United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2001

Event Notification Report for April 25, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/24/2001 - 04/25/2001

                              ** EVENT NUMBERS **

37806  37840  37858  37941  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37806       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/05/2001|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 12:25[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/05/2001|
+------------------------------------------------+EVENT TIME:        10:13[EST]|
| NRC NOTIFIED BY:  BRUCE BUTLER                 |LAST UPDATE DATE:  04/24/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEPHEN CAHILL       R2      |
|10 CFR SECTION:                                 |                             |
|*INB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING (RCIC) TRIPPED UNEXPECTEDLY DURING TESTING.   |
|                                                                              |
| Received RCIC "B" logic isolation signal causing RCIC in-board isolation     |
| valve, 2E51-F007, to close resulting in RCIC trip signal.  I&C personnel     |
| were performing 57SV-CAL-003-25 ATTS transmitter calibration for RCIC "B"    |
| steam line differential pressure transmitter 2E51-N057B when the isolation   |
| occurred and this instrument caused the isolation.  Investigation is in      |
| progress to determine the cause.  Received isolation signal at 1013 ET, I&C  |
| backed out of the procedure returning 2E51-N057B transmitter to service and  |
| RCIC isolation was reset and RCIC returned to standby at 1105 ET.            |
|                                                                              |
| All other Emergency Core Cooling systems were fully operable during the time |
| period RCIC was declared inoperable.                                         |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * RETRACTION ON 04/24/01 AT 1453 ET BY S. HOWARD TAKEN BY MACKINNON * *  |
| *                                                                            |
|                                                                              |
| Plant Hatch FSAR has been revised such that the Control Rod Drop accident    |
| limiting event path evaluated in the safety analysis (subsection 15.3.2)     |
| does not rely on RCIC to mitigate this Design Basis Accident (DBA).  None of |
| the DBAs, as evaluated in the safety analysis (section 15.3), rely on RCIC   |
| for event mitigation.  RCIC will no longer be an NRC notification when       |
| declared inoperable.  Therefore, this NRC notification is being retracted.   |
| R2DO (Paul Fredrickson) notified.                                            |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37840       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 03/14/2001|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 20:13[EST]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        03/14/2001|
+------------------------------------------------+EVENT TIME:        14:10[EST]|
| NRC NOTIFIED BY:  ROSS MOONITZ                 |LAST UPDATE DATE:  04/24/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI DECLARED INOPERABLE DUE TO FAILURE OF EXHAUST LINE VACUUM RELIEF VALVES |
| TO FUNCTION DURING IST TESTING                                               |
|                                                                              |
| "During routine testing of the Unit 2 High Pressure Coolant Injection system |
| (HPCI) exhaust line vacuum relief valves (VRV), it was discovered that both  |
| VRVs failed to open at their In Service Test (IST) required differential     |
| pressure value. The Unit 2 HPCI system has been declared inoperable and      |
| repairs are in progress.                                                     |
|                                                                              |
| "This event is being reported in accordance with 10CFR50.72(b)(3)(v)(D) due  |
| to a failure of a single train system which prevents fulfillment of a safety |
| function."                                                                   |
|                                                                              |
| With HPCI inoperable this places Unit 2 in a 14-day Limiting Condition of    |
| Operation.  All other ECCS systems have been verified operable.              |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
|                                                                              |
|                                                                              |
| * * * RETRACTION ON 04/24/01 AT 1254 ET BY STEVE BECK TAKEN BY MACKINNON * * |
| *                                                                            |
|                                                                              |
| The original design function of the affected vacuum relief valves was to     |
| prevent damage to the HPCI exhaust line rupture disks.  A failure of the     |
| rupture disks would result in steam being discharged into the HPCI Room and  |
| subsequent isolation of the HPCI system on high room temperature.  A         |
| modification to the rupture disk installed backing support plates to ensure  |
| that repetitive vacuum conditions in the exhaust line would not result in    |
| fatigue failure of the rupture disks.  As a result of the modification, the  |
| vacuum relief valves are no longer required to open to protect the rupture   |
| disks.                                                                       |
|                                                                              |
| Based on an Engineering evaluation, it was concluded that the HPCI exhaust   |
| line vacuum relief valves design function is not required to support HPCI    |
| system operability.                                                          |
|                                                                              |
| NUREG 1022, Rev. 2, allows "removal of a system or part of a system from     |
| service as part of a planned evolution for maintenance or surveillance       |
| testing when done in accordance with an approved procedure and the plant's   |
| TS (unless a condition is discovered that could have prevent the system from |
| performing its function)."                                                   |
|                                                                              |
| In this case, HPCI was removed from service for planned maintenance per      |
| plant procedures and Technical Specifications.  The condition found (vacuum  |
| relief valve inoperability) would not have prevented HPCI from performing    |
| its safety function; therefore this event is not reportable per              |
| 10CFR50.72(b)(3)(D) or 10CFR50.73(a)(2)(v).  R1DO (David Silk) notified.     |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37858       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/22/2001|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 16:10[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/22/2001|
+------------------------------------------------+EVENT TIME:        11:10[EST]|
| NRC NOTIFIED BY:  GUY GRIFFIS                  |LAST UPDATE DATE:  04/24/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|10 CFR SECTION:                                 |                             |
|*INB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RCIC DECLARED INOPERABLE                                                     |
|                                                                              |
| During an investigation of a ground on Div I 125/250 volt D.C. bus, the      |
| source of the ground was determined to be 2E51-F008 primary containment      |
| isolation valve.  2E51-F008 is the outboard steam supply to reactor core     |
| isolation coolant (RCIC).  It was closed and de-energized.  2E51-F008        |
| closure rendered RCIC system inoperable.                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * RETRACTION ON 04/24/01 AT 1453 ET BY S. HOWARD TAKEN BY MACKINNON * *  |
| *                                                                            |
|                                                                              |
| Plant Hatch FSAR has been revised such that the Control Rod Drop accident    |
| limiting event path evaluated in the safety analysis (subsection 15.3.2)     |
| does not rely on RCIC to mitigate this Design Basis Accident (DBA).  None of |
| the DBAs, as evaluated in the safety analysis (section 15.3), rely on RCIC   |
| for event mitigation.  RCIC will no longer be an NRC notification when       |
| declared inoperable.  Therefore, this NRC notification is being retracted.   |
| R2DO (Paul Fredrickson) notified.                                            |
|                                                                              |
| The NRC Resident Inspector was notified was notified of this retraction by   |
| the licensee.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37941       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 04/24/2001|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 03:23[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        04/24/2001|
+------------------------------------------------+EVENT TIME:        02:06[CDT]|
| NRC NOTIFIED BY:  MIKE MEYER                   |LAST UPDATE DATE:  04/24/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |STUART RICHARDS      NRR     |
|*AEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |NADER MAMISH         IRO     |
|                                                |GENE CANUPP          FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DECLARATION OF AN UNUSUAL EVENT DUE TO A SMALL DEBRIS FIRE ON A STEAM        |
| GENERATOR PLATFORM DURING THE PERFORMANCE OF EDDY CURRENT TESTING            |
|                                                                              |
| At 0148 CDT, the control room was notified of a fire in the Unit 1           |
| containment.  It is currently believed that a problem with eddy current      |
| testing equipment (possibly an electrical fault) resulted in a fire          |
| involving a small pile of debris on the 8-foot elevation steam generator 'A' |
| platform.  The fire brigade was dispatched immediately, and the fire was     |
| extinguished within 2 to 3 minutes of the time the extinguishing agent       |
| (water) was applied.  Offsite assistance was not required.  At 0211 CDT, a   |
| second team provided the control room with a confirmatory report that the    |
| fire had been successfully extinguished.  There were no reports of injuries  |
| or the spread of contamination as a result of the fire.                      |
|                                                                              |
| The exact time the extinguishing agent was applied to the fire was not known |
| at the time of this event notification.  Because the exact duration of the   |
| fire (i.e., less than or greater than 10 minutes) was not known, the         |
| licensee declared an Unusual Event at 0206 CDT as a conservative measure.    |
|                                                                              |
| At the time of this event, Unit 1 was defueled, and Unit 2 was operating at  |
| 100% power.                                                                  |
|                                                                              |
| The licensee notified Manitowac and Kewaunee Counties, the Sate of           |
| Wisconsin, and the NRC resident inspector.                                   |
|                                                                              |
| ***** UPDATE AT 0343 EDT ON 04/24/01 FROM MIKE MEYER TO LEIGH TROCINE *****  |
|                                                                              |
| The licensee terminated the Unusual Event at 0243 CDT.                       |
|                                                                              |
| The licensee plans to notify Manitowac and Kewaunee Counties, the Sate of    |
| Wisconsin, and the NRC resident inspector.  The NRC operations officer       |
| notified the R3DO (Kozak), NRR EO (Richards), IRO (Mamish), and FEMA         |
| (Canupp).                                                                    |
+------------------------------------------------------------------------------+