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Event Notification Report for December 26, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/21/2001 - 12/26/2001

                              ** EVENT NUMBERS **

38518  38537  38589  38590  38591  38592  
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|Power Reactor                                    |Event Number:   38518       |
+------------------------------------------------------------------------------+
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| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/26/2001|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 13:37[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/26/2001|
+------------------------------------------------+EVENT TIME:        12:32[CST]|
| NRC NOTIFIED BY:  ROBERT ADAMS                 |LAST UPDATE DATE:  12/22/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRUCE JORGENSEN      R3      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ERDS INOPERABLE DUE TO PLANNED OUTAGE OF THE PLANT PROCESS COMPUTER
SYSTEM   |
| (PPCS)                                                                       |
|                                                                              |
| AT 1232 CT, the Point Beach Nuclear Plant ERDS became inoperable as a result |
| of modifications to change out the plant process computer system (PPCS).     |
| This is a planned evolution.  ERDS will remain inoperable until              |
| approximately, December 18, 2001.                                            |
|                                                                              |
| This information was verbally provided to a representative of NRR during the |
| week of 10/15/2001.  The senior resident inspector has also been briefed on  |
| the modifications and schedule.  NMC to NRC letter (NRC 01-0080) dated       |
| 11/21/2001 stated we would be submitting this Non-Emergency report.          |
|                                                                              |
| ***** UPDATE FROM RICK ROBBINS TO LEIGH TROCINE AT 2006 EST ON 11/27/01      |
| *****                                                                        |
|                                                                              |
| The following additional information is a portion of a facsimile received    |
| from the licensee:                                                           |
|                                                                              |
| "As part of the PPCS modification, several inputs to the SPDS monitor were   |
| also made unavailable.  Any out-of-service indications on the SPDS can be    |
| obtained by control room control board indications."                         |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations center |
| notified the R3DO (Bruce Jorgensen).                                         |
|                                                                              |
| * * * UPDATE 1259EST ON 12/22/01 FROM RYAN RODE TO S. SANDIN * * *           |
|                                                                              |
| The licensee provided the following information as an update:                |
|                                                                              |
| "On 11/26/01 at 12:32, the PBNP ERDS and SPDS were declared out of service   |
| for the PPCS upgrade project.  EN #38518 indicated to the NRC that the       |
| systems would remain unavailable until approximately December 18, 2001.  Due |
| to reliability issues with the newly installed PPCS, that expected date has  |
| been delayed to approximately January 3, 2002."                              |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified R3DO(Phillips).  |
+------------------------------------------------------------------------------+
.
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38537       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 12/04/2001|
|    UNIT:  [2] [3] []                STATE:  NY |NOTIFICATION TIME: 16:03[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        12/04/2001|
+------------------------------------------------+EVENT TIME:        12:00[EST]|
| NRC NOTIFIED BY:  FRANK KICH                   |LAST UPDATE DATE:  12/21/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |JACK STROSNIDER      NRR     |
|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF PART OF THE OFF-SITE NOTIFICATION SIRENS TO OPERATE WHEN
TESTED   |
|                                                                              |
| The licensee was performing their semi-annual off-site notification siren    |
| operational test and found that only 147 of 154 sirens operated properly.    |
| The remaining 7 sirens are being investigated for the cause of their         |
| failure.  The licensee will use the Emergency Plan alternate means of        |
| informing the public, including route alerting and public announcements in   |
| the event of an accident.                                                    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE 1200EST ON 12/21/01 FROM JIM READY TO S. SANDIN * * *           |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "Indian Point Units 1,2 and 3 is retracting the eight (8) hour non-emergency |
| notification made in accordance with 10 CFR 50.72(b)(3)(xiii) on December 4, |
| 2001, at 1603 hours (EN # 38537). The notification reported the loss of a    |
| portion of the offsite communication capability due to a failure of 5 of 16  |
| sirens in Orange County to actuate during the semi-annual siren test.  The   |
| notification was a result of less than a 90% response rate of sirens in one  |
| county (Orange).  At the time, 5 sirens in Orange County were being          |
| investigated for the cause of failure.                                       |
|                                                                              |
| "Upon subsequent investigation and testing, which was completed on December  |
| 13, Entergy determined that this condition was not reportable because the 5  |
| Orange County sirens were acceptable and operable and thereby did not exceed |
| the threshold for notification.  The cause of the sirens to appear to have   |
| failed was attributed to a discrepancy in test coordination which occurred   |
| during the conduct of the siren test.                                        |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified R1DO(Kinneman).  |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38589       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OK DEQ RAD MANAGEMENT                |NOTIFICATION DATE: 12/21/2001|
|LICENSEE:  STANDARD TESTING                     |NOTIFICATION TIME: 11:33[EST]|
|    CITY:  OKLAHOMA CITY            REGION:  4  |EVENT DATE:        12/20/2001|
|  COUNTY:                            STATE:  OK |EVENT TIME:        08:00[CST]|
|LICENSE#:  OK-17054-01           AGREEMENT:  Y  |LAST UPDATE DATE:  12/21/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MIKE BRODERICK               |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER MOISTURE DENSITY
GAUGE     |
|                                                                              |
| On 12/20/01 a Standard Testing employee on his way to a jobsite stopped at a |
| McDonalds located at I-35 and South 29th Street in Oklahoma City, between    |
| 0725 and 0800CST for breakfast.  Later in the day the employee noticed that  |
| the soil moisture density gauge was missing.  The device was properly        |
| secured/blocked and braced for transport.  The chain securing the transport  |
| case was cut and the case containing the gauge missing.  The licensee        |
| informed both the Oklahoma DEQ Rad Management office and the Oklahoma City   |
| Police Department.  A press release will be issued offering a $500.00        |
| reward.  The stolen device is a Troxler Moisture Density Gauge Model #3430,  |
| S/N 25733, containing an 8 millicurie Cs-137 source, S/N 75-8614, and a 40   |
| millicurie  Am241/Be source, S/N 47-22109.                                   |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38590       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 12/22/2001|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 19:20[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        12/22/2001|
+------------------------------------------------+EVENT TIME:        15:42[EST]|
| NRC NOTIFIED BY:  JAMES CROSSMAN               |LAST UPDATE DATE:  12/22/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |LEONARD WERT         R2      |
|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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 EXPERIENCED A REACTOR TRIP/TURBINE TRIP DUE TO EHC SYSTEM LOSS OF 
   |
| POWER SUPPLY                                                                 |
|                                                                              |
| The Unit 2 electro-hydraulic control (EHC) system power supply failed,       |
| causing a loss of electrical load.  The resulting shrink in steam generator  |
| water level tripped the reactor on steam generator "1A" Lo-Lo level ("first  |
| out alarm indication").  A turbine trip on reactor trip occurred, as         |
| expected.  All control rods fully inserted.  Both AMSAC and the auxiliary    |
| feedwater (AFW) system actuated ( 2 motor-driven and the turbine-driven      |
| pump).  However, normal feedwater remained in service and the AFW pumps have |
| subsequently been returned to standby.                                       |
|                                                                              |
| Unit 2 is currently stable in mode 3 with decay heat removal to the main     |
| condenser.  No secondary safeties/atmospheric relief valves lifted.          |
| Abnormal indications during the transient included reactor coolant pump      |
| (RCP) "A" vibration alarm (cleared during transient), pressurizer            |
| power-operated relief valve (PORV) lifted/reseated and one Individual rod    |
| position indication (IRPI) indicator malfunctioned.                          |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38591       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 12/24/2001|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 09:39[EST]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        12/24/2001|
+------------------------------------------------+EVENT TIME:        07:22[EST]|
| NRC NOTIFIED BY:  DOUG GOMEZ                   |LAST UPDATE DATE:  12/24/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| Unaccounted for security weapon, immediate compensatory measures taken on    |
| discovery.                                                                   |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| Refer to the HOO Log for additional details.                                 |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38592       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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:  12/25/2001|
|  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     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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, their swing Emergency Diesel Generator, 1B,  |
| is degraded but fully operable.  Only other problem was that their 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 watching the output breakers.                         |
|                                                                              |
| The NRC resident inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+
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