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
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| 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). |
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.
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|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). |
+------------------------------------------------------------------------------+
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|General Information or Other |Event Number: 38589 |
+------------------------------------------------------------------------------+
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| 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
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| 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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