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Event Notification Report for March 6, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/05/2001 - 03/06/2001

                              ** EVENT NUMBERS **

37806  37807  37808  37809  37810  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37806       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/05/2001|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 12:25[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/05/2001|
+------------------------------------------------+EVENT TIME:        10:13[EST]|
| NRC NOTIFIED BY:  BRUCE BUTLER                 |LAST UPDATE DATE:  03/05/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEPHEN CAHILL       R2      |
|10 CFR SECTION:                                 |                             |
|*INB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING (RCIC) TRIPPED UNEXPECTEDLY DURING TESTING.   |
|                                                                              |
| Received RCIC "B" logic isolation signal causing RCIC in-board isolation     |
| valve, 2E51-F007, to close resulting in RCIC trip signal.  I&C personnel     |
| were performing 57SV-CAL-003-25 ATTS transmitter calibration for RCIC "B"    |
| steam line differential pressure transmitter 2E51-N057B when the isolation   |
| occurred and this instrument caused the isolation.  Investigation is in      |
| progress to determine the cause.  Received isolation signal at 1013 ET, I&C  |
| backed out of the procedure returning 2E51-N057B transmitter to service and  |
| RCIC isolation was reset and RCIC returned to standby at 1105 ET.            |
|                                                                              |
| All other Emergency Core Cooling systems were fully operable during the time |
| period RCIC was declared inoperable.                                         |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   37807       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SAINT LUKES HOSPITAL                 |NOTIFICATION DATE: 03/05/2001|
|LICENSEE:  SAINT LUKES HOSPITAL                 |NOTIFICATION TIME: 15:13[EST]|
|    CITY:  KANSAS CITY              REGION:  3  |EVENT DATE:        02/23/2001|
|  COUNTY:                            STATE:  MO |EVENT TIME:        11:15[CST]|
|LICENSE#:  24-00889-01           AGREEMENT:  N  |LAST UPDATE DATE:  03/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN MADERA          R3      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SCOTT SORENSEN               |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POSSIBLE MEDICAL MISADMINISTRATION                                           |
|                                                                              |
| A remote afterloader device failed to function as it was intended during a   |
| random FDA trial.  The remote afterloader was in automatic, and it was       |
| supposed to insert an intervascular, brachytherapy, 93-mCi, P-32, wire       |
| source into a patient.  The remote afterloader device did not operate        |
| properly, and it inserted and withdrew the wire source 4 times.  No dwell    |
| time was recorded by the afterloader since the wire source inserted less     |
| than 5 seconds each time before the wire source was automatically withdrawn. |
| The patient was supposed to have received a total dose of 20 grays.  The     |
| patient received a dose much less than intended.  The FDA was notified of    |
| this event by the licensee.                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37808       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 03/05/2001|
|LICENSEE:  NON-DESTRUCTIVE INSPECTION, CORP.    |NOTIFICATION TIME: 17:45[EST]|
|    CITY:  CLUTE                    REGION:  4  |EVENT DATE:        02/27/2001|
|  COUNTY:  BRAZORIA                  STATE:  TX |EVENT TIME:        00:00[CST]|
|LICENSE#:  L02712                AGREEMENT:  Y  |LAST UPDATE DATE:  03/05/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |WILLIAM JOHNSON      R4      |
|                                                |JOSEPH HOLONICH      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HELEN WATKINS                |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FOUR RADIOGRAPHERS EXCEEDED ANNUAL EXPOSURE LIMIT.                           |
|                                                                              |
|                                                                              |
| After receiving a Radiation Dosimeter Report on 01/22/01 for wear date of    |
| 11/20/00 through 12/19/00, it was discovered the licensee had 4 individual   |
| personnel dosimeters exceeding the annual limits of 5 rem/yr.  Participants  |
| ID and reported doses are listed below:                                      |
|                                                                              |
| 1.  Participant 00089 ID # 466313013, 5553 mrem.                             |
| 2.  Participant 00190 ID # 452717589, 5661 mrem.                             |
| 3. Participant 00174 ID # 453959946, 4673 mrem plus as assessment of 417     |
| mrem for a lost dosimeter equal a sum of 5091 mrem.                          |
| 4. Participant 00255 ID # 222582111, 3995 mrem, plus previous employment     |
| assessment of 1065 mrem equal a sum of 5060 mrem.                            |
|                                                                              |
| After receiving and reviewing the dosimetry reports phone notification was   |
| made confirming the resulting exposures exceeding annual limits in           |
| accordance with 25 TAC requirements.  At this time the licensee is awaiting  |
| the final dosimetry reports for 2000 year to date.  Upon receipt of the      |
| final dosimetry reports the licensee will set up an investigation date and   |
| time.                                                                        |
|                                                                              |
| Texas Department of Health is investigating to obtain additional             |
| information.                                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37809       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 03/05/2001|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 17:56[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        03/05/2001|
+------------------------------------------------+EVENT TIME:        16:00[EST]|
| NRC NOTIFIED BY:  K BELDEN                     |LAST UPDATE DATE:  03/05/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD CONTE        R1      |
|10 CFR SECTION:                                 |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTROL ROOM EMERGENCY VENTILATION DECLARED INOPERABLE.                      |
|                                                                              |
| Control Room Emergency Ventilation was declared inoperable at 1600 hours.    |
| This was a result of the Lab carbon sample analysis not meeting Technical    |
| Specification 3.4.5.c of  greater than 90%  radioactive methyl iodine        |
| removal capability when tested.   This required entering into a 7 day        |
| shutdown Limiting Condition for Operation.  Carbon sample analysis is        |
| required per Technical Specification to be performed once per cycle (2       |
| years).  Licensee is in the process of replacing the carbon.                 |
|                                                                              |
| The NRC Resident Inspector was notified of this event.                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37810       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 03/06/2001|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 00:24[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/05/2001|
+------------------------------------------------+EVENT TIME:        23:24[EST]|
| NRC NOTIFIED BY:  JIM CROWLEY                  |LAST UPDATE DATE:  03/06/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |RICHARD CONTE        R1      |
|10 CFR SECTION:                                 |BILL BATEMAN         NRR     |
|*AEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |CHARLES MILLER       IRO     |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|CHARLIE BAGWELL      FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCRETIONARY UNUSUAL EVENT DECLARED DUE TO A MOMENTARY LOSS OF OFFSITE      |
| POWER DURING AN ONGOING SEVERE WINTER STORM AND SUBSEQUENT AUTOMATIC REACTOR |
| TRIP DUE TO GRID INSTABILITY                                                 |
|                                                                              |
| During an ongoing severe winter storm, the 345-kV breakers tripped open and  |
| re-closed resulting in a momentary loss of offsite power.  An automatic      |
| reactor trip also occurred at 2324 on 03/05/01 due to electrical grid        |
| instability.  (The exact cause of the reactor trip is currently under        |
| investigation because there was no first out indication.)  All rods fully    |
| inserted.  The reactor coolant pumps tripped as expected, and one has been   |
| placed back in service.  Both emergency diesel generators automatically      |
| started but did not load.  Availability of the condenser was also lost due   |
| to the loss of power, and operators closed the main steam isolation valves.  |
| There were no radiation releases, and there were no reactor coolant system   |
| or steam generator tube leaks.  All systems functioned as required with one  |
| exception.  The steam-driven emergency feedwater pump failed to              |
| automatically actuate.                                                       |
|                                                                              |
| At this time, the unit is in Mode 3.  Normal charging and letdown,           |
| pressurizer heaters and sprays, and one reactor coolant pump are being       |
| utilized for primary system level, pressure, and transport control.  Water   |
| is being supplied to the steam generators via an electric-driven emergency   |
| feedwater pump, and the atmospheric dumps are being utilized as the heat     |
| sink.  Containment parameters are normal.  The grid is currently available   |
| for offsite power, and the emergency diesel generators are still running.    |
|                                                                              |
| Based on a discretionary shift management call, the licensee declared an     |
| Unusual Event at 2336 on 03/05/01.  The licensee stated that a               |
| "Discretionary Event" under item 18A refers to an event in progress (or has  |
| occurred) that indicates a potential degradation of the level of safety of   |
| the station.  The licensee plans to notify the NRC when the Unusual Event    |
| has terminated or if conditions degrade.                                     |
|                                                                              |
| A severe winter storm is currently ongoing.  At the time of the event, the   |
| unit was experiencing winds at a rate of  approximately 50 miles per hour.   |
| The licensee reported that these strong winds were ongoing and that only a   |
| few inches of snow had fallen (although up to 2 feet is expected).           |
|                                                                              |
| The licensee notified the state at 2347 on 03/05/01 and plans to notify the  |
| NRC resident inspector as well as applicable local officials.  The licensee  |
| also plans to issue a press release.                                         |
|                                                                              |
| ***** UPDATE AT 0222 ON 03/06/01 FROM JIM HILL TO LEIGH TROCINE *****        |
|                                                                              |
| This update provides both clarifications/corrections to the original event   |
| notification and additional information regarding licensee plans.            |
|                                                                              |
| CLARIFICATIONS/CORRECTIONS:  Prior to the event, two of three offsite power  |
| lines had been lost in close succession.  The remaining offsite line was     |
| subsequently lost, and its breaker re-closed within a short duration.  This  |
| resulted in the momentary loss of offsite power and subsequent plant         |
| transient.  This initial electrical imbalance was sufficient to result in    |
| the automatic starting and loading of both emergency diesel generators.      |
|                                                                              |
| CURRENT STATUS:  The unit remains in the Unusual Event, and winds are        |
| currently sustained at a rate of approximately 40 miles per hour.  All three |
| offsite power lines have been restored.  Both emergency diesel generators    |
| remain in operation and continue to provide power to both vital (emergency)  |
| buses.  The non-vital buses have been re-energized from offsite power.  An   |
| additional auxiliary pump (the startup feedwater pump) has also been started |
| to provide additional water to the steam generators.  This pump is a         |
| non-safety related housekeeping pump.                                        |
|                                                                              |
| PLANS:  Within the next half hour, the licensee plans to commence a          |
| discretionary plant cooldown and plans to place the unit in Mode 5 (Cold     |
| Shutdown).  At some point in time, the licensee also plans to secure the     |
| electric-driven emergency feedwater pump and rely on the startup feedwater   |
| pump to supply water to the steam generators.                                |
|                                                                              |
| The licensee notified the NRC resident inspector and an onsite member of an  |
| NRC residual heat removal inspection team.  The NRC operations officer       |
| notified the R1DO (Conte), NRR EO (Bateman), and IRO (Miller).               |
|                                                                              |
| ***** UPDATE AT 0438 ON 03/06/01 FROM JIM HILL TO LEIGH TROCINE *****        |
|                                                                              |
| The licensee has commenced a plant cooldown and anticipates that it will     |
| take approximately 6 hours for the unit to reach Cold Shutdown.  Other than  |
| commencement of the cooldown, there has been no change in plant conditions   |
| or equipment status.                                                         |
|                                                                              |
| The licensee stated that the criteria for exiting the Unusual Event have     |
| been met.  However, the licensee currently plans to remain in the Unusual    |
| Event for a while longer because the high line insulators onsite are still   |
| arcing and are suspect and because the in-house vital buses are still being  |
| powered by the emergency diesel generators.                                  |
|                                                                              |
| The licensee notified an onsite member of an NRC residual heat removal       |
| inspection team, who in turn notified the NRC resident inspector.  The NRC   |
| operations officer notified the R1DO (Conte), NRR EO (Bateman), and IRO      |
| (Miller).                                                                    |
+------------------------------------------------------------------------------+


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