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Event Notification Report for December 28, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/27/2000 - 12/28/2000

                              ** EVENT NUMBERS **

37559  37634  37635  37636  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37559       |
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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 11/30/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 20:55[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/30/2000|
+------------------------------------------------+EVENT TIME:        17:00[EST]|
| NRC NOTIFIED BY:  STEVE SAUER                  |LAST UPDATE DATE:  12/27/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANIELLO DELLA GRECA  R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| SERVICE WATER ACCUMULATOR LEVEL HIGH OUT OF SPECIFICATION                    |
|                                                                              |
| At 1700 on 11/30/00, it was identified that the 11B service water            |
| accumulator level was higher than that allowed by technical specifications.  |
| This was identified following a level device calibration.  The service water |
| accumulators support containment integrity by ensuring the containment fan   |
| coils remain properly filled during a design basis accident.  Tech Spec      |
| 3.6.1.1 and 3.6.2.3 were entered for containment integrity and the           |
| inoperability of 11 and 12 containment fan coil units.  Actions were taken   |
| within the one hour time requirement to comply with the containment          |
| integrity LCO.  The service water accumulator was subsequently drained to    |
| within specification at 1742.  Tech Spec 3.6.11 was exited at this time.     |
| The 11 and 12 containment fan coils were restored to operable at 1745 and    |
| Tech Spec 3.6.2.3 was exited.  Actions are underway to calibrate the         |
| redundant instrumentation and to investigate the cause of the instrument     |
| drift.  All power plant parameters remained stable throughout this event and |
| no other safety systems were affected.                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * RETRACTION ON 12/27/00 AT 1053ET BY BASHORE TAKEN BY MACKINNON * * *   |
|                                                                              |
| A review of the actual service water accumulator parameters that existed     |
| when the 11 service water accumulator level was high out of specification    |
| was performed.  Based on the actual service water accumulator pressure,      |
| level and temperature and the service water inlet temperature that existed,  |
| engineering has determined that the 11 service water accumulator would have  |
| been able to perform its design basis function if called upon to do so       |
| during the time that the accumulator level was high out of specification.    |
|                                                                              |
| Since the 11 service water accumulator was capable of performing its design  |
| basis function, the above report is being retracted.   NRC R1DO (L.          |
| Doerflein) notified.                                                         |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37634       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 12/27/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 12:47[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        12/27/2000|
+------------------------------------------------+EVENT TIME:        10:31[EST]|
| NRC NOTIFIED BY:  RANDY HAISLET                |LAST UPDATE DATE:  12/27/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) DECLARED INOPERABLE             |
|                                                                              |
| The licensee was performing the procedure to reset the RCIC isolation, after |
| a surveillance was completed, when the closed inboard steam isolation valve  |
| (MO-1301-16) went to dual indication while opening the outboard steam        |
| isolation valve (MO-1301-17).  Both steam isolation valves to the RCIC       |
| turbine were closed and the RCIC system was declared inoperable.  The        |
| licensee is investigating the problem.                                       |
|                                                                              |
| Active limiting conditions for operation were entered for the RCIC system    |
| and the primary containment isolation function of the RCIC inboard steam     |
| isolation valve (MO-1301-16).                                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37635       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NC DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 12/27/2000|
|LICENSEE:  CHARLOTTE-MECKLENBURG HOSPITAL AUTHOR|NOTIFICATION TIME: 15:52[EST]|
|    CITY:  CHARLOTTE                REGION:  2  |EVENT DATE:        12/27/2000|
|  COUNTY:                            STATE:  NC |EVENT TIME:        14:20[EST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  12/27/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MARK LESSER          R2      |
|                                                |SUSAN SHANKMAN       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GEORGE ACCATTATO             |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DELIVERY VEHICLE WRECK WHILE CARRYING RADIOACTIVE MATERIAL, NO               |
| CONTAMINATION                                                                |
|                                                                              |
| On 12/22/00 a Courier Dispatch was involved in an accident while             |
| transporting a Mo-99 generator, incident number ICD-00-47.  The accident     |
| occurred in Monroe, NC at the intersection of highways 116 and 74, about a   |
| half mile from the delivery point, Union Regional Med Center Nuc Med.  The   |
| Radiation Safety Officer (RSO) went to the scene and made a determination of |
| no contamination on the driver, vehicle, or package outside.  The package,   |
| no apparent damage, was transferred to Union Regional Med Center Nuc Med.    |
| There was no other radioactive material in the transport.                    |
|                                                                              |
| The incident has been closed and a written report to the NRC will follow.    |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37636       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 12/27/2000|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 18:03[EST]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        12/27/2000|
+------------------------------------------------+EVENT TIME:        13:30[CST]|
| NRC NOTIFIED BY:  JEFFREY EASLEY               |LAST UPDATE DATE:  12/27/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE INJECTION (HPCI) SYSTEM DISCOVERED INOPERABLE             |
|                                                                              |
| "On 12/27/00 at 1330 hours QCOS 2300-09 (U-1 HPCI Vent Verification) was in  |
| progress following QCOS 2300-11 (CCST/Torus Level Switch Functional          |
| Testing). During the process of vent verification of the U-1 HPCI system,    |
| the vent valves were open approximately 6.5 minutes prior to receiving water |
| through the vent lines; the U-1 HPCI system was found inoperable.            |
| Performance acceptance criteria of QCOS 2300-09 states that venting times    |
| >40 seconds could he construed as a preconditioning action per NRC IN 97-16  |
| and as such the U-1 HPCI system possibly could not have performed its'       |
| safety function prior to the venting that took place on 12/27/00 at 1330.    |
| The last successful vent of the U-1 HPCI system was completed on 11/30/00.   |
| An investigation is underway to try to determine the time of the loss of     |
| fill and the cause. This 4-hour ENS notification is being made in accordance |
| with 10 CFR 50.72(b)(2)(iii)(D)."                                            |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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