Event Notification Report for July 29, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/28/2003 - 07/29/2003 ** EVENT NUMBERS ** 40025 40028 40029 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 40025 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 07/28/2003| | UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 14:05[EDT]| | RXTYPE: [1] W-4-LP |EVENT DATE: 07/28/2003| +------------------------------------------------+EVENT TIME: 12:12[CDT]| | NRC NOTIFIED BY: DAVID LANTZ |LAST UPDATE DATE: 07/28/2003| | HQ OPS OFFICER: GERRY WAIG +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER R4 | |10 CFR SECTION: |ROBERTA WARREN DNS | |DDDD 73.71(b)(1) SAFEGUARDS REPORTS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFEGUARDS 1-HOUR REPORT | | | | The licensee discovered a vulnerability in a safeguard system that could | | allow access to a controlled access area for which compensatory measures | | have not been employed. The licensee will notify the NRC Resident Inspector. | | Contact the Headquarters Operations Officer for additional details. | | | | * * * RETRACTION ON 7/28/03 AT 1743 EDT FROM DAVID LANTZ TO GERRY WAIG * * | | * | | | | "Consistent with guidance outlined in Generic Letter 91-03, Reporting of | | Safeguards Events, this call [event] is being retracted." The licensee has | | notified the NRC Resident Inspector. | | | | Notified R4DO (Mark Shaffer), TAT (Roberta Warren). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 40028 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MFG, INC. |NOTIFICATION DATE: 07/28/2003| |LICENSEE: MFG, INC. |NOTIFICATION TIME: 18:34[EDT]| | CITY: COEUR d'ALENE REGION: 4 |EVENT DATE: 07/28/2003| | COUNTY: STATE: ID |EVENT TIME: 15:00[MDT]| |LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 07/28/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MARK SHAFFER R4 | | |JOHN GREEVES NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KEVIN YRJANA | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIALLY DAMAGED TROXLER MOISTURE DENSITY GAUGE | | | | At approximately 1500 PDT on 7/28/03 a rubber tire compactor ran over a | | Troxler Model 3440, Serial No. 31827, gauge containing an 8 millicurie | | Cs-137 and a 40 millicurie Am-241:Be source. The sources were in the safe | | position at the time the incident occurred. The licensee performed rad | | surveys and did not observe any abnormal rad readings. The manufacturer was | | contacted and requested a photograph to evaluate any potential damage. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 40029 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 07/29/2003| | UNIT: [] [] [3] STATE: AZ |NOTIFICATION TIME: 01:42[EDT]| | RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 07/28/2003| +------------------------------------------------+EVENT TIME: 18:54[MST]| | NRC NOTIFIED BY: Dan Marks |LAST UPDATE DATE: 07/29/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MARK SHAFFER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | |3 A/R Y 98 Power Operation |0 Hot Standby | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RPS ACTUATION, SPECIFIED SYSTEM ACTUATION | | | | "On July 28, 2003, at approximately 18:54 Mountain Standard Time (MST) Palo | | Verde Unit 3 experienced an automatic reactor trip on low DNBR [Departure | | from Nucleate Boiling Ratio] from approximately 98% rated thermal power due | | to reduced reactor coolant system flow when the main turbine tripped during | | a grid perturbation. Unit 3 was at normal temperature and pressure prior to | | the trip. All CEAs inserted fully into the reactor core. This was an | | uncomplicated reactor trip. No emergency classification was required per the | | Emergency Plan. No automatic ESF actuations occurred and none were required. | | The operators initiated a manual Main Steam Isolation System (MSIS) | | actuation, in accordance with the emergency operations procedures in | | response to the loss of forced reactor coolant system flow. Safety related | | buses remained energized during and following the reactor trip. The | | Emergency Diesel Generators did not start and were not required. The offsite | | power grid is stable. No significant LCOs have been entered as a result of | | this event. No major equipment was inoperable prior to the event that | | contributed to the event. | | | | "Unit 3 is stabilizing at approximately 520 degrees F and 2150 psia pressure | | in Mode 3. The reactor coolant system remains in natural circulation with | | heat removal via the atmospheric dump valves and feedwater from the | | essential auxiliary feedwater system. The event did not result in any | | challenges to fission product barriers and there were no adverse safety | | consequences as a result of this event. The event did not adversely affect | | the safe operation of the plant or the health and safety of the public. | | | | "Palo Verde Units 1 and 2 also observed the grid perturbation, but are | | continuing to operate in Mode 1 at approximately 98% rated thermal power. | | The cause of the perturbation is believed to be associated with switching in | | a nearby Hassayampa yard by Salt River Project. A fossil power plant in the | | vicinity also tripped off line during the grid perturbation event. | | | | "The [NRC] Senior Resident Inspector was informed of the Unit 3 reactor trip | | and this notification. The Senior Resident Inspector has arrived on-site to | | observe response to the reactor trip." | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021