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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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37016       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37017       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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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