The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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

|Power Reactor                                    |Event Number:   39915       |

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

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

| 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  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| 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.  |

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



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

|General Information or Other                     |Event Number:   40031       |

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

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

| 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        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| 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.                       |

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



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

|General Information or Other                     |Event Number:   40035       |

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

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

| 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        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| 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.                   |

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



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

|Power Reactor                                    |Event Number:   40043       |

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

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

| 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  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| 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.                        |

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



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

|General Information or Other                     |Event Number:   40044       |

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

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

| 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    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| 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."                  |

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



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

|Power Reactor                                    |Event Number:   40045       |

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

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

| 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      |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| 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.                        |

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



                    

Page Last Reviewed/Updated Thursday, March 25, 2021