Event Notification Report for March 1, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/29/2000 - 03/01/2000
** EVENT NUMBERS **
36737 36738
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36737 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/28/2000|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 23:29[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/28/2000|
+------------------------------------------------+EVENT TIME: 23:09[EST]|
| NRC NOTIFIED BY: STEVEN BAKER |LAST UPDATE DATE: 02/29/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |97 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN - BACKLEAKAGE FROM THE S/G TO THE AUXILIARY |
| FEEDWATER SYSTEM. |
| |
| Check valve leakage from the # 1 Steam Generator caused a rise in |
| temperature in the discharge piping of the "A" auxiliary feedwater pump. |
| The maximum allowed temperature is 190 degrees F. The maximum temperature |
| reached was 300 degrees F. The licensee entered Tech Spec 3.0.3 at 1209 and |
| started slowly lowering power. Injection with the "A" AFW pump reduced |
| the temperature in the line below the limit. The licensee is waiting to |
| determine if the check valve has reseated. |
| |
| The licensee notified the NRC resident inspector, the town of Waterford and |
| the state of Connecticut. |
| |
| * * * UPDATE 0026 2/29/2000 FROM JOHN CLAIR TAKEN BY BOB STRANSKY * * * |
| |
| TS 3.0.3 was exited at 2338 2/28/2000. The unit is returning to rated power. |
| The NRC resident inspector will be informed of this update by the licensee. |
| Notified R1DO (Trapp). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36738 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 02/29/2000|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 08:28[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/29/2000|
+------------------------------------------------+EVENT TIME: 08:03[EST]|
| NRC NOTIFIED BY: JIM CROSSMAN |LAST UPDATE DATE: 02/29/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES OGLE R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 72 Power Operation |72 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO THE FEDERAL ENERGY REGULATORY COMMISSION (FERC) |
| REGARDING FAILURE OF SPILLWAY EMERGENCY DIESEL GENERATOR TO START DURING |
| TESTING |
| |
| "THE NORTH ANNA SPILLWAY DIESEL FAILED TO START DURING THE PERFORMANCE OF |
| THE PERIODIC SURVEILLANCE (1-PT-1). THIS EVENT IS REPORTABLE TO THE FERC |
| REGIONAL ENGINEER, THEREFORE, THE NRC MUST BE NOTIFIED WITHIN 4 HOURS. |
| MAINTENANCE IS INVESTIGATING. THE SPILLWAY HAS NORMAL POWER AVAILABLE. |
| THIS IS THE EMERGENCY DIESEL GENERATOR AT THE DAM AND IS A SAFETY DEVICE PER |
| FERC REGULATIONS." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021