United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2000

Event Notification Report for March 3, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/02/2000 - 03/03/2000

                              ** EVENT NUMBERS **

36736  36741  36748  36749  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36736       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 02/28/2000|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 18:24[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        02/28/2000|
+------------------------------------------------+EVENT TIME:        14:15[CST]|
| NRC NOTIFIED BY:  MIKE BENSEN                  |LAST UPDATE DATE:  03/02/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY INOPERABLE                                          |
|                                                                              |
| High Pressure Core Spray was declared INOPERABLE following an overvoltage    |
| condition on the Division Three AC Power Distribution System.                |
|                                                                              |
| During performance of CPS 9080.02 Division Three Diesel Generator            |
| Operability Surveillance, the Division Three Diesel Generator was            |
| synchronized with the AC bus.  Following synchronization, bus voltage went   |
| to                                                                           |
| approximately 4360V, which is above the limit of 4300V.  The high voltage    |
| condition remained for approximately                                         |
| 3 1/2 minutes, until the Diesel Generator output breaker was opened and      |
| voltages returned to less than 4300V.                                        |
|                                                                              |
| The Division Three AC Power Distribution System was declared INOPERABLE due  |
| to being above 4300V pending an Engineering evaluation of the overvoltage    |
| condition.  CPS Improved Technical Specification 3.8.9, Action E.1 requires  |
| High Pressure Core Spray to be declared INOPERABLE with the Division Three   |
| AC Power Distribution System INOPERABLE.                                     |
|                                                                              |
| The Division Three Diesel Generator was also declared INOPERABLE.            |
|                                                                              |
| The cause of the overvoltage is not known and is being investigated at this  |
| time.                                                                        |
|                                                                              |
| NRC Resident Inspector C. Brown was notified.                                |
|                                                                              |
|                                                                              |
| * * * UPDATE ON 3/2/00 @ 1441 BY FUNCKHOUSER TO GOULD * * *                  |
|                                                                              |
| All portions of the Division Three AC Distribution System were initially     |
| declared INOPERABLE.  The Division Three AC Distribution System has had an   |
| Engineering Evaluation performed and restored to an OPERABLE status.   At    |
| this time the High Pressure Core Spray (HPCS) System was restored to an      |
| OPERABLE status.  The Division Three Diesel Generator is being worked to     |
| restore it to an OPERABLE status, subsequent to the abnormal conditions      |
| experienced during the Division 3 Diesel Generator run on Monday, February   |
| 28, 2000.                                                                    |
|                                                                              |
| The plants Technical Specifications Limited Condition for Operation (LCO)    |
| section 3.8.1, AC Sources Operating, does not require the Division 3 AC      |
| electrical power sources to be OPERABLE when the HPCS System is inoperable   |
| and it allows the use of the HPCS LCO in lieu of the Division 3 Diesel       |
| Generator.  Thus, the High Pressure Core Spray (HPCS) System has been        |
| declared INOPERABLE at approximately 1000 on March 2, 2000 in lieu of the    |
| Division 3 AC Source (Division 3 DG). This is allowed by the LCO 3.8.1       |
| Bases, Applicability section. The HPCS System LCO is covered in Technical    |
| Specifications section 3.5.1.                                                |
|                                                                              |
| At 1000 on 3/2/00 the plant exited LCO 3.8.1 and entered LCO 3.5.1.          |
|                                                                              |
| The NRC Resident Inspector was informed.                                     |
|                                                                              |
| The Reg 3 RDO(Jordan) was notified.                                          |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|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:  03/02/2000|
|  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.                                                        |
|                                                                              |
| * * * UPDATE AT 1040 ON 03/02/00 FROM TIM MOHS TO JOLLIFFE * * *             |
|                                                                              |
| The results of the bioassays indicated that no dose was received by either   |
| individual.  No personnel were contaminated.  Radiation levels inside the    |
| van were less than release limits.  Thus, the licensee desires to retract    |
| this event.                                                                  |
|                                                                              |
| The NRC Operations Officer notified the R3DO Mike Jordan and NMSS EO Brian   |
| Smith.                                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36748       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 03/02/2000|
|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 18:18[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/02/2000|
+------------------------------------------------+EVENT TIME:        18:00[EST]|
| NRC NOTIFIED BY:  HUSSEY                       |LAST UPDATE DATE:  03/02/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE DISCOVERED NON-CONSERVATISM IN CRITICALITY CALCULATIONS FOR     |
| FUEL POOL STORAGE REQUIREMENTS.                                              |
|                                                                              |
| It was determined that certain assumptions may result in a K-effective       |
| (K-eff) in excess of 0.95 at 0 ppm boron concentration in the spent fuel     |
| pool.  The Design Basis of the plant is that the fuel stored in the fuel     |
| pool will remain less than or equal to 0.95 K-eff when fully flooded with    |
| unborated water.  As such the Licensee is reporting this as a condition      |
| outside the design basis of the plant in accordance with                     |
| 10CFR50.72(b)(1)(ii)(B).                                                     |
|                                                                              |
| Currently each spent fuel pool has boron concentrations in excess of 2675    |
| ppm as required by Technical Specifications.  Under these conditions, with   |
| routine monitoring of boron concentration as required by Technical           |
| Specifications, the plant will not require any compensatory measures to      |
| remain operable in the fuel pool.  Duke will continue to evaluate the models |
| to further evaluate this condition.                                          |
|                                                                              |
| The NRC Resident Inspector was informed.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36749       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 03/02/2000|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 19:25[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/02/2000|
+------------------------------------------------+EVENT TIME:        16:30[CST]|
| NRC NOTIFIED BY:  MORRIS                       |LAST UPDATE DATE:  03/02/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         R4      |
|10 CFR SECTION:                                 |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LICENSEE DID NOT COMPLY WITH LCO ACTION STATEMENTS                           |
|                                                                              |
| On March 1, 2000 at 1008 hours, 125 VDC Battery System E1A11 was declared    |
| inoperable.  Subsequently, in accordance with Technical Specifications       |
| 3.8.2.2, "D. C. Sources," and 3.8.3.2, "Onsite Power Distribution -          |
| Shutdown," Nuclear Instrumentation Source Range Detector 31 should have been |
| declared inoperable or actions should have been initiated to suspend         |
| operations involving positive reactivity changes.  Contrary to these         |
| requirements, Source Range Detector 31 was not declared inoperable, and at   |
| 0027 hours on March 2, 2000, control rods were moved as part of rapid        |
| refueling rod holdout operations.  The rods were cycled 18 steps 3 times     |
| between the hours 0027 and 0400 @ 3/2/00.  No movements have taken place     |
| since then.  Detector 31 has been declared inoperable and is still           |
| inoperable.                                                                  |
|                                                                              |
| The NRC Resident Inspector has been notified.                                |
|                                                                              |
| This notification is being made pursuant to Operating License NPF-76         |
| Condition 2.G for operation or condition prohibited by Technical             |
| Specifications.                                                              |
+------------------------------------------------------------------------------+