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. |
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