Event Notification Report for November 12, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/08/2002 - 11/12/2002
** EVENT NUMBERS **
39289 39345 39346 39349 39352 39357 39358 39359 39360 39361 39362 39363
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39289 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ARIZONA RADIATION REGULATORY AGENCY |NOTIFICATION DATE: 10/15/2002|
|LICENSEE: CONSTRUCTION INSPECTION AND TESTING |NOTIFICATION TIME: 19:18[EDT]|
| CITY: TEMPE REGION: 4 |EVENT DATE: 10/15/2002|
| COUNTY: STATE: AZ |EVENT TIME: 15:25[MST]|
|LICENSE#: 7-98 AGREEMENT: Y |LAST UPDATE DATE: 11/08/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GREG PICK R4 |
| |M. WAYNE HODGES NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: AZ RAD REGULATORY AGENCY | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE - LOST OR STOLEN TROXLER MOISTURE DENSITY GAUGE |
| |
| "Description of event: The licensee reported the loss of a Troxler |
| moisture/density gauge sometime between 1030 and 1115 on 15 October after |
| the technician left a job site in the vicinity of Cactus and 151st Ave. The |
| gauge had been in the back of a pickup with the tailgate down. The gauge did |
| not have a handle lock. A search of his route for several hours failed to |
| turn up the gauge. The gauge is a Troxler Model 3400 series, serial number |
| 29519. It contains approximately 10 millicuries of cesium 137 and |
| approximately 50 millicuries of americium-beryllium. The company is offering |
| a $250 reward for information leading to the return of the gauge and truck. |
| |
| "The U.S. NRC, FBI, Mexico, and the states of Colorado, Nevada, Utah, New |
| Mexico and California are being informed of this incident." |
| |
| *****UPDATE ON 11/8/02 AT 14:44 FROM GODWIN TO LAURA***** |
| |
| "At approximately 10:20 AM a non-licensee reported that a gauge has been |
| turned in to 3777 E McDowell, Phoenix, AZ. Upon investigation the Agency |
| determined that the gauge was the one lost Oct. 15, 2002. The Agency leak |
| test indicated it is not leaking. The Licensee and Agency continue to |
| investigate this event. The states of CO, NV, UT, NM and CA, as well as the |
| U.S. NRC, U.S. FBI and Mexico are being notified of this recovery." |
| |
| Notified NMSS (Cool) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39345 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 11/05/2002|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 15:19[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 11/05/2002|
+------------------------------------------------+EVENT TIME: 11:10[CST]|
| NRC NOTIFIED BY: E. HENSON |LAST UPDATE DATE: 11/11/2002|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHARLES MARSCHALL R4 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEFECTIVE STEAM GENERATOR TUBES DISCOVERED DURING INSPECTION |
| |
| "During refueling outage RF12, interim results of "A" Steam Generator tube |
| inspections indicate 62 tubes out of 5431 tubes (i.e.,> 1%) have been found |
| to be defective. This steam generator tube inspection result for the "A" |
| Steam Generator is classified as category C-3 in accordance with Technical |
| Specification 5.5.9, Table 5.5.9-2. All defective tubes will be plugged |
| before the steam generator is returned to service. There were no adverse |
| safety consequences or implications as a result of this event. This event |
| did not adversely affect the safe operation of the plant or the health and |
| safety of the public." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| |
| * * * UPDATE ON 11/11/02 @ 1653 BY HENSON TO GOULD * * * |
| |
| "This initial notification was reported under 10CFR50.72(b)(3)(ii)(A) as a |
| Degraded Condition, however, under NUREG 1022, section 3.2.4, discussion (A) |
| 3, the present C-3 classification of the 'A' Steam Generator tubes does not |
| meet the listed criteria for serious steam generator tube degradation. This |
| notification is to amend initial notification, EN #39345, to reflect that |
| this report was made per requirements of Technical Specification 5.5.9, |
| Table 5.5.9-2 only. This C-3 condition does not meet the criteria for |
| serious steam generator tube degradation and thus is not a degraded or |
| unanalyzed condition." |
| |
| The Licensee will notify the NRC Resident Inspector. Notified R4DO |
| (Pruett). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39346 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 11/06/2002|
|LICENSEE: SCIENCE APPLICATIONS INTERNATIONAL CO|NOTIFICATION TIME: 00:25[EST]|
| CITY: San Diego REGION: 4 |EVENT DATE: 09/30/2002|
| COUNTY: STATE: CA |EVENT TIME: [PST]|
|LICENSE#: CA 2290-37 AGREEMENT: Y |LAST UPDATE DATE: 11/06/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES MARSCHALL R4 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT GREGER | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TWO SEALED CESIUM SOURCES INADVERTENTLY SHIPPED WITH VEHICLES |
| |
| " SAIC [Science Applications International Corp.] sold two Mobile VACIS |
| trucks to the Department of the Army-SECOM. The Mobile Vehicle and Cargo |
| Inspection System (VACIS) is a truck-mounted gamma-ray imaging system |
| designed to non-intrusively inspect the contents of trucks, containers, |
| cargo and passenger vehicles for explosive devices and/or contraband. |
| |
| "Each Mobile VACIS truck contains one 1.6 Ci Cs-137 sealed source. The |
| trucks were to be shipped first, then the Cs-137 sealed sources were to be |
| shipped later. However on September 30, 2002, the trucks were shipped with |
| the sealed sources inside by mistake without the proper DOT paperwork and |
| marking/labeling. This mistake was not discovered until November 5, 2002, |
| when SAIC prepared to ship the sources. They then discovered that the |
| sources were inside the trucks that had been shipped previously. The trucks |
| were shipped first to Houston by ground and then overseas by ocean carrier. |
| The two shipping companies involved are US Freight and Saudi Arabia |
| Shipping. SAIC has faxed all DOT shipping information to the carrier. The |
| shipment is not due to arrive in port until November 15, 2002. The company |
| plans to have a representative meet the shipment when it arrives at port. |
| |
| "According to SAIC, the sources are in type A containers that are locked. |
| SAIC has the key in their possession- without this key the sources cannot be |
| removed. The highest reading on the truck found during the package survey |
| prior to shipment was 50 microR/hour." |
| |
| The State of California has notified NRC Region 4 (Linda McLean) of this |
| event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39349 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NEW YORK STATE DEPT. OF HEALTH |NOTIFICATION DATE: 11/06/2002|
|LICENSEE: |NOTIFICATION TIME: 15:50[EST]|
| CITY: TROY REGION: 1 |EVENT DATE: 11/01/2002|
| COUNTY: STATE: NY |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 11/06/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LAWRENCE DOERFLEIN R1 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROBERT DANSEREAU (fax) | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING MEDICAL MISADMINISTRATION |
| |
| "On 11/1 /2002, the Radiation Oncologist was administering a EndoVascular |
| brachytherapy procedure to the patient using a Novoste Beta Cath source. It |
| was noticed on the image monitor by the Radiation Oncologist and the |
| Cardiologist that the distal marker began to move, raising the possibility |
| of source movement despite adequate pressure (as noted by the amber lights). |
| A decision was made by the Radiation Oncologist and the Cardiologist to |
| remove the entire system immediately. The catheter system with its transfer |
| device attached was removed and returned to the 'bailout box'. The patient |
| was surveyed right away and found to have no radioactivity. The transfer |
| device and catheter were surveyed. The sources were found within the system. |
| The sources were successfully returned to the transfer device without any |
| problem. The transfer device was visually checked and surveyed again. The |
| activity remained the same as in the pre-procedure survey. Since the source |
| could not be safely extended again, the treatment was discontinued. 71% of |
| the prescribed dose was delivered. The patient received 29% less dose than |
| prescribed: No increase in complications expected. While one cannot be fully |
| sure of the reduction in control rates, the dose delivered appears to be |
| within the range (800 cGy to 3000 cGy in the Scripps and Gamma 1 trials and |
| 13% less than the WRIST trial) to benefit in preventing restenosis. The |
| patient and the referring physician were informed was informed of this |
| event. |
| |
| |
| "Novoste Model: TDA 0040 transfer device; Ser # 83178 |
| Source strength: Source train Ser # 474/01; Source Strength 1.92 GBq |
| Source length: 40 mm |
| Diagnosis: Coronary artery restenosis |
| Prescribed treatment: 1840 cGy at 2 mm |
| Treatment site and length: RCA; 40 mm |
| Present during procedure: Cardiologist, Radiation Oncologist, Physicist, and |
| Radiation Therapy Physicist ." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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: 11/07/2002|
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39357 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: POWER RESOURCES |NOTIFICATION DATE: 11/08/2002|
|LICENSEE: POWER RESOURCES |NOTIFICATION TIME: 11:02[EST]|
| CITY: REGION: 4 |EVENT DATE: 11/07/2002|
| COUNTY: CONVERSE STATE: WY |EVENT TIME: 15:00[MST]|
|LICENSE#: SUA-1551 AGREEMENT: N |LAST UPDATE DATE: 11/08/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |TROY PRUETT R4 |
| |FRED BROWN NMSS |
+------------------------------------------------+MYRON FLIEGEL |
| NRC NOTIFIED BY: SCOTT BAKKEN | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LICENSEE REPORTED THAT A MONITORING WELL HAS BEEN PLACED ON EXCURSION |
| STATUS. |
| |
| THE LICENSEE REPORTED THAT MONITORING WELL M42 (IN "B" WELL FIELD) FOR AN |
| IN-SITU URANIUM MINE HAS BEEN PLACED IN "EXCURSION STATUS" DUE TO HIGH |
| BICARBONATE AND CONDUCTIVITY MEASUREMENTS. ON 11/07/02 THE WELL WAS |
| SAMPLED WITH THE FOLLOWING RESULTS: |
| |
| CHLORIDES 11 milligram/liter |
| BICARBONATE 375 milligram/liter |
| CONDUCTIVITY 751 micromho/centimeter |
| |
| THE MONITORING LIMITS ARE: |
| |
| CHLORIDES 11 milligram/liter |
| BICARBONATE 281 milligram/liter |
| CONDUCTIVITY 735 micromho/centimeter |
| |
| THE LICENSEE PLANS TO CONTACT THE WYOMING DEPARTMENT OF ENVIRONMENTAL |
| QUALITY, LAND QUALITY DIVISION AND NRC REGION IV REGARDING THIS EVENT. |
| |
| |
| * * * UPDATE AT 1340 ON 11/08/02 BY FUEGEL TO GOULD * * * |
| |
| It was determined that no other agencies should be notified of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39358 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 11/08/2002|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 12:30[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 11/08/2002|
+------------------------------------------------+EVENT TIME: 09:05[EST]|
| NRC NOTIFIED BY: RAY GILLOW |LAST UPDATE DATE: 11/08/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LAWRENCE DOERFLEIN R1 |
|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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TEAR IN CONTROL ROOM RETURN AIR LINE JOINT AT GINNA |
| |
| "At 0905 on 11/08/02 a tear was discovered in a flexible suction joint to |
| the Control Room Return Air Fan. This tear could allow unisolable outside |
| air to be drawn into the Control Room. A temporary repair was affected at |
| 0945 restoring the integrity of the Control Room ventilation system. An |
| investigation will be conducted to determine the cause of the tear. The NRC |
| inspector was informed." |
| |
| Additionally, the licensee indicated the tear was 6 inches in length. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39359 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39360 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 11/08/2002|
| UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 16:00[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/08/2002|
+------------------------------------------------+EVENT TIME: 06:33[PST]|
| NRC NOTIFIED BY: MICHAEL KENNEDY |LAST UPDATE DATE: 11/08/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |TROY PRUETT R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 20 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL PLANT SHUTDOWN AND MANUAL AFW INITIATION DUE TO LOSS OF CONDENSER |
| VACUUM EVENT |
| |
| "High Ocean Swells and Debris results in a manual shutdown and a Valid |
| Specific System |
| Actuation: Manual Start of Auxiliary Feedwater (AFW) pumps. |
| |
| "On November 8, 2002, at 0633 PST, with Unit 2 operating at 20 percent |
| reactor power, operators manually tripped the turbine due to indications of |
| high differential pressure on the traveling screens at the intake structure. |
| Operators also manually tripped both circulating water pumps resulting in a |
| loss of condenser. In accordance with the abnormal procedure for loss of |
| condenser, operators manually shutdown the reactor and started 2 motor |
| driven AFW pumps. The manual actuation of AFW pumps is being conservatively |
| reported as a specific system actuation per 10 CFR 50.72(b)(3)(iv). |
| |
| "Station loads transferred from auxiliary power to startup power. During the |
| transfer, several systems automatically start standby trains, including 2 |
| containment fan cooler units (CFCUs) and the standby auxiliary saltwater |
| (ASW) pump as designed. No emergency diesel generators started. No PORVs or |
| safety valves lifted. During this event, all safety systems functioned as |
| designed. |
| |
| "On November 7, 2002, operators had ramped Unit 2 power from 100 percent to |
| 20 percent power in anticipation of a significant storm and associated high |
| swells and ocean debris. The possibility of losing the circulating water |
| pumps as a result of the storm was anticipated, and procedures specify |
| maintaining reactor power at 20 percent during these conditions. Unit 2 is |
| currently stable in Mode 3 with heat being removed by AFW and atmospheric |
| steam dumps. |
| |
| "Unit 1 was unaffected by these events due to being in Mode 5 for a |
| generator rotor replacement." |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39361 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 11/11/2002|
| UNIT: [1] [] [] STATE: AZ |NOTIFICATION TIME: 04:28[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 11/10/2002|
+------------------------------------------------+EVENT TIME: 22:50[MST]|
| NRC NOTIFIED BY: RAY BUZZARD |LAST UPDATE DATE: 11/11/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |TROY PRUETT R4 |
|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 A/R Y 63 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP - RPS ACTUATION FROM LOW DNBR SIGNAL |
| |
| "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. |
| |
| "At approximately 2250 Mountain Standard Time (MST) Palo Verde Nuclear |
| Generating Station Unit 1 experienced an automatic reactor trip. The trip is |
| believed to have been caused by a control element assembly deviation that |
| resulted in the generation of a low departure from nucleate boiling (DNBR) |
| trip signal. The cause of the CEA deviation is not known at this time. At |
| the time of the trip the plant was being shutdown in a planned effort to |
| effect repairs on the A train shutdown cooling suction line that had been |
| experiencing high vibration. |
| |
| "All CEAs inserted into the core and safety systems actuated as expected. No |
| other essential safety system actuations occurred and none were required. |
| The plant did experience a loss of letdown flow when nuclear cooling water |
| to the letdown heat exchanger was sensed as being low. Letdown has been |
| restored. |
| |
| "The plant is currently operating in Mode 3, Hot Shutdown. Safety and |
| non-safety related electrical buses remained energized during and following |
| the reactor trip. The offsite power grid is stable. No major equipment was |
| inoperable prior to the event that contributed to the event." |
| |
| The licensee has notified the NRC Resident Inspector of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39362 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/11/2002|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 07:56[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/11/2002|
+------------------------------------------------+EVENT TIME: 05:15[EST]|
| NRC NOTIFIED BY: MARK GREER |LAST UPDATE DATE: 11/11/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LAWRENCE DOERFLEIN R1 |
|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 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAM - RPS ACTUATION ON HIGH REACTOR PRESSURE VESSEL PRESSURE |
| |
| "At 05:15 [EST] all main steam isolation valves isolated unexpectedly. |
| Reactor protection system actuation occurred due to high reactor pressure |
| vessel pressure. All control rods fully inserted. Reactor pressure vessel |
| pressure is being controlled using safety relief valves. Reactor pressure |
| vessel water level is being controlled using reactor core isolation cooling |
| system. Suppression pool temperature is being controlled using residual heat |
| removal system in suppression pool cooling mode. |
| |
| "Cause of the main steam isolation valve isolation is unknown. Plant |
| parameters are stable. [The licensee is] making plans to achieve cold |
| shutdown conditions." |
| |
| The licensee reported that the reactor core isolation cooling system was |
| manually initiated and that reactor vessel level decreased to level 3 during |
| the reactor scram transient. Suppression pool temperature peaked at, and is |
| being maintained steady at, 95 degrees Fahrenheit. |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39363 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 11/11/2002|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 22:08[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/11/2002|
+------------------------------------------------+EVENT TIME: 19:46[EST]|
| NRC NOTIFIED BY: MATTHEW MORGAN |LAST UPDATE DATE: 11/11/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LAWRENCE DOERFLEIN R1 |
|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 53 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO TURBINE MOTORING CONDITION ALARM |
| |
| "BVPS Unit 1 was performing a plant shutdown from full power for a scheduled |
| maintenance outage. At 1946 hours [EST], the plant was at 53% power and the |
| 'Turbine Motoring Condition' alarm was received. The condition will cause a |
| Turbine Trip if it exists for thirty seconds. A Turbine Trip will cause an |
| automatic Reactor Trip if greater than 49% reactor power. The Reactor was |
| Manually tripped and the Emergency Operating Procedure E-O was implemented. |
| The Emergency Operating Procedures were exited at 2034 hours [EST]. The |
| Auxiliary Feed Water System actuated as expected. All other systems |
| functioned as required. The cause of the Turbine Motoring alarm is under |
| investigation. The plant is currently stable in Mode 3. Shutdown to Mode 5 |
| will continue for the planned maintenance outage." |
| |
| |
| The Licensee will be notifying the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021