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
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|Power Reactor |Event Number: 35806 |
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+------------------------------------------------------------------------------+
| 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 |
| | |
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EVENT TEXT
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| 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). |
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+------------------------------------------------------------------------------+
|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. |
+------------------------------------------------------------------------------+
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|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 105�F, 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. |
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|Power Reactor |Event Number: 35809 |
+------------------------------------------------------------------------------+
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| 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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021