Event Notification Report for March 2, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/01/2000 - 03/02/2000
** EVENT NUMBERS **
36657 36739 36740 36741 36742 36743 36744 36745 36746 36747
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36657 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 02/03/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 16:08[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 02/03/2000|
+------------------------------------------------+EVENT TIME: 11:14[CST]|
| NRC NOTIFIED BY: VERN CARLSON |LAST UPDATE DATE: 03/01/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLAUDE JOHNSON R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| BOTH TRAINS OF POST ACCIDENT H2 ANALYZERS DECLARED ADMINISTRATIVELY |
| INOPERABLE. |
| |
| During an ongoing review of calculations for "Normal and Accident Gamma and |
| Beta Doses for Mechanical Equipment Qualifications" it was discovered that |
| an inaccurate assumption was made concerning the operation of the |
| Containment and Drywell post accident hydrogen monitoring system. This |
| inaccurate assumption could lead to the sample isolation valves receiving |
| more radiation exposure than assumed in the calculations curing a design |
| bases accident. This extra radiation exposure could cause deterioration of |
| the valve seats and prevent them from sealing properly. With the valves |
| leaking the indicated hydrogen concentrations could be non-conservatively |
| low leading to improper actions during an accident. This condition affects |
| both safety trains of the post accident hydrogen analyzers. The actual |
| affect is still indeterminate however both trains have been conservatively |
| declared administratively inoperable. The system is still in a standby |
| lineup and is expected to continue to perform its function during the early |
| stages of an accident. Engineering is continuing to evaluate the actual |
| affect of the increased radiation exposure on the equipment. The NRC |
| Resident Inspector will be informed of this event by the licensee. |
| |
| * * * UPDATE AT 1713 ON 3/1/2000, BY FELTNER RECEIVED BY WEAVER * * * |
| |
| On 2/3/2000, (event notification 36657), River Bend Station reported that |
| the Containment and Drywell hydrogen monitor system had been conservatively |
| declared inoperable. The inoperability was based on the impact of an |
| inadequate assumption in a post accident dose calculation for the system |
| sample valves. This could have lead to more post accident radiation |
| exposure than determined in the original calculation, which may have lead to |
| failure of the sample valves to properly seat. At the time of the original |
| report. the actual affect of the condition on the valves was indeterminate |
| and the system was declared inoperable. Engineering re-evaluated the |
| condition as documented in a revision to calculation PR(c) 547. This |
| calculation found that the original assumption in the calculation did not |
| impact system operability. The calculation states that the potential doses |
| due to plateout in the system would be negligible when compared to the |
| airborne beta doses, and therefore the doses presented in the original |
| calculation conservatively represent dose expected following a design basis |
| accident. Based on this the system it was determined to be operable, and |
| the condition not reportable. The licensee notified the NRC resident |
| inspector. The NRC Operations Center notified the RDO (Cain). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36739 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 03/01/2000|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 06:27[EST]|
| RXTYPE: [2] GE-4 |EVENT DATE: 03/01/2000|
+------------------------------------------------+EVENT TIME: 05:30[EST]|
| NRC NOTIFIED BY: MIKE PHILIPPON |LAST UPDATE DATE: 03/01/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM CREED, IAT R3 |
|10 CFR SECTION: |MIKE JORDAN, DO R3 |
|DDDD 73.71 UNSPECIFIED PARAGRAPH |DICK ROSANO, IAT NRR |
| |CHRIS GRIMES, EO NRR |
| |MIKE WEBER, IAT NMSS |
| |BRIAN SMITH, EO NMSS |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - OVERDUE SHIPMENT OF NEW FUEL - |
| |
| The licensee reported that a shipment of new fuel from General Electric was |
| due to arrive onsite at 0500 on 03/01/00. The shipper (Kindrick Trucking |
| Company) was contacted and the shipment was located in Canton, Ohio, at 0550 |
| on 03/01/00. The new expected arrival time is 0900 on 03/01/00. The |
| licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 0955 ON 03/01/00 BY PAT FALLON TO JOLLIFFE * * * |
| |
| General Electric notified the licensee that the reason for the delay was |
| that a tarp on the nuclear fuel truck blew off and is being recovered and |
| reinstalled on the truck. Estimated time of arrival onsite now is 1300 on |
| 03/01/00. The licensee plans to notify the NRC Resident Inspector. The NRC |
| Operations Officer notified R3 IAT Jim Creed, R3DO Mike Jordan, NRR IAT Dick |
| Rosano, NRR EO Chris Grimes, NMSS IAT Mike Weber, NMSS EO Brian Smith, and |
| IRO Frank Congel. |
| |
| * * * UPDATE AT 1254 ON 3/1/2000 BY COSEO TAKEN BY WEAVER * * * |
| |
| The licensee is retracting this event. |
| |
| "10 CFR 73.67(g)(3) states that each licensee, either shipper or receiver, |
| who arranges for the physical protection of special nuclear material of low |
| strategic significance while in transit or who takes delivery of such |
| material free on board (f.o.b.) the point at which it is delivered to a |
| carrier for transport shall: conduct immediately a trace investigation of |
| any shipment that is lost or unaccounted for after the estimated arrival |
| time and notify the NRC Operations Center within one hour after the |
| discovery of the loss of the shipment and within one hour after recovery of |
| or accounting for such lost shipment in accordance with the provisions of 10 |
| CFR 73.71. In accordance with a General Electric (GE) letter to Detroit |
| Edison, dated August 12, 1992, GE stated that they are responsible for |
| in-transit physical protection of fuel shipments from Wilmington to the |
| Fermi 2 site. Therefore, the notification to the NRC regarding lost or |
| unaccounted for special nuclear material of low strategic significance while |
| in transit should have been completed by GE. |
| |
| "However, further evaluation of the event revealed that communication |
| between GE and the truck driver regarding the trucks location and problem, |
| did occur. Therefore, the truck was never lost or unaccounted for by GE. The |
| delay in the estimated arrival time was apparently due to problems with the |
| truck during the transit. Based on the above information and the fact that |
| the shipment was never lost or unaccounted for, the reporting requirements |
| of 10 CFR 73.71 do not apply in this event. Therefore, Detroit Edison is |
| retracting the 1-hour notification." |
| |
| The licensee notified the NRC resident inspector and the Operations Center |
| notified the RDO (Jordan), EO (Smith), IRO (Congel). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36740 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FL BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 03/01/2000|
|LICENSEE: HALIFAX MEDICAL CENTER |NOTIFICATION TIME: 08:58[EST]|
| CITY: DAYTONA BEACH REGION: 2 |EVENT DATE: 01/31/2000|
| COUNTY: STATE: FL |EVENT TIME: 12:00[EST]|
|LICENSE#: FL-194-3 AGREEMENT: Y |LAST UPDATE DATE: 03/01/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LEN WERT R2 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CHARLIE ADAMS | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - MEDICAL MISADMINISTRATION EVENT IN AN AGREEMENT STATE - |
| |
| On 01/31/00, during the second of three applicator treatments of 3.43 curies |
| of Ir-192 at Halifax Medical Center, Daytona Beach, FL, the hospital |
| therapist switched the location numbers and the patient was treated at a |
| location of 898 mm instead of 989 mm. The result was that the majority of |
| the dose went to the wrong treatment site. The maximum dose received was |
| 1600 Rads. The doctor and the patient have been notified. No damage to the |
| patient is expected. The patient has since completed the full course of |
| treatments which were compensated for the error. A written report has been |
| filed with Florida. This incident is still under investigation by Florida. |
| Florida Incident Number FL00-018. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36741 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: US ARMY (ACALA) |NOTIFICATION DATE: 03/01/2000|
|LICENSEE: US ARMY (ACALA) |NOTIFICATION TIME: 10:36[EST]|
| CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 02/17/2000|
| COUNTY: STATE: IL |EVENT TIME: 12:00[CST]|
|LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 03/01/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MIKE JORDAN R3 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TIM MOHS | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|IBAD 30.50(b)(1)(ii) MATL >5X LOWEST LIMIT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - M1A1 COLLIMATOR WAS OVERPRESSURIZED AND RUPTURED - |
| |
| On 02/17/00, while the Third Army Corp Maintenance Unit from Fort |
| Wainwright, AK, was performing a purge for Fort Hood units during training |
| at Fort Irwin, CA, an M1A1 collimator containing 10 curies of tritium was |
| overpressurized and ruptured. The M1A1 collimator was double bagged but not |
| reported to the Fort Irwin Radiation Safety Officer. On 02/29/00, when the |
| military van containing the M1A1 collimator was being readied for shipment |
| back to Fort Wainwright, the broken M1A1 collimator was noted and surveyed. |
| The survey came back contaminated (as high as 255,000 dpm). The military |
| van is being held at Army/Marine Base, Yermo Annex, Barstow, CA, by Fort |
| Hood personnel. Results are pending. The two individuals who performed the |
| purge are being bioassayed. Results are pending. Further investigation of |
| what happened and surveys to determine contamination status are ongoing. |
| Army Incident #00-12. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36742 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ALLEGHENY GENERAL HOSPITAL |NOTIFICATION DATE: 03/01/2000|
|LICENSEE: ALLEGHENY GENERAL HOSPITAL |NOTIFICATION TIME: 11:38[EST]|
| CITY: PITTSBURGH REGION: 1 |EVENT DATE: 03/01/2000|
| COUNTY: ALLEGHENY STATE: PA |EVENT TIME: 10:30[EST]|
|LICENSE#: 37-0131704 AGREEMENT: N |LAST UPDATE DATE: 03/01/2000|
| DOCKET: 03033730 |+----------------------------+
| |PERSON ORGANIZATION |
| |JIM TRAPP R1 |
| |DON COOL NMSS |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: JOE OCH | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AMERICIUM-241 SEALED SOURCE DISCOVERED TO BE MISSING FROM ALLEGHENY GENERAL |
| HOSPITAL LOCATED IN PITTSBURGH, PENNSYLVANIA. |
| |
| At approximately 1030 on 03/01/00, representatives at Allegheny General |
| Hospital located in Pittsburgh, Pennsylvania, discovered that a |
| 14-millicurie, americium-241, sealed source was missing from a stationary |
| gamma camera. The licensee reported that the source was last seen at 1130 |
| on 02/29/00. |
| |
| The licensee stated that the source is a relatively low level source with |
| longevity which is used to mark images. It is about the size of a pencil |
| eraser, and it is typically glued into a holder on the gamma camera. |
| |
| The licensee currently believes that the source may have become dislodged |
| from the holder and that it may have fallen to the floor. If that occurred, |
| the source may have been placed in the trash when the room was cleaned the |
| on the evening of 02/29/00. The licensee's investigation is ongoing, and |
| surveys are underway. |
| |
| The licensee plans to notify the state inspector. (Call the NRC operations |
| officer for a licensee contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36743 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 03/01/2000|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 13:06[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 03/01/2000|
+------------------------------------------------+EVENT TIME: 12:15[EST]|
| NRC NOTIFIED BY: PHILIP ROSE |LAST UPDATE DATE: 03/01/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - NON CONSERVATIVE LIMITING CONDITION FOR OPERATION |
| |
| On March 1, 2000, at 1215 hours, resulting from evaluations performed in |
| response to the McGuire Station Notification (02/04/2000, event # 36659), |
| Virgil C. Summer Nuclear Station has determined that a condition outside of |
| design basis may have existed during past plant operation. |
| |
| The specific condition is a deficiency in the current Limiting Condition for |
| Operation for Engineered Safety Feature Actuation System (ESFAS) |
| instrumentation. For one inoperable channel (in the Emergency Feedwater |
| suction swap over on low suction pressure, RWST [Reactor Water Storage Tank] |
| swap over to RB [Reactor Building] Sump on low level, and/or Containment |
| Spray actuation on High-3 pressure) the Technical Specification (TS) action |
| is to place the channel in bypass with no Allowed Outage Time (AOT) limit. |
| These are energize to actuate functions. At this point the actuation logic |
| changes from 2 out of 4 to 2 out of 3. |
| |
| Because of the indefinite period of time that this condition is permitted to |
| remain in effect, this condition cannot be considered a single failure |
| during a design basis accident. During a design basis accident, a single |
| failure involving a loss of power to the opposite train instrumentation, |
| while one or more of these functions were in bypass, would prevent the |
| safety function from automatically occurring. Manual operator action is |
| specified in the station Emergency Operating Procedures. |
| |
| Currently all four channels for each of the above functions are OPERABLE. |
| Therefore, Summer is not operating with a single failure vulnerability at |
| this time. A preliminary PRA [Probability Risk Assessment] assessment shows |
| the change in Core Damage Frequency to be 2.4 E-8 for placing one channel |
| from each of these functions in bypass indefinitely. |
| |
| Administrative controls have been developed to limit the AOT for these |
| particular channels to be in bypass until such time as a TS change request |
| can be submitted and approved. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36744 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 03/01/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 13:20[EST]|
| RXTYPE: [1] GE-2 |EVENT DATE: 03/01/2000|
+------------------------------------------------+EVENT TIME: 10:58[EST]|
| NRC NOTIFIED BY: TRITRUSKI |LAST UPDATE DATE: 03/01/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 24 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR MANUALLY SCRAMMED DUE TO A LOSS OF 3 OF 5 RECIRCULATION PUMPS. |
| |
| STARTUP TRANSFORMER "A" WAS BEING USED TO FEED ELECTRICAL POWER TO 4.16 kV |
| NON- VITAL BUS "A" AND VITAL BUS "C". EARLIER IN THE DAY THE REACTOR HAD |
| BEEN TAKEN OFF LINE SO THAT AUXILIARY TRANSFORMER "M1A" COULD BE PLACED BACK |
| IN SERVICE. AUXILIARY TRANSFORMER "M1A" WAS REPAIRED OVER THE PAST FEW |
| WEEKS. WHEN AUXILIARY TRANSFORMER BREAKER "1A" WAS CLOSED TO TRANSFER |
| STATION ELECTRICAL LOADS FROM THE STARTUP TRANSFORMER TO THE "M1A" |
| AUXILIARY TRANSFORMER, STARTUP TRANSFORMER "A" BREAKER "S1A" OPENED AS |
| EXPECTED BUT "1A" BREAKER DID NOT CLOSE. THE FAILURE OF BREAKER "1A" TO |
| CLOSE RESULTED IN A LOSS OF ELECTRICAL POWER TO BOTH NON-VITAL BUS "A" AND |
| VITAL BUS "C". |
| |
| THE LOSS OF NON- VITAL BUS "A" CAUSED THREE OF FIVE REACTOR RECIRCULATION |
| PUMPS TO TRIP. THE OPERATORS MANUALLY SCRAMMED THE REACTOR IN ACCORDANCE |
| WITH PROCEDURES. ALL CONTROL RODS FULLY INSERTED INTO THE CORE. LOSS OF |
| ELECTRICAL POWER TO VITAL BUS "C" CAUSED A LOSS OF POWER TO 1/2 OF THE |
| REACTOR PROTECTION SYSTEM. THIS RESULTED IN VITAL BUS EMERGENCY DIESEL |
| GENERATOR #1 TO AUTOMATICALLY START AND LOAD ONTO THE BUS. THE MAIN STEAM |
| ISOLATION VALVES CLOSED WHEN REACTOR VESSEL PRESSURE DECREASED BELOW 850 |
| PSIG. |
| |
| AT THE PRESENT TIME THE ISOLATION CONDENSER IS BEING USED TO COOL THE |
| REACTOR VESSEL DOWN. WHEN REACTOR PRESSURE DROPS BELOW 100 PSIG THE MAIN |
| STEAM ISOLATION VALVES CAN BE REOPENED. OFFSITE POWER HAS BEEN RESTORED TO |
| NON- VITAL BUS "A" AND VITAL BUS "C" VIA STARTUP TRANSFORMER "A." EMERGENCY |
| DIESEL GENERATOR # 1 IS BEING PROPERLY SECURED. DURING THIS INCIDENT BOTH |
| NON-VITAL BUS "B" AND VITAL BUS "D" REMAINED IN SERVICE. |
| |
| THE LICENSEE IS INVESTIGATING WHY "1A" BREAKER DID NOT CLOSE. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVEN BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36745 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/01/2000|
| UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 13:56[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/01/2000|
+------------------------------------------------+EVENT TIME: 12:35[CST]|
| NRC NOTIFIED BY: LARRY MCLERRAN |LAST UPDATE DATE: 03/01/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION - USING THE AUXILIARY FEEDWATER PUMP TO FEED THE STEAM |
| GENERATORS VIA THE MAIN FEEDWATER SYSTEM IS UNANALYZED. |
| |
| ANO engineering has determined that using the Auxiliary Feedwater pump to |
| feed S/Gs via the Main Feedwater system is unanalyzed. The ability of the |
| Main Feedwater Block valves to shut and isolate the affected S/G on a Main |
| Steam Line Break has not been fully evaluated. Preliminary evaluation |
| indicates that the valves may not shut under worst case conditions (low |
| voltage supplied to the MOV and high D/P across the valves). This condition |
| is only applicable during low power operations with Auxiliary Feedwater |
| feeding via the Main Feedwater piping. |
| |
| Auxiliary Feedwater is not an Engineered Safety Feature at ANO Unit 2. The |
| plant has a separate Emergency Feedwater system which is not affected by |
| this problem. |
| |
| The licensee will notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36746 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: RESTON HOSPITAL CENTER |NOTIFICATION DATE: 03/01/2000|
|LICENSEE: RESTON HOSPITAL CENTER |NOTIFICATION TIME: 14:22[EST]|
| CITY: RESTON REGION: 2 |EVENT DATE: 02/28/2000|
| COUNTY: STATE: VA |EVENT TIME: 08:00[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 03/01/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LEN WERT R2 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DR. FRUMAN | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST I-125 SEED |
| |
| A 0.401 mCi I-125 seed was lost on 2/28/2000, at Reston Hospital Center in |
| Reston, VA. The technician working with the seed believes the seed was lost |
| in the hot lab while preparing the seeds for use. The hot lab was searched |
| but the seed could not be found. The technician frisked herself prior to |
| leaving the hot lab, so the licensee does not believe the seed is outside of |
| the lab. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36747 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/01/2000|
| UNIT: [] [2] [] STATE: AZ |NOTIFICATION TIME: 19:25[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/01/2000|
+------------------------------------------------+EVENT TIME: 07:49[MST]|
| NRC NOTIFIED BY: DAN LARKIN |LAST UPDATE DATE: 03/01/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY EVENT |
| |
| A LICENSED OPERATOR TESTED POSITIVE FOR ALCOHOL DURING A FOR CAUSE TEST. |
| THE OPERATOR'S PROTECTED AREA ACCESS HAS BEEN SUSPENDED. CONTACT THE |
| OPERATIONS CENTER FOR ADDITIONAL DETAILS. |
| |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021