Event Notification Report for November 13, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/12/2002 - 11/13/2002
** EVENT NUMBERS **
39352 39356 39359 39364 39365 39367
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|General Information or Other |Event Number: 39352 |
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| 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: 11/07/2002|
| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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. |
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|General Information or Other |Event Number: 39356 |
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| 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 | |
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| | |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 39359 |
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| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 11/08/2002|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 14:50[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/08/2002|
+------------------------------------------------+EVENT TIME: 13:10[EST]|
| NRC NOTIFIED BY: V. BELLAMY |LAST UPDATE DATE: 11/08/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHARLES R. OGLE R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| FITNESS FOR DUTY |
| |
| A contract supervisor tested positive for drugs during a random test. The |
| employee's access to the plant has been terminated. Refer to HOO log for |
| additional details. |
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|Power Reactor |Event Number: 39364 |
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| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/12/2002|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 13:01[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/12/2002|
+------------------------------------------------+EVENT TIME: 09:48[EST]|
| NRC NOTIFIED BY: Joe Sullivan |LAST UPDATE DATE: 11/12/2002|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| MANUAL REACTOR TRIP OF SALEM UNIT 1 DUE TO LOW S/G WATER LEVEL CAUSED BY |
| FEED PUMP RUNBACK |
| |
| "This 4-hour notification is being made to report that Salem Unit 1 reactor |
| was manually tripped at 0948 [EST] (RPS actuation). The trip was initiated |
| due to low steam generator level (~16% narrow range). The low SG level |
| appears to have been caused due to a runback of the 11 steam generator feed |
| pump (SGFP) to idle. The cause of the runback has not been determined at |
| this time. As a result of the runback, the level in steam generators |
| dropped and the operators initiated a main turbine runback and tripped 11 |
| SGFP manually. When operators observed the steam generators approaching the |
| automatic reactor trip setpoint (14%), a manual reactor trip was initiated. |
| |
| "11, 12 & 13 auxiliary feed water pumps auto started after the trip due to |
| valid steam generator low level, as expected on a unit trip. Main feedwater |
| to the steam generators was isolated due to the "feed water interlock" which |
| is expected on a normal trip. Additionally the ATWS mitigation system |
| (AMSAC) did actuate post trip due to low steam generator levels but all |
| auxiliary feed water pumps were already running prior to the actuation. |
| |
| "Salem Unit-1 is currently in MODE 3 [Hot Standby]. Reactor coolant system |
| temperature is 547 [degrees] F with pressure at 2235 PSIG. Unit 1 has no |
| shutdown tech. spec. action statements in effect. Major equipment out of |
| service for planned maintenance includes the 16 service water pump which is |
| expected back later today and Salem Unit-3 which is scheduled to be |
| available on 11/15/02. |
| |
| "There were no personnel injuries or radiological occurrences associated |
| with this event." |
| |
| Additionally, the licensee indicated that while the exact cause of the |
| runback is not known, there was ongoing work on the limit switches for the |
| 11 SGFP at the time of the runback, and there was some arcing in the |
| switches. |
| |
| The licensee notified the resident inspector of this event. |
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|Power Reactor |Event Number: 39365 |
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| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 11/12/2002|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 16:12[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 11/12/2002|
+------------------------------------------------+EVENT TIME: 12:30[MST]|
| NRC NOTIFIED BY: DON STRAKA |LAST UPDATE DATE: 11/12/2002|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHUCK CAIN R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
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| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Startup |0 Startup |
|2 N Y 99 Power Operation |99 Power Operation |
|3 N Y 99 Power Operation |99 Power Operation |
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EVENT TEXT
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| UNINTENTIONAL RELEASE OF REVERSE OSMOSIS PRODUCT WATER |
| |
| "The following event description is based on information currently |
| available. If through subsequent reviews of this event, additional |
| information is identified that is pertinent to this event or alters the |
| information being provided at this time, a follow-up notification will be |
| made via the ENS or under the reporting requirements of 10CFR50.73. |
| |
| "On November 12, 2002, APS reported to the Arizona Department of |
| Environmental Quality (ADEQ) the unintentional release of less than 500 |
| gallons of reverse osmosis (RO) product water to sedimentation basin #2 that |
| occurred on October 19, 2002 during a storm. RO product water is make-up |
| water to the site drinking water system and meets all aquifer water quality |
| standards. The Ground Water Quality Protection Permit does not authorize |
| such a release. |
| |
| "This report to the ADEQ is in the form of a letter sent via certified |
| mail. |
| |
| "No news release is anticipated." |
| |
| The licensee notified the resident inspector of this event. |
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|Power Reactor |Event Number: 39367 |
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| 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| |
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| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
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EVENT TEXT
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| 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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021