentially effect the Safety Function of this system, and is |
| reportable as an 8 hour ENS notification." |
| |
| "Add info on current results/status below. |
| The required actions of Technical Specification 3.5.1 were entered when the |
| system was made inoperable for the maintenance window on 10/13 at 1900, and |
| are continuing to be followed for the Inoperable High pressure Core Spray |
| System (HPCS), until the Diesel Generator is restored to Operable Status." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39297 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 10/17/2002|
| UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 13:03[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 10/17/2002|
+------------------------------------------------+EVENT TIME: 11:21[EDT]|
| NRC NOTIFIED BY: RANDY BRAMLETT |LAST UPDATE DATE: 10/17/2002|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|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 |
|2 N N 0 Refueling |0 Refueling |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| COMPROMISE OF SAFEGUARDS INFORMATION |
| |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. |
| |
| CONTACT HOO FOR ADDITIONAL DETAILS. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39298 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CREST FOAM INDUSTRIES |NOTIFICATION DATE: 10/17/2002|
|LICENSEE: CREST FOAM INDUSTRIES |NOTIFICATION TIME: 14:37[EDT]|
| CITY: MOONACHIE REGION: 1 |EVENT DATE: 10/17/2002|
| COUNTY: STATE: NJ |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 10/17/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KENNETH JENISON R1 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: LARRY LAVELLE | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MISSING NUCLEAR DENSITY METER |
| |
| The licensee reported a missing Texas Nuclear Density Meter, Model 5201, |
| serial number B764 and source number GV1731. The meter source contains 100 |
| millicuries of Cs-137. The licensee had already contacted the local police |
| department to report the missing meter. The exact date of loss is not known |
| but the last physical audit performed by the licensee was in January 2002. |
| The meter is used to measure the thickness of the foam density. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39299 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 10/17/2002|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 15:50[EDT]|
| RXTYPE: [3] CE |EVENT DATE: 10/14/2000|
+------------------------------------------------+EVENT TIME: 23:00[CDT]|
| NRC NOTIFIED BY: GREGORY SCOTT |LAST UPDATE DATE: 10/17/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GREG PICK R4 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Hot Standby |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT EFW ACTUATION ON 10/14/2000 |
| |
| "Per 10CFR50.73(a), Entergy is providing a verbal notification of an |
| inadvertent actuation of the emergency feedwater (EFW) system at Waterford |
| 3, which occurred on October 14, 2000. This event was initially determined |
| to be not reportable, based on the reasoning that the actuation of the |
| emergency feedwater components were initiated from the Diverse Emergency |
| Feedwater System (DEFAS), and not from an Emergency Feedwater Actuation |
| System (ESFAS) actuation. However, during a technical specification audit in |
| August of 2002, questions were raised regarding the validity of this |
| reportability determination and a condition report was initiated. A |
| subsequent review by licensing completed on August 21, 2002 determined that |
| the event should have been reported per the then existing 10CFR50.72 |
| (b)(3)(iv) requirement as a 4-hour notification and reported as a follow-up |
| LER notification per 10CFR50.73(a). The current applicable reporting |
| criteria do not require immediate notification, however an LER or verbal |
| notification is required per 10CFR50.73(a). Accordingly, this report is |
| provided as a verbal notification per 10CFR50.73(a), Reportable events, |
| which states, in part, in the case of an invalid actuation reported under |
| 50.73(a)(2)(iv), the licensee may, at its option, provide a telephone |
| notification to the NRC Operation Center within 60 days after the discovery |
| of the event instead of submitting a written LER. This actuation was |
| invalid, as described further below. |
| |
| "On October 14, 2000, the plant was in mode 3 in preparation for refueling |
| outage 10, when an inadvertent actuation of emergency feedwater components |
| occurred. This event occurred during the performance of procedure |
| OP-904-017, Anticipated Transient System Check. While performing section |
| 7.2, Testing of Diverse Emergency Feedwater System (DEFAS), step 7.2.12 (to |
| replace the Diverse Emergency Feedwater Actuation System selector switch to |
| disable) was inadvertently missed. This caused the emergency feedwater |
| components to move to their safety positions when the DEFAS test switch was |
| restored to its normal position. The two motor driven emergency feedwater |
| pumps and the steam driven emergency feedwater pump started. The emergency |
| feedwater isolation valves opened, but the emergency feedwater control |
| valves did not open, as per design, due to adequate steam generator water |
| levels. Accordingly, this event did not result in emergency feedwater flow |
| or emergency feedwater injection into the steam generators. The operator |
| immediately secured the EFW pumps and closed the EFW isolation valves. |
| |
| "NUREG 1022, revision 2, Event Reporting Guidelines 10CFR50.72 and 50.73 |
| provides guidance for determining if an actuation is invalid. The NUREG |
| states, in part, that invalid actuations include actuations that are not the |
| result of valid signals and are not intentional manual actuations. Valid |
| signals are those signals that are initiated in response to actual plant |
| conditions or parameters satisfying the requirements for initiation of the |
| safety function of the system. This report documents an actuation that was |
| not the result of a valid signal and was not an intentional manual |
| actuation, For these reasons, this event constitutes an invalid actuation." |
| |
| The NRC resident inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39300 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 10/17/2002|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 18:55[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/17/2002|
+------------------------------------------------+EVENT TIME: 14:30[CDT]|
| NRC NOTIFIED BY: BRIAN HUPKE |LAST UPDATE DATE: 10/17/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS KOZAK R3 |
|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 94 Power Operation |94 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI INOPERABLE DUE TO LOW INTERNAL BATTERY RESISTANCE |
| |
| The licensee reported that during a 250 Vdc battery surveillance the |
| internal resistance of cell #18 was greater than the technical specification |
| (TS) limit. As a result, the licensee declared battery bank 1D4 inoperable |
| which also rendered inoperable the HPCI system and any containment isolation |
| valves powered from the battery bank. This included 5 total CIVs from the |
| following systems: HPCI, RWCU and MSL drain and Torus drain valves. |
| Corrective maintenance was performed on the battery cell and the internal |
| resistance passed the TS limit. HPCI and CIVs were returned to an operable |
| status approximately 3 hours after being declared inoperable. At the time |
| of this event, the RCIC system was inoperable for planned maintenance so the |
| LCO entered for HPCI was more restrictive allowing 12 hours rather than the |
| normal 14 day LCO for HPCI. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 39301 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/17/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:30[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/17/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:40[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/17/2002|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |THOMAS KOZAK R3 |
| DOCKET: 0707001 |M. WAYNE HODGES NMSS |
+------------------------------------------------+NADER MAMISH IRO |
| NRC NOTIFIED BY: K. A. BEASLEY | |
| HQ OPS OFFICER: ARLON COSTA | |
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|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
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EVENT TEXT
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| 24-HOUR 91-01 BULLETIN RESPONSE NOTIFICATION |
| |
| At 1708 on 10-17-02, the Plant Shift Superintendent (PSS) was notified that |
| potentially fissile (PF) waste had been discovered improperly stored at the |
| Wet Air Pump station in the C-333 building. A pile of used absorbent pads |
| was found in the floor at the West Air station. The absorbent pads are used |
| to soak up oil that has leaked from the pumps. These pads should have been |
| placed in an AQ-NCS approved 5.5 gallon drum and controlled as PF waste as |
| they were picked up. This is a violation of the requirements of NCSA |
| GEN-15. |
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| The NRC Resident inspector has been notified of this event. |
| |
| SAFETY SIGNIFICANCE OF EVENTS: The used absorbent pads were accumulated |
| incorrectly; however the uranium concentration for heterogeneous waste is |
| low and a large quantity of heterogeneous fissile material would be required |
| for a criticality to occur. |
| |
| PATHWAYS INVOLVED: In order for a criticality to be possible, the |
| interaction process condition would also have to be violated. However, the |
| interaction control was maintained and therefore a criticality was not |
| possible. |
| |
| CONTROLLED PARAMETERS: The two process conditions relied upon for double |
| contingency for this scenario are interaction and geometry. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEMS(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: The first leg of double contingency is |
| based on a minimum 2 ft. edge-to-edge spacing requirement to ensure double |
| contingency for spacing violations involving waste drums end other items |
| containing fissile/potentially fissile material. This control was not |
| violated. |
| |
| The second leg of double contingency is based on geometry controls of the |
| waste when it is placed into an AQ-NCS approved waste drum and the secondary |
| containment pans used to store the drums. Since the waste was accumulated on |
| the floor and not into the NCS-approved container, this control was |
| violated. The process condition was not maintained and double contingency |
| was not maintained |
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| Since the used absorbent pads were not generated into an AQ-NCS approved |
| waste container, the process condition for waste accumulation was not |
| maintained. Therefore, double contingency was not maintained. |
| |
| CORRECTIVE ACTIONS: A buffer area has been established to control movement |
| of fissile material within the area. A remediation guide will be prepared by |
| NCS prior to removal of the used absorbent pads. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021