United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2001

Event Notification Report for March 20, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/19/2001 - 03/20/2001

                              ** EVENT NUMBERS **

37848  37849  37850  37851  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37848       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/19/2001|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 10:44[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/19/2001|
+------------------------------------------------+EVENT TIME:        08:00[EST]|
| NRC NOTIFIED BY:  ROBINSON                     |LAST UPDATE DATE:  03/19/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KENNETH JENISON      R1      |
|10 CFR SECTION:                                 |                             |
|*DEG 50.72(b)(3)(ii)(A)  DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECONDARY CONTAINMENT BYPASS LEAKAGE RATE WAS EXCEEDED.                      |
|                                                                              |
| "With Unit 2 in Mode 5 on the 10th day of its 10th Refuel and Inspection     |
| Outage, it has been determined that the Secondary Containment Bypass Leakage |
| (SCBL) rate criteria of 9 scfh has been exceeded.   During performance of    |
| Local Leak Rate Test SE-259-045, a leakage rate of 3,838 sccm was recorded   |
| for the Division 2 RHR Drywell Spray Containment Isolation Valve HV251F016B. |
| With this leak rate, the Min Path SCBL leak rate was calculated to be 4,312  |
| sccm (or 9.14 scfh).  This leak rate exceeds the Technical Specification     |
| 3.6.1.3 criteria of 9 scfh for SCBL.  They will rework the valve and         |
| retest."                                                                     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37849       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 03/19/2001|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 11:10[EST]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        03/19/2001|
+------------------------------------------------+EVENT TIME:        10:30[EST]|
| NRC NOTIFIED BY:  TODD YOUNG                   |LAST UPDATE DATE:  03/19/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY. IMMEDIATE COMPENSATORY MEASURES   |
| TAKEN UPON DISCOVERY. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37850       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 03/19/2001|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 14:22[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        03/19/2001|
+------------------------------------------------+EVENT TIME:        12:32[EST]|
| NRC NOTIFIED BY:  JAMES KRITZER                |LAST UPDATE DATE:  03/19/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KENNETH JENISON      R1      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|*ESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM                                                                |
|                                                                              |
| On 3/19/2001, at 1232 a reactor scram signal was received, all rods inserted |
| after the scram.  Reactor Pressure Vessel  (RPV) water level dropped below   |
| 127" (normal water level is about 160") which actuated primary containment   |
| isolation signals for groups 2, 3 and 5.  RPV water level is being           |
| controlled by feedwater and RPV pressure control is via turbine bypass       |
| valves.  The plant is stable.  The cause of the reactor scram is under       |
| investigation.                                                               |
|                                                                              |
| The licensee notified the NRC resident inspector and will notify the state   |
| authorities.  A press release may be issued.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37851       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 03/19/2001|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 18:02[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/19/2001|
+------------------------------------------------+EVENT TIME:        10:57[CST]|
| NRC NOTIFIED BY:  JOHN CONLY                   |LAST UPDATE DATE:  03/19/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|*DEG 50.72(b)(3)(ii)(A)  DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| GREATER THAN 1% OF STEAM GENERATOR TUBES DEFECTIVE                           |
|                                                                              |
| "During refueling outage 2RE08, the results of steam generator tube          |
| inspections in steam generator 2C were classified as category C-3 in         |
| accordance with Technical Specification 4.4.5.2.d) in that 48 tubes out of   |
| 4,615 (i.e.,> 1%) have been found to be defective.   All defective steam     |
| generator tubes will be plugged before the steam generators are returned to  |
| service.  There were not any adverse safety consequences or implications as  |
| a result of this event.  This event did not adversely affect the safe        |
| operation of the plant or the health and safety of the public.  The cause of |
| the imperfections is outside diameter stress corrosion cracking."            |
|                                                                              |
| South Texas Project conducted a steam generator tube inspection results      |
| conference call with Region IV, the Senior Resident Inspector, and Nuclear   |
| Reactor Regulation this afternoon.   The occurrence of the C-3 condition was |
| noted during the call.                                                       |
+------------------------------------------------------------------------------+