Event Notification Report for May 23, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/22/2000 - 05/23/2000
** EVENT NUMBERS **
37015 37016 37017 37018 37019
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|Power Reactor |Event Number: 37015 |
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| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/22/2000|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 04:48[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/22/2000|
+------------------------------------------------+EVENT TIME: 02:53[EDT]|
| NRC NOTIFIED BY: BOB KIDDER |LAST UPDATE DATE: 05/22/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|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 |
| | |
| | |
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EVENT TEXT
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| - ESF ACTUATION OF REACTOR WATER CLEANUP SYSTEM FOR UNKNOWN REASONS - |
| |
| At 0253 on 05/22/00, the plant experienced an isolation of the Reactor Water |
| Cleanup System on a Division 2 isolation signal when the Residual Heat |
| Removal heat exchanger vent valve closed unexpectedly. An apparent |
| electrical power supply spike to the Division 2 isolation instrumentation |
| occurred. No testing or maintenance activities or electrical storms were |
| occurring at the time of the isolation. The licensee is investigating the |
| cause of the isolation. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 37016 |
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| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 05/22/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 13:42[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 05/22/2000|
+------------------------------------------------+EVENT TIME: 12:59[EDT]|
| NRC NOTIFIED BY: ABRAMSKI |LAST UPDATE DATE: 05/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAN HOLODY R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM MAY NOT BE PROTECTED BY STEAM |
| LEAK DETECTION CIRCUITRY. |
| |
| A LICENSEE ENGINEERING REVIEW IDENTIFIED A SECTION OF RCIC SYSTEM PIPING |
| WHICH MAY NOT BE PROTECTED BY THE STEAM LEAK DETECTION CIRCUITRY. |
| SPECIFICALLY, THE STEAM SUPPLY ISOLATION SIGNAL MAY NOT ISOLATE A POSTULATED |
| CRACKED STEAM SUPPLY LINE PRIOR TO CRACK PROPAGATION AS IN THE DESIGN INTENT |
| OF THE STEAM LEAK DETECTION SYSTEM. THE LICENSEE IS CONTINUING WITH ITS |
| INVESTIGATION. THE RCIC SYSTEM WAS NOT DECLARED INOPERABLE AND THE LICENSEE |
| HAS NOT ENTERED ANY LCO ACTION STATEMENTS. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37017 |
+------------------------------------------------------------------------------+
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| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/22/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 16:27[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/22/2000|
+------------------------------------------------+EVENT TIME: 11:53[CDT]|
| NRC NOTIFIED BY: LYNCH |LAST UPDATE DATE: 05/22/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CLAUDE JOHNSON R4 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| POSITIVE TEST FOR ALCOHOL |
| |
| AN ENTERGY EMPLOYEE TESTED POSITIVE FOR ALCOHOL FOLLOWING A FOR-CAUSE TEST. |
| UPON NOTIFICATION, THE EMPLOYEE'S PLANT ACCESS AUTHORIZATION WAS SUSPENDED |
| AT RIVER BEND STATION PENDING FURTHER INVESTIGATION. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37018 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/23/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 00:11[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/22/2000|
+------------------------------------------------+EVENT TIME: 21:59[CDT]|
| NRC NOTIFIED BY: JOHN LECHMAIER |LAST UPDATE DATE: 05/23/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - AUTO Rx SCRAM FROM 100% AFTER REPLACEMENT OF MAIN TURBINE CONTROL VALVE |
| SOLENOID - |
| |
| On 05/21/00, the Unit 2 Main Turbine #1 Control Valve Fast Acting Solenoid |
| failed its required Tech Spec Surveillance Test. |
| |
| At 2159 CDT on 05/22/00, during return to service activities following |
| replacement of this solenoid, Unit 2 automatically scrammed from 100% power |
| due to receipt of an APRM High-High RPS Actuation signal. All control rods |
| inserted completely. No safety/relief valves lifted. Steam is being dumped |
| to the main condenser. During the transient, reactor vessel water level |
| dropped to +8 inches (normal level is +30 inches) and all PCIS Group II |
| actuations occurred, as expected. These actuations included Reactor |
| Building Ventilation Valves closed, Train 'A' Standby Gas Treatment System |
| auto started (Train 'B' SBGT System was inoperable), Control Room |
| Ventilation System isolated, and Containment Isolation Valves closed. Quad |
| Cities has one Emergency Diesel Generator (EDG) for each unit and a shared |
| EDG. The Unit 2 EDG received a spurious auto start signal during the 4 KV |
| auxiliary bus power transfer to the reserve transformer. The licensee |
| secured the Unit 2 EDG. |
| |
| Unit 2 is now stable in Condition 3 (Hot Shutdown) with reactor vessel water |
| level within its normal band. |
| |
| This event had no effect on Unit 1 which is at 100% power. |
| |
| The licensee is investigating the cause of this reactor scram. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37019 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/23/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 02:52[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 05/22/2000|
+------------------------------------------------+EVENT TIME: 23:38[EDT]|
| NRC NOTIFIED BY: NICK CONICELLA |LAST UPDATE DATE: 05/23/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAN HOLODY 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 Y 4 Startup |4 Startup |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - HIGH PRESSURE COOLANT INJECTION SYSTEM AUTO ISOLATED WHILE BRINGING IT ON |
| LINE - |
| |
| At 2338 on 05/22/00, the High Pressure Coolant Injection (HPCI) System |
| isolated due to a spurious high steam flow isolation signal. A valid high |
| steam line flow condition would normally be indicative of a piping break; |
| however, a piping break did not occur. Although the signal was not valid, |
| this is nonetheless considered an Engineered Safety Features (ESF) Actuation |
| since a containment isolation had occurred. |
| |
| The Hope Creek reactor was in Operational Condition 2 (Startup) with Reactor |
| Coolant System (RCS) pressure at 200 psig and power at about 4%. The HPCI |
| System steam line warmup, which is required to place the HPCI System in a |
| standby alignment, had just commenced. When shutdown, the HPCI steam line |
| is isolated from the reactor by three containment isolation valves. These |
| valves are an outboard valve, an inboard valve, and a bypass valve around |
| the inboard valve for steam line warm-up purposes. As part of the steam |
| line warmup procedure, the outboard valve is fully opened and the inboard |
| bypass valve is throttled to slowly heat up and pressurize the steam line. |
| Once the steam line is pressurized, the inboard valve is opened. |
| |
| During the initial phases of the steam line warmup process, a high steam |
| line flow signal was generated when the bypass valve was throttled open. |
| This occurred due to steam pressure and flow perturbations within the steam |
| line. As a result, an isolation signal was generated and the bypass valve |
| automatically closed as expected for this isolation signal. Prior to |
| resetting the isolation signal, the HPCI steam line was verified to be |
| operable. The HPCI System warmup was then recommenced and the HPCI System |
| is currently in its standby alignment. |
| |
| 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