United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 1999

Event Notification Report for June 9, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/08/1999 - 06/09/1999

                              ** EVENT NUMBERS **

35806  35807  35808  35809  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35806       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 06/08/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 14:54[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/08/1999|
+------------------------------------------------+EVENT TIME:        12:06[EDT]|
| NRC NOTIFIED BY:  R. M. PEAL                   |LAST UPDATE DATE:  06/08/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN CARUSO          R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM DUE TO MAIN TRANSFORMER LOCKOUT                                |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee.   |
|                                                                              |
| "On June 8, 1999, Susquehanna Unit 2 was operating at 100% power.  The unit  |
| experienced a unit primary lockout associated with [the] 'A'  main           |
| transformer resulting in a main turbine trip and a reactor scram on turbine  |
| control valve fast closure.  [All rods fully inserted.]  Reactor water level |
| dropped to approximately 0.4 inches on wide range instrumentation, [and]     |
| level was restored to 35 inches using feedwater.  Reactor pressure peaked at |
| approximately 1,114 psig which is higher than the reactor scram setpoint of  |
| 1,087 psig.  Two [safety relief valves] cycled once during the initial       |
| event, and [the] turbine bypass valves are now open controlling at [the]     |
| pressure setpoint.  There were no [emergency core cooling system]            |
| initiations or diesel generator starts.  There were no challenges to         |
| containment."                                                                |
|                                                                              |
| "This event is an unplanned actuation of an engineered safety feature and,   |
| therefore, requires a 4-hour ENS notification under 10 CFR                   |
| 50.72(b)(2)(ii)."                                                            |
|                                                                              |
| The licensee stated that the lockout was caused by a sudden pressure relay   |
| and that oil was initially spraying from the transformer.  The fire brigade  |
| responded and has since been secured.  A fire watch is currently in place.   |
| The licensee plans to place the unit in Cold Shutdown.                       |
|                                                                              |
| The licensee notified the NRC resident inspector and plans to issue a press  |
| release.                                                                     |
|                                                                              |
| ******************** UPDATE AT 1850 ON 06/08/99 FROM MIKE PEAL TO LEIGH      |
| TROCINE ********************                                                 |
|                                                                              |
| The licensee notified the Pennsylvania Department of Environmental           |
| Protection of the oil spill from the 'A' main transformer.  The licensee     |
| stated that the state notification was not required and was made as a        |
| courtesy.  The transformer leaked for more than 1 hour, and the licensee     |
| drained the transformer from the bottom to stop the leak.  This oil was      |
| placed into the pit so that it was contained.  The quantity of oil that      |
| sprayed from the transformer and landed on the ground outside the            |
| transformer's berm was not known, but it covered only a small area.  None of |
| the oil entered the storm drains, and there was no run off.                  |
|                                                                              |
| The licensee notified the NRC resident inspector of this update.  The NRC    |
| operations officer notified the R1DO (Caruso).                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35807       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 06/08/1999|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 15:39[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        09/10/1998|
+------------------------------------------------+EVENT TIME:        15:44[CDT]|
| NRC NOTIFIED BY:  ERICK MATZKE                 |LAST UPDATE DATE:  06/08/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNPLANNED INITIATION OF THE VENTILATION ISOLATION ACTUATION SYSTEM (VIAS)    |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "A condition report on 09/10/98 documented the actuation of the VIAS         |
| circuitry due to the operation of the KEY switch on RM-062.  Due to the      |
| questioning attitude of system engineering personnel, the control room log   |
| for 09/10/98 was reviewed to determine the events surrounding the VIAS       |
| actuation.   A containment pressure reduction (CPR) had been initiated prior |
| to the VIAS actuation.  The control room logs indicate that the CPR was      |
| terminated by the VIAS.   In addition, the isolation valves for containment  |
| radiation monitoring (RM-050 and 051) were also actuated.   The isolation of |
| the monitors and the CPR are documented in the control room logs for         |
| 09/10/98.   10 CFR 50.72(b)(2)(ii) and 10 CFR 50.73(a)(2)(iv) require        |
| reporting actuations of engineered safety feature (ESF) equipment except     |
| when:                                                                        |
| (A) The actuation resulted from and was part of a pre-planned sequence       |
| during testing or reactor operation;                                         |
| (B) The actuation was invalid and:                                           |
| (1) Occurred while the system was properly removed from service;             |
| (2) Occurred after the safety function had already completed; or             |
| (3) Involved only the following specific ESFs or their equivalent systems;   |
| (i) Reactor water clean-up system;                                           |
| (ii) Control room emergency ventilation system;                              |
| (iii) Reactor building ventilation system;                                   |
| (iv) Fuel building ventilation system; or                                    |
| (v) Auxiliary building ventilation system."                                  |
|                                                                              |
| "This actuation was not preplanned, and although the actuation was invalid   |
| it affected containment equipment which is not excluded by subparagraph      |
| (B)(3).   This event should have been reported as a 4-hour verbal to the NRC |
| and a 30-day written report to the NRC."                                     |
|                                                                              |
| The NRC resident inspector has been notified by the licensee.                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35808       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 06/08/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 21:35[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/08/1999|
+------------------------------------------------+EVENT TIME:        17:40[EDT]|
| NRC NOTIFIED BY:  DAVID NOYES                  |LAST UPDATE DATE:  06/08/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN CARUSO          R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED LOW PRESSURE COOLANT INJECTION SYSTEM LOOP SELECT LOGIC ACTUATION |
| DURING LOGIC SYSTEM TESTING                                                  |
|                                                                              |
| At 1740 EDT on 06/08/99, with the unit in the Refueling mode, moderator      |
| temperature of 105F, reactor water level of 40 inches in the normal band,   |
| and the 'A' loop of shutdown cooling in service; the low pressure coolant    |
| injection (LPCI) loop select logic caused the 'A' loop injection valve to    |
| travel from the throttled position to fully open.  At the time, the 'B' loop |
| was removed from service for maintenance, and the 'B' loop injection valve   |
| went fully closed.  The effect on the plant was that shutdown cooling flow   |
| increased from 9,600 gpm to 11,200 gpm.  After 5 minutes, control was        |
| restored to the 'A' loop injection valve, and flow was reduced to 9,600 gpm. |
| There was no noticeable change on level because LPCI takes a suction from    |
| the vessel and returns water to the vessel.                                  |
|                                                                              |
| The initiation occurred during a Recirculation Motor-Generator Set Lockout   |
| Relay and 4,160-V Drive Motor Trip Control Test.  Investigation into the     |
| cause of the event is ongoing.  Logic system testing has been suspended      |
| until the cause has been determined and until a verification that all        |
| initiations occurred as designed has been completed.                         |
|                                                                              |
| The licensee notified the NRC resident inspector and plans to notify the     |
| Massachusetts Civil Defense tomorrow morning.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35809       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 06/09/1999|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 00:26[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/09/1999|
+------------------------------------------------+EVENT TIME:        00:20[EDT]|
| NRC NOTIFIED BY:  MIKE FERGUSON                |LAST UPDATE DATE:  06/09/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRIAN BONSER         R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN - BOTH CHEMICAL & VOLUME CONTROL PUMPS           |
| INOPERABLE                                                                   |
|                                                                              |
| The licensee commenced a Tech Spec required shutdown at 0020 on 6/9/99.      |
| The shutdown was terminated at 0029 when the 1A Chemical and Volume Control  |
| (CVC) charging pump was returned to an operable status.   Reactor power had  |
| been reduced to 99%.                                                         |
|                                                                              |
| On 6/7/99, at 1500 the 1A CVC charging pump was declared inoperable because  |
| the "A" Service water pump was inoperable.  At  2320 on 6/8/99, the 1B CVC   |
| charging pump was also declared inoperable because of abnormal flow.   The   |
| licensee entered Tech Spec 3.0.3 at that time, and since the condition had   |
| not been repaired by 0020 on 6/9/99, a shutdown was commenced.               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+