Event Notification Report for March 30, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/29/2000 - 03/30/2000

                              ** EVENT NUMBERS **

36843  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36843       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/29/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 02:38[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/29/2000|
+------------------------------------------------+EVENT TIME:        02:00[EST]|
| NRC NOTIFIED BY:  GRANT FERNSLER               |LAST UPDATE DATE:  03/29/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EXCESSIVE LEAKAGE THROUGH CONTROL ROD DRIVE CHECK VALVES                     |
|                                                                              |
| "During the Unit 1 Refuel and Inspection Outage, it has been determined that |
| the CRD check valves (CRD Seismic Island) exceeded the as-found minimum path |
| leakage limit of 508 ml/hr. This failure is a degraded condition found while |
| the plant is shutdown, and requires a 4 hour ENS notification under          |
| 10CFR50.72(b)(2)(i)."                                                        |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
+------------------------------------------------------------------------------+