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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.                   |
+------------------------------------------------------------------------------+