Event Notification Report for November 14, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/13/2002 - 11/14/2002
** EVENT NUMBERS **
39300 39352 39356 39367 39368 39369
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39300 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 10/17/2002|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 18:55[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/17/2002|
+------------------------------------------------+EVENT TIME: 14:30[CDT]|
| NRC NOTIFIED BY: BRIAN HUPKE |LAST UPDATE DATE: 11/13/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 94 Power Operation |94 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| HPCI INOPERABLE DUE TO LOW INTERNAL BATTERY RESISTANCE |
| |
| The licensee reported that during a 250 Vdc battery surveillance the |
| internal resistance of cell #18 was greater than the technical specification |
| (TS) limit. As a result, the licensee declared battery bank 1D4 inoperable |
| which also rendered inoperable the HPCI system and any containment isolation |
| valves powered from the battery bank. This included 5 total CIVs |
| [Containment isolation valves] from the following systems: HPCI, RWCU and |
| MSL drain and Torus drain valves. Corrective maintenance was performed on |
| the battery cell and the internal resistance passed the TS limit. HPCI and |
| CIVs were returned to an operable status approximately 3 hours after being |
| declared inoperable. At the time of this event, the RCIC system was |
| inoperable for planned maintenance so the LCO entered for HPCI was more |
| restrictive allowing 12 hours rather than the normal 14 day LCO for HPCI. |
| |
| *** THIS EVENT WAS RETRACTED AT 1357 ON 11/13/2002 BY CLARE BLEAU TO ERIC |
| THOMAS *** |
| |
| The licensee is retracting this report based on the following: |
| |
| "On 10/17/02 Event Notification #39300 was completed pursuant to 10 CFR |
| 50.72 (b)(3)(v)(D) due to the 250 Volt Station Battery 1D4 being declared |
| inoperable which caused the High Pressure Coolant Injection (HPCI) system to |
| also be inoperable. At the time that this occurred, the Reactor Core |
| Isolation Cooling (RCIC) system was also inoperable due to preplanned |
| maintenance. This required that a 12 hour to hot shutdown and 36 hour to |
| cold shutdown LCO be entered per Technical Specification 3.5.1.J. |
| Maintenance was performed on battery 1D4 and it was returned to operability. |
| The other related LCOs were also exited prior to plant shutdown. |
| |
| "An operability evaluation was subsequently completed which determined that |
| 1D4 could have performed its design function with the data taken from STP |
| 3.8.4-05. C&D Technologies has confirmed this. Only one of the two |
| connections needs to be below 50 micro ohms to meet TS 3.8.4.5. |
| |
| "If all of the discharge current were to pass through the 129 micro ohm |
| connection, the voltage drop would be 0.06 volts. This has no bearing on the |
| design function of the 250 VDC system. 1D4 currently has a design margin of |
| 1.65 (65% excess battery capacity). Therefore, battery 1D4 actually was |
| operable and capable of performing its required safety function. The PCIV |
| [Primary Containment Isolation Valve] LCO 3.6.1.3 was also entered for |
| 250VDC MOVs that are PCIVs. This included the HPCI outboard steam supply |
| valve MO-2239 and the HPCI feedwater injection isolation valve MO-2312. |
| Review of the shift logs and discussion with the shift manager confirmed |
| that these valves were not closed so that HPCI remained available during |
| this event. No LER is required under 10 CFR 50.73 (a)(2)(v)(D) and the |
| 8-hour Non-emergency notification under 10 CFR 50.72 (b)(3)(v)(D) (EN#39300) |
| can be retracted." |
| |
| The NRC Resident Inspector was notified of this retraction by the licensee. |
| |
| Notified Bruce Burgess, R3DO. |
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+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39352 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 11/07/2002|
|LICENSEE: HARRINGTON GEOTECHNICAL ENGINEERING |NOTIFICATION TIME: 12:50[EST]|
| CITY: ORANGE REGION: 4 |EVENT DATE: 10/06/2002|
| COUNTY: ORANGE STATE: CA |EVENT TIME: 04:30[PST]|
|LICENSE#: CA 5657 AGREEMENT: Y |LAST UPDATE DATE: 11/13/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES MARSCHALL R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT GREGER | |
| HQ OPS OFFICER: MIKE RIPLEY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING STOLEN MOISTURE DENSITY GAUGE |
| |
| The licensee reported at 1115 PST on 7/6/02 that a CPN Model MC3 moisture |
| density gauge was stolen from the back of the licensee's pickup truck on |
| 7/06/02 sometime between 0430 and 0530 PST in the city of Orange, CA . The |
| gauge serial number is not currently available. Gauge contains nominally 10 |
| millicuries Cs-137 and 30 millicuries Am-241/Be. The gauge was chained and |
| locked in the back of the pickup and the chain was found cut. Local law |
| enforcement responded. The licensee plans on issuing a press release and a |
| reward for the return of the gauge. |
| |
| ****UPDATE ON 11/13/02 AT 14:100 FROM LAURA**** |
| |
| The above text listed the incorrect date for the event. The event occurred |
| on 11/6/02 and NOT 7/6/02. |
| |
| Notified DIRO (McGinty) and R4DO (Cain). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39356 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 11/08/2002|
|LICENSEE: LITTON SYSTEMS, INC. |NOTIFICATION TIME: 09:41[EST]|
| CITY: Apopka REGION: 2 |EVENT DATE: 11/07/2002|
| COUNTY: STATE: FL |EVENT TIME: [EST]|
|LICENSE#: 2159-1 AGREEMENT: Y |LAST UPDATE DATE: 11/08/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES R. OGLE R2 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JERRY EAKINS | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - LOST OR STOLEN AM-241 SOURCE |
| |
| "Licensee reported at 1530 [EST] that source could not be found during |
| current inventory. Last inventory was performed on 14 February. Licensee is |
| conducting an investigation." |
| |
| The lost or stolen material is a sealed 4 microcurie Am - 241 source used |
| for military sighting application. |
| |
| The State of Florida Bureau of Radiation Control radiological incident |
| number is FL02-172. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39367 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 11/13/2002|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 04:53[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/13/2002|
+------------------------------------------------+EVENT TIME: 04:07[EST]|
| NRC NOTIFIED BY: J.C. WILLIAMS |LAST UPDATE DATE: 11/13/2002|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LEONARD WERT R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 21 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP FROM 21% POWER |
| |
| "Unit Two Reactor was at 21% power and Main Turbine roll up was in progress |
| to synch to [the] grid after 2R9 refueling outage. Main feedwater was in |
| service to all 4 steam generators. Steam generator #3 water level increased |
| to the Hi-Hi P-14 setpoint which tripped the main turbine and main |
| feedwater. AFW [auxiliary feedwater] actuated as required. The reactor was |
| manually tripped. All rods fully inserted. The cause of the transient is |
| being evaluated at this time. The reactor is stable in Mode 3 [Hot |
| Standby]." |
| |
| Highest steam generator level attained was 88%. |
| |
| Licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39368 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 11/13/2002|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 10:13[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 11/13/2002|
+------------------------------------------------+EVENT TIME: 04:58[CST]|
| NRC NOTIFIED BY: D. CLARK |LAST UPDATE DATE: 11/13/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRUCE BURGESS R3 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 1 EMERGENCY DIESEL GENERATOR AUTOSTARTED AND LOADED TO DIVISION 2 BUS. |
| |
| "At 0458 CST on 11/13/02, an undervoltage was detected on 4 KV ESS Div 2 |
| Bus 14-1. The normal feed breaker to the bus auto tripped, the U-1 |
| Emergency Diesel Generator auto started, and loaded to the bus. The |
| preliminary investigation determined that work was being performed in a |
| breaker cubicle adjacent to the bus auxiliary cubicle. Vibration from the |
| work may have caused the bus potential fuse drawer to fall open, actuating |
| the bus undervoltage relay. Normal power to the bus was restored at 0538 |
| hours. A prompt investigation is in progress." |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39369 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 11/14/2002|
| UNIT: [] [] [3] STATE: SC |NOTIFICATION TIME: 05:24[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 11/14/2002|
+------------------------------------------------+EVENT TIME: 04:19[EST]|
| NRC NOTIFIED BY: NEIL CONSTANCE |LAST UPDATE DATE: 11/14/2002|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LEONARD WERT R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 A/R Y 100 Power Operation |0 Hot Standby |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP |
| |
| "The Moisture Separator drain tanks each provide a trip signal to the main |
| turbine on a high level on 2 [of] 3 level switches. At 0419 [EST], 2 [of] 3 |
| level switches indicated a high level in the 3A Moisture Separator Drain |
| Tank Level, resulting in a MT [Main Turbine] trip and anticipatory RPS trip. |
| Post-trip response was normal." |
| |
| All rods inserted into the core. No PORV's lifted. No ECCS actuation. The |
| cause of the heater drain system upset is under investigation. |
| |
| The licensee notified the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021