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Event Notification Report for June 2, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           05/30/2003 - 06/02/2003



                              ** EVENT NUMBERS **



39883  39884  39891  39893  39894  39895  39896  39897  39898  



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|General Information or Other                     |Event Number:   39883       |

+------------------------------------------------------------------------------+

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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 05/27/2003|

|LICENSEE:  GUIDANT CORPORATION                  |NOTIFICATION TIME: 10:17[EDT]|

|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        05/23/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:        15:50[CDT]|

|LICENSE#:  L05178-000            AGREEMENT:  Y  |LAST UPDATE DATE:  05/27/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |WILLIAM JONES        R4      |

|                                                |LAWRENCE DOERFLEIN   R1      |

+------------------------------------------------+TOM ESSIG            NMSS    |

| NRC NOTIFIED BY:  OGDEN                        |                             |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| MALFUNCTION OF A HIGH DOSE RATE AFTERLOADER                                  |

|                                                                              |

| During a heart procedure at the Union Memorial Hospital in Maryland with a   |

| Galileo III (HDR - High dose rate afterloader) device using a Phosphorus -   |

| 32 source wire, of up to 600 millicuries, a malfunction occurred with the    |

| active wire in place in the patient's heart.  When the source was to be      |

| retracted the source would not retract.  The physician utilized the machine  |

| interrupt to try to get the source to move to the shielded position and it   |

| failed.  The physician then pushed the system STOP button to get the source  |

| to retract and it also failed to perform the retraction.  The physician then |

| moved to the hand-wheel to retract the source, but this function also        |

| malfunctioned.  At this point the physician pulled the entire catheter and   |

| dropped it to the Operating Room floor.   The power cord was then removed    |

| from the wall receptacle depriving the machine of power and then the source  |

| retracted to the fully shielded position.  The licensee was informed that    |

| this would constitute a Therapy Event within the State of Texas and the      |

| state would need a complete report and an emergency read of all badged       |

| personnel in the OR during the procedure.   The Licensee responded that the  |

| machine was not within the State of Texas.   A report to the state of Texas  |

| is still required by License Condition # 16 due to failure of the drive      |

| mechanism of the GALILEO III to retract the source to safe storage until the |

| fourth emergency procedure was performed.                                    |

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|General Information or Other                     |Event Number:   39884       |

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| REP ORG:  NEW MEXICO RAD CONTROL PROGRAM       |NOTIFICATION DATE: 05/27/2003|

|LICENSEE:  SPECTRATEK SERVICES                  |NOTIFICATION TIME: 12:49[EDT]|

|    CITY:  ALBUQUERQUE              REGION:  4  |EVENT DATE:        05/23/2003|

|  COUNTY:                            STATE:  NM |EVENT TIME:        16:30[MDT]|

|LICENSE#:  TA-172-21             AGREEMENT:  Y  |LAST UPDATE DATE:  05/27/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |WILLIAM JONES        R4      |

|                                                |DOUG BROADDUS        NMSS    |

+------------------------------------------------+CAUDLE JULIAN        R2      |

| NRC NOTIFIED BY:  WILLIAM FLOYD                |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| AGREEMENT STATE REPORT                                                       |

|                                                                              |

| On 5/22/2003, the licensee sent a shipment of radioactive material to Elite  |

| Airfreight in Houston, TX.  On 5/23/2003 at approximately 1630 MDT, Elite    |

| Airfreight contacted the licensee to inform them that only 2 of the 3 boxes  |

| of radioactive material in the shipment had arrived in Houston.  The         |

| licensee contacted Federal Express, who tracked the missing package to the   |

| Fedex facility in Memphis, TN.  Fedex planned to send the missing package to |

| Houston on 5/24/2003.  As of 5/27/2003, the package still had not arrived in |

| Houston.  The licensee contacted Fedex again, and was told the package was   |

| still in Memphis, and would be shipped to Houston today (5/27/2003).         |

|                                                                              |

| The missing package is a 12X12X12 inch fiberboard box containing 40          |

| millicuries of Antimony-124, and has a Transportation Index of 4.  This      |

| event is state of New Mexico event number NM03-02.                           |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39891       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 05/30/2003|

|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 00:43[EDT]|

|   RXTYPE: [1] CE                               |EVENT DATE:        05/29/2003|

+------------------------------------------------+EVENT TIME:        21:18[CDT]|

| NRC NOTIFIED BY:  DON KURTTI                   |LAST UPDATE DATE:  05/30/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |KRISS KENNEDY        R4      |

|10 CFR SECTION:                                 |                             |

|NONR                     OTHER UNSPEC REQMNT    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| 161 KV WAS DECLARED INOPERABLE DUE TO THE PREDICTED POST TRIP VOLTAGE BELOW  |

| SETPOINT                                                                     |

|                                                                              |

| The following information was obtained from the licensee via facsimile:      |

|                                                                              |

| " [Abnormal Operating Procedure] AOP-31 '161KV GRID MALFUNCTIONS' was        |

| entered due to the predicted post trip 161 KV voltage dropping to 160.6 KV   |

| on the PCMMINT [Personal Computer Monitoring of Missouri, Iowa and Nebraska  |

| Transmission] computer monitoring program.  161 KV was declared inoperable   |

| due to the predicted post trip voltage being below the 160.7 KV setpoint.    |

| Tech Spec 2.7(2)C, 72 hour LCO was entered.  Both emergency diesel           |

| generators are operable.                                                     |

|                                                                              |

| "Main generator VARS [Volt-Amperes Reactive] were raised from 100 to 150     |

| MVARS lagging in an attempt to raise predicted post trip voltage.  Predicted |

| voltage rose above 161 KV for approx. 5 minutes and then lowered below 161   |

| KV again to 160.8 KV and is now fluctuating.  System Operations was notified |

| and stated that 161 KV actual voltage remained at approx. 164 KV and that    |

| the electrical grid was stable.                                              |

|                                                                              |

| "Design Engineering was notified and hypothesizes that MAPP [Mid-America     |

| Power Pool] values into PCMMINT program may not be valid and that they will  |

| attempt to validate the inputs."                                             |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39893       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 05/30/2003|

|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 15:21[EDT]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/30/2003|

+------------------------------------------------+EVENT TIME:        13:30[CDT]|

| NRC NOTIFIED BY:  EDWARD HARRISON              |LAST UPDATE DATE:  05/30/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK RING            R3      |

|10 CFR SECTION:                                 |                             |

|NONR                     OTHER UNSPEC REQMNT    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       93       Power Operation  |93       Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| RECEIPT OF CONTAMINATED MATERIAL IN EXCESSOF 10 CFR 71.87 LIMITS             |

|                                                                              |

| "On May 30, 2003 at 1330 CDT Duane Arnold Energy Center (DAEC) confirmed     |

| receipt of a material shipment with removable surface contamination that     |

| exceeded the limits of 10 CFR 71.87 (20.1906 d.1) of 22,000 dpm/100 square   |

| cm. The shipment, a transfer cask intended for future dry storage, had       |

| 23,496 dpm/100 square cm of non-fixed external contamination. The            |

| contamination was found upon receipt of the cask during routine receipt      |

| surveys. This shipment was a surface contaminated object (SCO), with less    |

| than type A quantity of radioactive material."                               |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39894       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 05/30/2003|

|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 16:54[EDT]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/30/2003|

+------------------------------------------------+EVENT TIME:        08:30[EDT]|

| NRC NOTIFIED BY:  KEN ROBINSON                 |LAST UPDATE DATE:  05/30/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |LAWRENCE DOERFLEIN   R1      |

|10 CFR SECTION:                                 |                             |

|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       99       Power Operation  |99       Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| SECURITY GUARD POSTED WITHOUT PROPER EQUIPMENT                               |

|                                                                              |

| A plant security officer was stationed at a security post without all        |

| equipment required to properly man that post. Immediate compensatory         |

| measures were taken upon discovery. The licensee notified the NRC Resident   |

| Inspector. Refer to the Headquarters Operations Officer Log for additional   |

| details.                                                                     |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39895       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 05/30/2003|

|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 22:36[EDT]|

|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        05/30/2003|

+------------------------------------------------+EVENT TIME:        18:55[CDT]|

| NRC NOTIFIED BY:  DAVE DEES                    |LAST UPDATE DATE:  05/30/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |KRISS KENNEDY        R4      |

|10 CFR SECTION:                                 |                             |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| LOSS OF OFF-SITE EMERGENCY NOTIFICATION SIRENS AT WOLF CREEK                 |

|                                                                              |

| "At 1755 CST 5/30/2003 power was lost to the Otter Creek and Jacobs Creek    |

| Emergency Notification sirens. Lake Siren #2 has been out of service since   |

| 5/28/2003 due to lightning damage. Station procedures consider the loss of   |

| three or more Emergency Notification Sirens for greater than one hour a      |

| major loss of emergency assessment capability reportable under               |

| 50.72(b)(3)(xiii).                                                           |

|                                                                              |

| "At 2108 CST station monitoring equipment indicated that power had been      |

| restored to the Otter Creek and Jacobs Creek Sirens."                        |

|                                                                              |

| The licensee has notified the NRC Resident Inspector and local authorities.  |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39896       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 05/31/2003|

|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 01:07[EDT]|

|   RXTYPE: [1] GE-6                             |EVENT DATE:        05/30/2003|

+------------------------------------------------+EVENT TIME:        22:00[CDT]|

| NRC NOTIFIED BY:  KEN LEFFEL                   |LAST UPDATE DATE:  05/31/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK RING            R3      |

|10 CFR SECTION:                                 |                             |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       92       Power Operation  |92       Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| LOSS OF COMMUNICATION DUE TO UNAVAILABILITY OF SIRENS                        |

|                                                                              |

| "At about 2200 [CDT] on 5/30/03, greater than 25% of the CPS [Clinton Power  |

| Station] notification sirens became unavailable due to a loss of AC power.   |

| Fourteen sirens are unavailable at this time [due to inclement weather],     |

| eleven constitutes 25% lost for greater than one hour."                      |

|                                                                              |

| The licensee has notified the State Police, will notify the NRC Resident     |

| Inspector and is in the process of restoring availability of the inoperable  |

| sirens.                                                                      |

|                                                                              |

| *** UPDATE AT 0555 EDT ON 5/31/03 FROM KEN LEFFEL TO ARLON COSTA ***         |

|                                                                              |

| Availability was restored to all sirens, except four.  The licensee will     |

| notify the NRC Resident Inspector.                                           |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Fuel Cycle Facility                              |Event Number:   39897       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: WESTINGHOUSE HEMATITE                |NOTIFICATION DATE: 05/31/2003|

|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 13:40[EDT]|

| COMMENTS: LEU CONVERSION (UF6 to UO2)          |EVENT DATE:        05/28/2003|

|           COMMERCIAL LWR FUEL                  |EVENT TIME:        16:30[CDT]|

|                                                |LAST UPDATE DATE:  05/31/2003|

|    CITY:  HEMATITE                 REGION:  3  +-----------------------------+

|  COUNTY:  JEFFERSON                 STATE:  MO |PERSON          ORGANIZATION |

|LICENSE#:  SNM-33                AGREEMENT:  N  |MARK RING            R3      |

|  DOCKET:  07000036                             |MELVYN LEACH         NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  KEVIN HAYES                  |                             |

|  HQ OPS OFFICER:  GERRY WAIG                   |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NBNL                     RESPONSE-BULLETIN      |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| NRC BULLETIN 91-01, 4 HOUR REPORT                                            |

|                                                                              |

| The following is taken from a facsimile report from the licensee to the NRC  |

| Operations Center.                                                           |

|                                                                              |

| "Short Description/Event Title: Enriched uranium rods mixed with Maine       |

| Yankee boron carbide poison rods.                                            |

|                                                                              |

| "Consequences - details: This material was always within our control. The    |

| identification and tracking of the material was deficient. Additionally, the |

| necessary controlled parameters to assure nuclear safety were not            |

| established or maintained for the specific location and configuration in     |

| which the rods were stored.                                                  |

|                                                                              |

| "Immediate action taken: Rod downloading personnel were instructed to obtain |

| the pin-stamped number from each rod that is determined to contain uranium,  |

| which will aid subsequent investigation. The remaining rods in the storage   |

| box were evaluated for extent of condition, and the potentially containing   |

| uranium have been segregated to an approved location to further ensure their |

| favorable configuration. Key personnel at Hematite and Columbia were also    |

| informed of the issue.                                                       |

|                                                                              |

| "Full Description: Three uranium-bearing fuel rods were identified at        |

| approximately 1630 hours on May 28, 2003 as part of a zircaloy scrap         |

| recovery project. The scrap recovery effort is being conducted inside the    |

| rod loading room of Building 230, and involves tubing from a Maine Yankee    |

| fuel fabrication campaign conducted by the previous owner, ABB, in 1997. The |

| fuel was never shipped to Maine Yankee due to that plant's subsequent        |

| shutdown. The fuel rods were opened by ABB, and the enriched uranium pellets |

| were recovered during the first quarter of 1998. The boron carbide (B4C)     |

| poison rods were not opened at that time. The B4C rods are now being         |

| downloaded by a Westinghouse sub-contractor for recovery of the zircaloy     |

| cladding. When opened, three rods from the last box to be downloaded were    |

| found to contain uranium pellets rather than B4C, Because of the potential   |

| of finding at least some pellets, all operations were being conducted under  |

| appropriate radiological controls. An additional 21 rods from that last box  |

| that have been identified as suspect due to their weight difference. They    |

| have been put aside at an approved location, but not yet opened for          |

| verification.                                                                |

|                                                                              |

| "Additionally, a separate box of rods containing what appears to be depleted |

| uranium were also identified about two weeks ago. The preliminary            |

| determination of the contents being depleted uranium is based on their       |

| physical characteristics and markings. These rods are still under            |

| investigation to confirm that they contain depleted uranium.                 |

| During the period of storage, this material was stored in the warehouse      |

| portion of Building 230, which is located within the fenced and protected    |

| area of the site. This material was always within our control, but the       |

| identification and tracking of the material was deficient. In response to    |

| this issue the following actions have been taken:                            |

|                                                                              |

| "A review of the reporting requirements of 10 CFR Parts 70.50, 74.11, 73.71  |

| and Appendix G of Part 73 established that this issue does not meet the      |

| requirements for formal reporting. Nevertheless, a courtesy call was placed  |

| this afternoon to the D&D Project Manager at NRC Region III. A high level    |

| CAPS item, has been established for tracking of all actions taken regarding  |

| this matter. A Root Cause Analysis will also be conducted. Consideration was |

| given to whether this issue should be treated as an extension of the Kardex  |

| issue that was the subject of a separate report, but it appears that it      |

| would be appropriate to treat this matter separately due to the differing    |

| circumstances. Arrangements have been made to have an independent review     |

| conducted at the site to determine if additional measures should be taken in |

| locating material. This is expected to occur next week.                      |

|                                                                              |

| "Plant management initially assessed this situation as unreportable to the   |

| NRC for material control aspects as noted above. It was also assessed as not |

| reportable under NRC Bulletin 91-01, Supplement 1, 'Reporting Loss of        |

| Criticality Safety Controls,' because of the following criticality safety    |

| aspects:                                                                     |

|                                                                              |

| "The as-found condition was bounded by existing analysis for rod channel     |

| boxes formerly used in the manufacture of fuel rods; The as-found condition  |

| was safe due to the extensive amount of absorber, in the form of B4C rods,   |

| surrounding the uranium rods; The as-found condition was safe due to the     |

| inability for introducing moderator because a lid was secured on the storage |

| box. The box was stored on a cantilever rack that further precluded the      |

| possibility of flooding.                                                     |

|                                                                              |

| "Nevertheless, a courtesy call was placed within 24-hours of discovery to    |

| the facility's Project Manager at NRC Region III. Further review has         |

| determined that the as-found condition was not bounded by the rod channel    |

| box analysis, but is bounded by fuel assembly analyses. Additionally, the    |

| situation is now assessed as reportable under Bulletin 91-01 because the     |

| necessary controlled parameters to assure nuclear safety were not            |

| established or maintained for the specific location and configuration in     |

| which the rods were stored. A formal 91-01 report, Number 39897, has         |

| therefore been made to the facility's NRC Project Manager and the NRC        |

| Operations Center."                                                          |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39898       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 06/01/2003|

|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 11:00[EDT]|

|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/01/2003|

+------------------------------------------------+EVENT TIME:        08:50[EDT]|

| NRC NOTIFIED BY:  MCDONNELL                    |LAST UPDATE DATE:  06/01/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |LAWRENCE DOERFLEIN   R1      |

|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   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     A/R        Y       98       Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| REACTOR SCRAM FROM 98% POWER DUE TO LOAD REJECTION                           |

|                                                                              |

| "At 0850 EST [6/1/03] Pilgrim Station received a full reactor scram from     |

| 98.5% power from the Main Generator lockout relay tripping.  The Main        |

| Generator lockout relay caused both 345 KV output breakers to open and       |

| caused a load reject scram.                                                  |

|                                                                              |

| "All systems operated  as designed.  Received expected alarms and isolations |

| [as follows]: Group 2 C PCIS, Primary Containment Isolations, Reactor        |

| Building isolation, Group 6 (Reactor Water clean up isolation).  Isolations  |

| [were] due to normal post scram level shrink to +2 inches.  Isolations occur |

| at +12.                                                                      |

|                                                                              |

| "Preliminary indications are a fault on Unit Aux. Transformer."              |

|                                                                              |

| All control rods fully inserted.  There was no ECCS actuation and the lifted |

| Safety Relief valves seated properly.  The unit is currently stable in the   |

| hot standby mode of operation.                                               |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

+------------------------------------------------------------------------------+