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Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for October 17, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/16/2000 - 10/17/2000

                              ** EVENT NUMBERS **

37432  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37432       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 10/16/2000|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 12:43[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/16/2000|
+------------------------------------------------+EVENT TIME:        09:21[CDT]|
| NRC NOTIFIED BY:  JIM SCHOTTEL                 |LAST UPDATE DATE:  10/16/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL SCRAM INSERTED PRIOR TO REACHING AUTOMATIC SCRAM SETPOINT FOLLOWING   |
| REPLACEMENT OF ATWS POWER SUPPLIES                                           |
|                                                                              |
| "Clinton Power Station is currently in day 3 of refueling outage RF-7.  At   |
| 09:20 I&C Technicians were performing PMs (PCIMSA017 and PCIMSA019) which    |
| replaced power supplies in the Anticipated Transient Without Scram system    |
| (ATWS).  During reenergization of the ATWS system, the ARI (Alternate Rod    |
| Insertion) initiation alarm occurred. The 'A' RO observed Scram Discharge    |
| Volume Vents and Drains closing and a rising level in the Scram Discharge    |
| Volume (SDV).  At 09:21 a manual scram was inserted at approximately 11      |
| gallons SDV level prior to reaching the automatic scram setpoint of 19.6     |
| gallons Scram Discharge Volume level.                                        |
|                                                                              |
| "Prior to this event Reactor Water Level was at 195 inches. The extra input  |
| of water into the reactor due to this scram caused a level rise to 200       |
| inches. The Reactor Operators raised Reactor Water Cleanup letdown rate from |
| the RPV to bring level back to the preferred range of 190 - 200 inches.      |
|                                                                              |
| "Investigation has revealed that reenergizing the ATWS instrumentation       |
| causes actuation of the ATWS trip system."                                   |
|                                                                              |
| There was no rod motion since all rods were fully inserted prior to the      |
| event.  The licensee informed the NRC resident inspector.                    |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Thursday, March 25, 2021

Page Last Reviewed/Updated Thursday, March 25, 2021