Event Notification Report for June 17, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/14/2002 - 06/17/2002
** EVENT NUMBERS **
38979 38985 38991 38992 38993 38995
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|General Information or Other |Event Number: 38979 |
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| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE:
06/11/2002|
|LICENSEE: THE BOEING COMPANY |NOTIFICATION TIME: 19:50[EDT]|
| CITY: ANAHEIM REGION: 4 |EVENT DATE: 06/11/2002|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: 0065-30 AGREEMENT: Y |LAST UPDATE DATE: 06/11/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANTHONY GODY R4 |
| |THOMAS ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT GREGER | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT FROM CA REGARDING POTENTIAL PERSONNEL
OVEREXPOSURE |
| |
| The California state radiation safety officer called in a potential 20.2202 |
| personnel overexposure incident that occurred at The Boeing Company in |
| Anaheim, California. The licensee utilizes irradiator facilities large |
| enough for an individual to enter. The individual's dosimeter was read by |
| the personnel monitoring vendor (i.e., Landauer) as 94 Rem DDE, 94 Rem LDE |
| and 112 Rem SDE. The dosimetry was worn during the period of April 1 to |
| April 30, 2002. The licensee commenced an investigation to determine the |
| validity of the high and unexpected reading. The licensee will conduct an |
| interview with the individual and also the State indicated a blood test will |
| most likely be performed. The State indicated the badge received a "static" |
| exposure, and it will probably turn out to be a dosimeter-only exposure. |
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|General Information or Other |Event Number: 38985 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 06/12/2002|
|LICENSEE: FURGO SOUTH INC. |NOTIFICATION TIME: 17:30[EDT]|
| CITY: HOUSTON REGION: 4 |EVENT DATE: 06/12/2002|
| COUNTY: HARRIS STATE: TX |EVENT TIME: 12:00[CDT]|
|LICENSE#: L00058 AGREEMENT: Y |LAST UPDATE DATE: 06/12/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANTHONY GODY R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS (via fax) | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE |
| |
| "A technician was transporting a gauge that was chained, locked, and secured |
| on the back of a pickup truck. He stopped at a restaurant for a take out |
| lunch. Upon returning to the truck, he noticed the gauge was missing. The |
| chain was cut. |
| Some other items, including test equipment and a sand cone, were taken. |
| Gauge: Troxler Model 3430, ser#26992 Sources: 8 mCi Cs-137 ser#750-171 [and] |
| 40 mCi Am-241 ser#47-23560." |
| |
| The local police, Troxler Electronics and the TXDOT were informed. Texas |
| Incident No.: I-7907 |
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|Power Reactor |Event Number: 38991 |
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| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 06/14/2002|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 07:14[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/14/2002|
+------------------------------------------------+EVENT TIME: 04:35[CDT]|
| NRC NOTIFIED BY: KLAY KLIMPLE |LAST UPDATE DATE: 06/14/2002|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANTHONY GODY R4 |
|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 M/R Y 100 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| MANUAL REACTOR TRIP FOLLOWING CLOSURE OF A FEEDWATER ISOLATION VALVE
DURING |
| SURVEILLANCE TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 04:35 [CDT] on 06/14/2002, operators manually tripped the reactor |
| following closure of feedwater isolation valve 2C during surveillance |
| testing. The cause of the feedwater isolation valve failure is unknown at |
| this time. Also, both source range nuclear instruments failed to energize |
| following the reactor trip, but both extended range nuclear instruments are |
| available. The auxiliary feedwater system actuated as expected on steam |
| generator low-low level." |
| |
| "Did the rods fully insert? yes |
| Did steam bypass to the condenser or to atmosphere? condenser |
| Did any primary/secondary relief valves lift? no |
| Any electrical bus transfer problems? no |
| State normal operating temperature and pressure (NOT/NOP)[:] 590 degrees |
| 2235 psig |
| Any significant TS LCOs entered? no" |
| |
| The licensee stated that there was nothing unusual or misunderstood with the |
| exception of the cause of the feedwater isolation valve failure and the |
| cause of the failure of both source range nuclear instruments to energize |
| following the reactor trip. All systems functioned as required with the |
| same exceptions. |
| |
| The licensee also stated that the unit is currently stable in Mode 3 (Hot |
| Standby). Normal charging and letdown, pressurizer heaters and sprays, and |
| the reactor coolant pumps are currently being utilized for primary system |
| level, pressure, and transport control. Secondary steam is being dumped to |
| the condenser, and auxiliary feedwater is supplying water to the steam |
| generators. Operators are in the process of transferring from auxiliary |
| feedwater to main feedwater. All engineered safety feature equipment and |
| emergency core cooling systems are operable and available if needed. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * UPDATE ON 6/14/02 @ 2243 BY REDDIX TO GOULD * * * |
| |
| Licensee reported that after further investigation it was determined that |
| both source range instruments did energize as expected, however, after |
| indicating some counts erratically, they decayed away to zero. Both source |
| range detectors are inoperable at this time. |
| |
| The NRC Resident Inspector was notified. |
| |
| Notified Reg 4 RDO(Gody) |
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|Power Reactor |Event Number: 38992 |
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| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/14/2002|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 11:24[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/13/2002|
+------------------------------------------------+EVENT TIME: 11:30[EDT]|
| NRC NOTIFIED BY: DOUG RICHARDSON |LAST UPDATE DATE: 06/14/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: |JOHN DAVIDSON IAT |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| 24 HOUR REPORT ON LICENSE CONDITION 2F |
| |
| " At 1130 hours on 6/13/02 it was discovered that the Safety Relief Valve |
| (SRV) Position Indication Channel for one of the SRVs controlled from the |
| Remote Shutdown Panel was inoperable. The inoperability was due to both |
| alarm card inhibit switches for associated acoustic monitoring channel being |
| found to be in the inhibit position. These switches are normally in the |
| "alarm" position. With the switches in the "inhibit" position the SRV |
| position indication from a high vibration condition would not provide an |
| open position indication for the SRV in the Control Room or at the Remote |
| Shutdown Panel. Immediate Action was to return the switches to the alarm |
| position and all other SRV acoustic monitoring switches were verified to be |
| in the correct "alarm" position. |
| |
| "Technical Specification LCO 3.3.3.2 requires that the Remote Shutdown |
| System Functions shall be OPERABLE. With this channel inoperable, Required |
| Actions require restoration to OPERABLE status within 30 days OR placing the |
| Unit in Mode 3 within the following 12 hours. Since the potential exists |
| that this condition has existed in excess of the 30-day requirement this |
| event may be considered a Condition Prohibited by Technical Specifications. |
| |
| "This report is being made in accordance with Section 2F of Operating |
| License NPF-69 for Nine-Mile Point Unit 2. Section 2F requires that the |
| initial notification of a violation of any requirement contained in Section |
| 2C to the Operating License (License Conditions) be reported to the NRC |
| Operations Center via the Emergency Notification System within 24 hours with |
| written follow-up with 30 days. License Condition 2C requires that Nine Mile |
| Point Nuclear Station, LLC shall operate the facility in accordance with the |
| Technical Specifications." |
| |
| The NRC Resident Inspector has been notified. |
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|Power Reactor |Event Number: 38993 |
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 06/14/2002|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 17:14[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/14/2002|
+------------------------------------------------+EVENT TIME: 14:43[EDT]|
| NRC NOTIFIED BY: MAY |LAST UPDATE DATE: 06/14/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES CREED R3 |
|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
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 88 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| REACTOR MANUALLY TRIPPED FROM 88% POWER DUE TO LOSS OF THE EAST MAIN
FEED |
| PUMP ON LOW CONDENSER VACUUM |
| |
| At 1443 the unit one reactor was manually tripped from 88% reactor power due |
| to the loss of the East Main Feedwater pump on low condenser vacuum. Loss |
| of East Main Feedwater Pump Condenser Vacuum occurred during the start of |
| #13 Main Circulating Water Pump. It is believed that this was caused by |
| high differential pressure across the feed pump condenser and it appeared |
| that the circulating water pump transferred some debris from the forebay |
| into the condenser resulting in the loss of condenser vacuum, but this |
| incident is still under investigation. |
| |
| All rods fully inserted, no ECCS injection and no safety relief valves |
| lifted. |
| |
| Plant is currently stable in Mode 3. All plant equipment functioned as |
| designed. Event Investigation is currently in progress. |
| |
| The NRC Resident Inspector was notified. |
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|Power Reactor |Event Number: 38995 |
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/15/2002|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 14:54[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/15/2002|
+------------------------------------------------+EVENT TIME: 08:30[EDT]|
| NRC NOTIFIED BY: WATTS |LAST UPDATE DATE: 06/15/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KERRY LANDIS 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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| FITNESS-FOR-DUTY QUESTIONED DUE TO FAILURE OF ALCOHOL TEST |
| |
| COMPENSATORY MEASURES TAKEN |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED |
| |
| Refer to HOO for additional details |
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