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Event Notification Report for August 4, 2003






                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           08/01/2003 - 08/04/2003



                              ** EVENT NUMBERS **



39915  40031  40035  40043  40044  40045  



!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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|Power Reactor                                    |Event Number:   39915       |

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| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 06/10/2003|

|    UNIT:  [1] [2] []                STATE:  NC |NOTIFICATION TIME: 17:50[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/10/2003|

+------------------------------------------------+EVENT TIME:        12:11[EDT]|

| NRC NOTIFIED BY:  RANDY TRACEY                 |LAST UPDATE DATE:  08/01/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |MARK LESSER          R2      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|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  |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| INADEQUATE I & C CABLE SEPARATION DISCOVERED DURING APPENDIX "R" REVIEW      |

|                                                                              |

| "McGuire has identified that Unit 1 and Unit 2 electrical cables associated  |

| with redundant safe shutdown trains do not meet the separation criteria of   |

| Appendix R.  Specifically, cables for all four channels of a Unit's Reactor  |

| Protection System (RPS) are routed together through the respective Unit's    |

| ETA Switchgear Room.  This room has no fire detection or suppression         |

| capabilities in the area containing the cables.  Consequently, in the event  |

| of a postulated Appendix R fire in the ETA Switchgear Room, all four         |

| channels of the respective Unit's RPS could be susceptible to fire damage.   |

| Upon discovery of this condition, a fire watch was established in the Unit 1 |

| and Unit 2 ETA Switchgear Rooms.                                             |

|                                                                              |

| "McGuire has not yet determined whether this condition would result in the   |

| loss of a safety function significantly degrading plant safety.  However,    |

| since this condition is similar to an example provided in NUREG 1022 Section |

| 3.2.4, McGuire is conservatively reporting this as an unanalyzed condition   |

| significantly degrading plant safety."                                       |

|                                                                              |

| The licensee informed the NRC resident inspector.                            |

|                                                                              |

| * * *Retraction on 08/01/03 at 1034 EDT by Tom Arlow taken by MacKinnon * *  |

| *                                                                            |

|                                                                              |

| "Subsequent evaluation has concluded that the condition identified in the    |

| event report 39915 does not significantly degrade plant safety since the     |

| affected Unit would remain capable of proceeding to a safe shutdown          |

| condition should the subject RPS trains experience fire damage.  In          |

| addition, probabilistic risk assessment of this condition determined it has  |

| low safety significance.  Therefore, McGuire is retracting Event Report      |

| 39915."  R2DO (Jim Moorman).                                                 |

|                                                                              |

| The NRC Resident Inspector was notified of this retraction by the licensee.  |

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|General Information or Other                     |Event Number:   40031       |

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| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 07/29/2003|

|LICENSEE:  H&G INSPECTION                       |NOTIFICATION TIME: 17:22[EDT]|

|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        07/25/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:        10:45[CDT]|

|LICENSE#:  L02181                AGREEMENT:  Y  |LAST UPDATE DATE:  07/29/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |CHUCK CAIN           R4      |

|                                                |DANIEL GILLEN        NMSS    |

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

| NRC NOTIFIED BY:  HELEN WATKINS                |                             |

|  HQ OPS OFFICER:  BILL GOTT                    |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| AGREEMENT STATE REPORT OF PERSONNEL OVEREXPOSURE                             |

|                                                                              |

| "A [radiography] source was not retracted to the fully shielded position     |

| resulting in a 17.978 R exposure to a radiographer and a 2.650 R exposure to |

| a trainee.  A trainer was also at the job site, but was not exposed during   |

| the event.  The radiographers were up on top of a scaffolding platform       |

| radiographing a 100 foot high vessel.  The first exposure ran for 2 minutes  |

| and the film was too light for use.  The second exposure ran for 5 minutes   |

| and the radiographer cranked the source back, but not all the way. The       |

| source remained 6-8 inches outside the shielded position.  The radiographers |

| were up on the scaffolding in an 8 foot space for about 15 minutes with the  |

| source exposed.   When the radiographers came to make a third exposure, they |

| noticed the source was out.  It took about 1 to 11/2 cranks to retract it.   |

| The crank cables were about 35 feet long and guide tubes were used.          |

|                                                                              |

| "The radiographer's ratemeter did not work and the trainee did not hear his  |

| above the excessive noise and the earplugs.  Both pocket dosimeters were off |

| scale.  The dosimeters were sent for emergency processing on Friday, July    |

| 25, 2003, to determine if an overexposure had occurred.  The exposure        |

| results were received by the Licensee on Monday, July 28, 2003.  The         |

| Licensee then reported the exposure to the Agency.  An Agency inspector made |

| a site visit to the Licensee's facility to investigate the event on July 29, |

| 2003."                                                                       |

|                                                                              |

| Equipment: SPEC 300 exposure device ser. #: 009                              |

| Source:  99 Curie cobalt-60, SPEC Model G70, ser. #: C60-02                  |

|                                                                              |

| This occurred at the Amoco Refinery in Texas City, TX.                       |

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|General Information or Other                     |Event Number:   40035       |

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| REP ORG:  MA RADIATION CONTROL PROGRAM         |NOTIFICATION DATE: 07/30/2003|

|LICENSEE:  WHEELABRATOR                         |NOTIFICATION TIME: 12:56[EDT]|

|    CITY:  DORCHESTER               REGION:  1  |EVENT DATE:        07/30/2003|

|  COUNTY:                            STATE:  MA |EVENT TIME:             [EDT]|

|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  07/30/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |JAMES NOGGLE         R1      |

|                                                |TOM ESSIG            NMSS    |

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

| NRC NOTIFIED BY:  MARIO IANNACCONE             |                             |

|  HQ OPS OFFICER:  BILL GOTT                    |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| AGREEMENT STATE REPORT ON DAMAGED GENERALLY LICENSED LEVEL GAUGE             |

|                                                                              |

| "On 7/28/03 Wheelabrator became aware that a TN [Texas Nuclear] Level Gauge, |

| Cs-137 100 mCi [milli Curie] [Model Number: 5197] SN # B728 (SS&D No.        |

| TX634D119B) had gone missing.  Plant was in shutdown and work was being      |

| performed on the associated hopper.  The gauge was removed not following     |

| standard procedure.   A search of the premises was conducted with negative   |

| results.  A consultant was hired, and located the gauge in a scrap metal     |

| pile on the morning of 7/30/03.  The shielding was partially melted away, it |

| was surmised that the gauge may have passed through the boiler. The          |

| consultant performed radiation surveys and placed the gauge in a metal       |

| container in the storage area.  The manufacturer was contacted, arrangements |

| will be made to return the gauge.                                            |

|                                                                              |

| "Cause description: Gauge removed from frame to accommodate work taking      |

| place on hopper (steel replacement).                                         |

|                                                                              |

| "Precipitating factor: Not secured in storage area; typically used a secure  |

| holding area prior to shipping/installation."                                |

|                                                                              |

| State Event Number: MA 03-0023                                               |

|                                                                              |

| Wheelabrator is located at 100 Salem Turnpike, Saugus, MA.                   |

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|Power Reactor                                    |Event Number:   40043       |

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| FACILITY: BYRON                    REGION:  3  |NOTIFICATION DATE: 08/01/2003|

|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 15:35[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        08/01/2003|

+------------------------------------------------+EVENT TIME:        11:07[CDT]|

| NRC NOTIFIED BY:  CHRIS COTE                   |LAST UPDATE DATE:  08/01/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |BRUCE BURGESS        R3      |

|10 CFR SECTION:                                 |JOE STAMBAUGH        DOE     |

|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |PO SLACH             EPA     |

|                                                |RICHARD DAVIDSON     HHS     |

|                                                |MIKE EACHES          FEMA    |

|                                                |                             |

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

|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  |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| OFFSITE NOTIFICATION DUE TO MINOR OIL SPILL                                  |

|                                                                              |

| The following information was received by the licensee via facsimile:        |

|                                                                              |

| "During the restoration of the 0A River Screen House air compressor,         |

| lubricating oil leaked internal to the compressor and was blown down to a    |

| drain trench which discharged to the Rock River.  A film or sheen of         |

| approximately 2 square feet was observed on the Rock River water surface.    |

| An estimated three cups of lubricating oil was discharged [through] the      |

| drain trench to the Rock River.  Based on this information, a notification   |

| to the Illinois Emergency Management Agency (IEMA) was performed within 15   |

| minutes, and notification to the National Response Center within 1 hour was  |

| performed.  Actions taken to stop the discharge include isolation of the air |

| compressor blowdown flowpath and placement of oil absorbent rags at the      |

| discharge location to the Rock River. The discharge of oil has been          |

| terminated."                                                                 |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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|General Information or Other                     |Event Number:   40044       |

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| REP ORG:  NATIONAL INSTITUTE OF HEALTH         |NOTIFICATION DATE: 08/01/2003|

|LICENSEE:  NATIONAL INSTITUTE OF HEALTH         |NOTIFICATION TIME: 15:46[EDT]|

|    CITY:  BALTIMORE                REGION:  1  |EVENT DATE:        06/27/2003|

|  COUNTY:                            STATE:  MD |EVENT TIME:             [EDT]|

|LICENSE#:  19-00296-10           AGREEMENT:  Y  |LAST UPDATE DATE:  08/01/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |JAMES NOGGLE         R1      |

|                                                |DANIEL GILLEN        NMSS    |

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

| NRC NOTIFIED BY:  ROBERT ZOON                  |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|BLO2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| LOST VIAL OF PHOSPHORUS-32                                                   |

|                                                                              |

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

|                                                                              |

| "This is a potential 30 day report of loss of licensed material in           |

| accordance with 10CFR20.2201(a)(ii).  I use the qualifier 'potential'        |

| because the regulation as written is confusing as to what the activity of    |

| the missing material must be to qualify as a reportable at the time of the   |

| report.  The lost material was a vial of Perkin-Elmer Easytides P-32         |

| [Phosphorus-32]-DCTP, 250 microCurie (9.25 Mbq) on the day of loss. Today,   |

| the activity would be approximately 50 microCurie, which would not be        |

| reportable under the regulation.  However, due to the confusion created by   |

| the wording of the regulation, I am conservatively reporting the event.      |

|                                                                              |

| "On July 7, 2003 the NIH Radiation Safety Branch was called by a purchasing  |

| agent at the Gerontology Research Center (GRC), Baltimore, MD to inquire as  |

| to the status of an item of radioactive material ordered in June.  The GRC   |

| is a research facility of the National Institute on Aging, part of the NIH.  |

| Our database indicated that the item in question had been received and       |

| processed in at Building 21 on the Bethesda, MD main campus on June 27, 2003 |

| and subsequently delivered to the GRC facility the afternoon of that same    |

| day.                                                                         |

|                                                                              |

| "Following the inquiry, a search for the material was conducted by the       |

| Authorized User and also, on July 8, 2003, by the Health Physicist assigned  |

| to the GRC, accompanied by one of the contract delivery technicians.  This   |

| search was exhaustive, covering every corridor in the complex as well as     |

| each lab where five other items were delivered on June 27, 2003.  The item   |

| was not discovered in inventory within any laboratory, nor in any corridor.  |

|                                                                              |

| "At this time, our conclusion is that the item was inadvertently misplaced   |

| during the delivery run of the six items that day, probably in a corridor.   |

| The container for the item was a cardboard box labeled Radioactive           |

| Material-Excepted Package-Limited Quantity of Material, UN2910. The box was  |

| likely mistaken as empty and disposed of to the refuse dumpster servicing    |

| the GRC facility on June 27, 2003.                                           |

|                                                                              |

| "The low volume comprising the Easytides product is doubly-contained within  |

| a very durable Plexiglas vial, which also serves to shield the beta          |

| emissions from the P-32. Therefore we believe it is very unlikely that       |

| anyone would have been exposed to the P-32 as a result of the disposition of |

| the vial into municipal refuse.                                              |

|                                                                              |

| "Corrective measures have been implemented with the delivery contractor to   |

| prevent the likelihood of another such loss in the future."                  |

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|Power Reactor                                    |Event Number:   40045       |

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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 08/03/2003|

|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 11:10[EDT]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        08/03/2003|

+------------------------------------------------+EVENT TIME:        04:30[EDT]|

| NRC NOTIFIED BY:  A. BARTLIK                   |LAST UPDATE DATE:  08/03/2003|

|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |JAMES NOGGLE         R1      |

|10 CFR SECTION:                                 |WILLIAM BECKNER      NRR     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|RICHARD WESSMAN      IRO     |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|ROY ZIMMERMAN        NSIR    |

|                                                |CARL PAPERIELLO      EDO     |

|                                                |BILL BORCHARDT       NRR     |

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

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

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

|2     A/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| TURBINE TRIP/REACTOR TRIP                                                    |

|                                                                              |

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

|                                                                              |

| "At 04:30 [EDT], Indian Point 2 lost all load due to an Offsite electrical   |

| disturbance.  The loss of load caused the Turbine-Generator speed to         |

| increase above 1800 RPM resulting in a "TURBINE CONTROL OIL AUTO TRIP" which |

| in turn caused a REACTOR TRIP.                                               |

|                                                                              |

| "The over frequency condition prevented the FAST TRANSFER of Bus 1, 2, 3 and |

| 4 to the Station Auxiliary Transformer, resulting in a loss of all Reactor   |

| Coolant Pumps and power to Safeguards Bus 2A and 3A.                         |

|                                                                              |

| "All Emergency Diesel Generators auto-started as required.  Power remained   |

| available to Safeguards Buses 5A and 6A from the Station Auxiliary           |

| Transformer and the EDGs did not assume load.                                |

|                                                                              |

| "Auxiliary Feedwater (AFW) Pumps 22 and 23 automatically started on low      |

| steam generator level condition.  AFW pump 21 did not start due to loss of   |

| power to bus 3A.                                                             |

|                                                                              |

| "Power was restored to bus 2A and 3A by manual closure of the output         |

| breakers of EDG 22 at approximately 4:40.                                    |

| Initial core cooling was provided by natural circulation cooling.            |

|                                                                              |

| "The Condenser remained available as a heat sink and the Steam Generator     |

| Atmospheric Relief Valves and Safety Valves remained closed.                 |

|                                                                              |

| "A Pressurizer Power Operated Relief Valve (PORV) actuated, resulting in     |

| discharge to the Pressurizer Relief Tank (PRT), which remained intact.  The  |

| Pressurizer Code Safety Valves remained closed.                              |

|                                                                              |

| "Forced RCS circulation was re-established at 05:30.  At present 3 RCPs      |

| [Reactor Coolant Pumps] have been restored to service, with actions in       |

| progress to restore the fourth RCP.                                          |

|                                                                              |

| "Currently, plant conditions [are] Hot Zero Power with preparations for unit |

| recovery in progress."                                                       |

|                                                                              |

| The electrical disturbance in the switchyard was due to electrical storms in |

| the area.  All rods inserted into the core during the trip.  The site's      |

| other nuclear unit was not affected.  All electrical feeders required by     |

| Technical Specifications are in service at this time.                        |

|                                                                              |

| Notified Region 1 PAO (Neil Sheehan) & Headquarters PAO (Beth Hayden). & EDO |

| Office (Ho Nieh).                                                            |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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