Event Notification Report for December 28, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/27/2001 - 12/28/2001
** EVENT NUMBERS **
38592 38597 38598
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|Power Reactor |Event Number: 38592 |
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 12/25/2001|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 20:40[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/25/2001|
+------------------------------------------------+EVENT TIME: 18:19[EST]|
| NRC NOTIFIED BY: STEVE HOWARD |LAST UPDATE DATE: 12/27/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LEONARD WERT R2 |
|10 CFR SECTION: |JOSEPH HOLONICH IRO |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 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
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM DUE TO 'A' RECIRCULATION PUMP SPEED
UNEXPECTEDLY |
| INCREASING |
| |
| "At 18:19 Eastern on 12/25/01, Hatch Nuclear Plant Unit 2 reactor tripped. |
| The cause is presently under investigation. Preliminary indications are |
| that the 'A' Recirculation Pump speed increased. Reactor power increased |
| causing the all four channels in the Neutron Monitoring System to trip. |
| Group 2 Primary Containment isolation occurred. All group 2 isolated as |
| expected. No other group isolations were required. RFPTs were used to |
| maintain reactor water level, and Main Turbine Bypass valves maintained |
| reactor pressure. No initiation signals required ECCS or RCIC to |
| initiate." |
| |
| On the automatic reactor scram, one control rod inserted to the 01 position |
| and drifted to the 00 position. The swing Emergency Diesel Generator, 1B, |
| is degraded but fully operable. The only other problem was that the Main |
| Generator Output breakers did not automatically open but were manually |
| opened from the control room. This problem has occurred before, and the |
| control room operators are watching the output breakers. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
| |
| ***** UPDATE FROM GUY S. GRIFFIS TO LEIGH TROCINE AT 1217 ON 12/27/01 ***** |
| |
| This update was made to correct/clarify the cause of the automatic reactor |
| scram from 100% power and to provide additional information. |
| |
| It was initially reported that 'A' recirculation pump speed increased and |
| caused all four channels in the neutron monitoring system to trip. However, |
| further review determined that decreased main steam line 'B' flow caused the |
| neutron monitoring system trip due to increased flux. Initial diagnostics |
| indicate the 2B21-F028B main steam isolation valve as the failure. |
| |
| The licensee's investigation is still ongoing. The licensee plans to |
| provide additional detailed information in a Licensee Event Report. |
| |
| NOTE: Cold Shutdown was achieved at 0255 on 12/27/01 in compliance with |
| Technical Specification 3.6.1.3.e. |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R2DO (Boland) and IRO (Holonich). |
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|Power Reactor |Event Number: 38597 |
+------------------------------------------------------------------------------+
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| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 12/27/2001|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 14:10[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 12/16/2001|
+------------------------------------------------+EVENT TIME: 00:18[EST]|
| NRC NOTIFIED BY: ANDY HALLIDAY |LAST UPDATE DATE: 12/27/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHELE EVANS R1 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| INVALID PRIMARY AND SECONDARY CONTAINMENT ISOLATION DUE TO A SPURIOUS
|
| UPSCALE SPIKE OF REACTOR BUILDING VENTILATION RADIATION MONITOR B
(60-Day |
| Report) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Event Description" |
| |
| "At 0018 hours on December 16, 2001, with the plant operating at 100 percent |
| of rated thermal power, Reactor Building (Secondary Containment) Ventilation |
| Exhaust Radiation Monitor B spiked upscale and immediately returned to |
| normal." |
| |
| "The radiation monitor upscale spike (trip) resulted in automatic closure of |
| outboard isolation valves and therefore isolation of the following systems |
| or functions: |
| * Primary Containment Drywell and Suppression Chamber pressure sensing for |
| alarm and indication functions only, |
| * Primary Containment Continuous Atmosphere Monitoring (CAM) for |
| particulate and gaseous radioactivity monitoring, and |
| * Primary Containment Hydrogen and Oxygen Analyzer B." |
| |
| "The trip signal also resulted in automatic isolation of the Reactor |
| Building (Secondary Containment) Ventilation system and starting of Standby |
| Gas Treatment subsystem B to maintain the reactor building atmosphere at a |
| slightly negative pressure." |
| |
| "System performance was in accordance with the design. Examination of |
| operating records indicated that the redundant radiation monitor, other |
| monitoring systems, and the plant computer system did not detect any |
| abnormal radioactivity. Shift operating and radiation protection personnel |
| investigated and did not detect any abnormal radiological conditions. |
| Examination of the radiation monitor did not reveal any indication of |
| abnormal operation, and it was concluded that the trip signal had been a |
| spurious invalid signal." |
| |
| "Shift operating personnel completed restoration of the affected systems to |
| normal at 0104 hours, 46 minutes after the event start." |
| |
| "Actions Taken" |
| |
| "1. Verified system response was in accordance with the design. |
| 2. Investigated radiological conditions and determined they were normal. |
| 3. Restored the affected systems to normal." |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 38598 |
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| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 12/27/2001|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 16:03[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 12/27/2001|
+------------------------------------------------+EVENT TIME: 13:21[EST]|
| NRC NOTIFIED BY: DOUG PERRY |LAST UPDATE DATE: 12/27/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHELE EVANS R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 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 M/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM AFTER TWO RECIRCULATION MOTOR-GENERATOR (MG)
SETS |
| TRIPPED DURING THE PERFORMANCE OF ANTICIPATED TRANSIENT WITHOUT
SCRAM (ATWS) |
| LOGIC TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "While performing ATWS logic testing, both [the] 'A' [and] 'B' |
| [recirculation] MG sets tripped, and the reactor was scrammed. The cause of |
| the scram is being determined at this time. All control rods fully inserted |
| on the scram. All safety systems functioned properly during the transient. |
| The plant is in the process of being maneuvered to Cold Shutdown." |
| |
| The licensee stated that the main steam isolation valves remained open and |
| that none of the safety relief valves lifted. In addition, there were no |
| emergency core cooling system actuations, and none were required. The |
| reported engineered safety feature actuation was the manual actuation of the |
| reactor protection system. |
| |
| The unit is currently stable in Hot Shutdown. Normal condensate and |
| feedwater is being utilized to supply water to the reactor vessel, and the |
| condenser is being utilized as a heat sink. Containment parameters are |
| normal, offsite power is available, and the electrical grid is stable. The |
| emergency diesel generators and engineered safety feature systems are |
| available if needed. |
| |
| The licensee stated that the ATWS logic test procedure was not new and that |
| it had been performed on several occasions in the past. The ATWS logic test |
| was successfully completed for the 'A' side earlier today, and the plant |
| transient occurred during the performance of the ATWS logic test for the 'B' |
| side. The cause of the recirculation MG set trips is currently under |
| investigation. |
| |
| The licensee notified the NRC resident inspector. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021