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Event Notification Report for July 20, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/19/2000 - 07/20/2000

                              ** EVENT NUMBERS **

37107  37158  37178  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37107       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 06/22/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 18:07[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        06/22/2000|
+------------------------------------------------+EVENT TIME:        14:07[CDT]|
| NRC NOTIFIED BY:  BORING                       |LAST UPDATE DATE:  07/19/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT ENTERED A 14 DAY LCO ACTION STATEMENT DUE TO HIGH PRESSURE COOLANT |
| INJECTION (HPCI) SYSTEM BEING DECLARED INOPERABLE.                           |
|                                                                              |
| During routine surveillance testing of the Containment Cooling Water System  |
| (CCWS), required system flow through the HPCI Room Cooler could not be       |
| obtained due to leakage past 2-3999-252 check valve.                         |
|                                                                              |
| With the HPCI Room Cooler inoperable, the HPCI System was declared           |
| INOPERABLE, a 14 day LCO Action Statement was entered, and an action request |
| for repair of the 2-3999-252 valve was submitted.                            |
|                                                                              |
| The NRC Resident Inspector was notified by the licensee.                     |
|                                                                              |
| * * * UPDATE AT 1917 ON 07/19/00 BY MARK RUNION TO JOLLIFFE * * *            |
|                                                                              |
| Upon further review of this event by Dresden Operations and Engineering      |
| Department personnel, the licensee determined that with the HPCI Room Cooler |
| blower available, even without CCWS flow to the HPCI Room Cooler, the HPCI   |
| System will perform its required function and remain operable.  Thus, the    |
| HPCI System was not inoperable at the time of the notification of this event |
| and therefore, this event is not reportable to the NRC.  Based on this, the  |
| licensee desires to retract this event.                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The NRC Operations        |
| Officer notified the R3DO Mike Parker.                                       |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37158       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 07/10/2000|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 17:28[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        07/10/2000|
+------------------------------------------------+EVENT TIME:        10:38[EDT]|
| NRC NOTIFIED BY:  JAMES RUSSELL                |LAST UPDATE DATE:  07/19/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEORGE BELISLE       R2      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|4     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY REPORT                                                      |
|                                                                              |
| A licensed training supervisor tested positive for alcohol use during a      |
| random drug and alcohol test. The individual's access has been suspended and |
| the licensee will review the individual's work for the past 90 days. The NRC |
| resident inspector has been informed of this event by the licensee.          |
|                                                                              |
| * * * RETRACTION ON 07/19/00 AT 1122 ET BY STEWART TAKEN BY MACKINNON * * *  |
|                                                                              |
| After discussions with NRC Region 2 it was determined that the above         |
| reported event did not have to be reported and is being withdrawn.  The      |
| individual was not a supervisor at the time of the event.  This report will  |
| be reported on the licensee's Semi - Annual Fitness for Duty Report. NRC     |
| R2DO (Bonser) notified.                                                      |
|                                                                              |
| The NRC Resident Inspector was notified of this update by the licensee.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37178       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 07/20/2000|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 04:28[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        07/20/2000|
+------------------------------------------------+EVENT TIME:        03:52[EDT]|
| NRC NOTIFIED BY:  TESORIERO                    |LAST UPDATE DATE:  07/20/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GREGORY CRANSTON     R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT OUTSIDE OF DESIGN BASIS                                                 |
|                                                                              |
| "On July 20, 2000 at 0352 hours a Reactor Coolant system leakrate of 0.30    |
| gpm was calculated. Currently the Charging and Letdown systems are isolated  |
| for maintenance. Investigation revealed the leakage being from the Excess    |
| Letdown system to the systems isolated for maintenance, which are located    |
| outside Containment. This leakrate exceeds the limit of 0.68 gph outside     |
| Containment and therefore is a condition outside the design basis of the     |
| plant. The Control Room Ventilation system is inoperable and a 72 hour       |
| limiting condition of operation has been entered."                           |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
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