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Event Notification Report for May 29, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           05/28/2003 - 05/29/2003



                              ** EVENT NUMBERS **



39879  39885  39886  39887  39888  



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|General Information or Other                     |Event Number:   39879       |

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| REP ORG:  MA RADIATION CONTROL PROGRAM         |NOTIFICATION DATE: 05/23/2003|

|LICENSEE:  SIPEX CORP.                          |NOTIFICATION TIME: 14:58[EDT]|

|    CITY:  Billerica                REGION:  1  |EVENT DATE:        05/15/2003|

|  COUNTY:                            STATE:  MA |EVENT TIME:        12:00[EDT]|

|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  05/23/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |ANTHONY DIMITRIADIS  R1      |

|                                                |CHARLES MILLER       NMSS    |

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

| NRC NOTIFIED BY:  JOHN SUMARES                 |                             |

|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| MISSING/LOST STATIC ELIMINATOR POLONIUM-210 SOURCE.                          |

|                                                                              |

| On May 22, 2003, the MA Radiation Control Program received a letter, dated   |

| May 16, 2003, from Sipex, Corporation, a general license holder, notifying   |

| them that Sipex Corp. was missing one Static Eliminator source.  The Static  |

| Eliminator was manufactured by NRD and it contained four Po-210 sources. The |

| Po-210 sources are located in the fitting of an air line.  On May 15, 2003   |

| the air line was relocated to a different location.  After the air line had  |

| been relocated it was discovered that one of its four Po-210 sources was     |

| missing.  Sipex Corp. believes that the source is still in the facility or   |

| it ended up in the trash.  The calculated Po-210 source strength as of May   |

| 23, 2003 is 1.6 millicuries.  The State of MA tracking number for this event |

| is 05 4172.                                                                  |

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|Power Reactor                                    |Event Number:   39885       |

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| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 05/28/2003|

|    UNIT:  [] [2] []                 STATE:  MD |NOTIFICATION TIME: 12:38[EDT]|

|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        05/28/2003|

+------------------------------------------------+EVENT TIME:        11:34[EDT]|

| NRC NOTIFIED BY:  ROBERT PACE                  |LAST UPDATE DATE:  05/28/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |LAWRENCE DOERFLEIN   R1      |

|10 CFR SECTION:                                 |                             |

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

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|                                                   |                          |

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

|                                                   |                          |

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                                   EVENT TEXT                                   

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| RPS ACTUATION                                                                |

|                                                                              |

| At 1134 EDT on 5/28/03, Calvert Cliffs Unit 2 experienced an automatic       |

| reactor trip.  The cause of the trip appears to be loss of load caused by a  |

| main turbine trip on either reverse power or overspeed.  The turbine trip    |

| may have been caused by planned troubleshooting on the turbine governor      |

| valve controls.  All control rods inserted normally on the trip.  One or     |

| both pressurizer power operated relief valves lifted and immediately         |

| re-seated following the trip.  The steam generator atmospheric valves opened |

| and immediately closed following the trip.  All Emergency Diesel Generators  |

| and ECCS systems are operable, and the licensee plans to conduct a quick     |

| trip recovery.                                                               |

|                                                                              |

| The licensee notified the NRC Resident Inspector, and the Calvert County     |

| Control Center of this event.                                                |

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|Power Reactor                                    |Event Number:   39886       |

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| FACILITY: MAINE YANKEE             REGION:  1  |NOTIFICATION DATE: 05/28/2003|

|    UNIT:  [1] [] []                 STATE:  ME |NOTIFICATION TIME: 18:44[EDT]|

|   RXTYPE: [1] CE                               |EVENT DATE:        05/24/2003|

+------------------------------------------------+EVENT TIME:        12:00[EDT]|

| NRC NOTIFIED BY:  TERRY WHITE                  |LAST UPDATE DATE:  05/28/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |LAWRENCE DOERFLEIN   R1      |

|10 CFR SECTION:                                 |                             |

|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|1     N          N       0        Decommissioned   |0        Decommissioned   |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| OFFSITE NOTIFICATION                                                         |

|                                                                              |

| On 5/24/03, Maine Yankee left an inaccurate message on their answering       |

| service that provides the public with information regarding the daily        |

| release of radioactivity from the site.  Due to the vacuum drying of spent   |

| fuel that was being transferred from the fuel pool to dry storage casks, the |

| daily gaseous release from the site on 5/24/03 was 0.1 Curies, which         |

| disagreed with the level of 0.01 Curies that was left on an information      |

| telephone recording that the public can access.  On 5/28/03, the licensee    |

| discovered this administrative error and informed the Maine Emergency        |

| Management Agency and the Maine Department of Health and Human Services.     |

|                                                                              |

| The Region 1 Duty Officer was informed of this event.                        |

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|Fuel Cycle Facility                              |Event Number:   39887       |

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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 05/28/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 23:00[EDT]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/28/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:00[CDT]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/28/2003|

|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+

|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |

|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MARK RING            R3      |

|  DOCKET:  0707001                              |MELVYN LEACH         NMSS    |

+------------------------------------------------+TIM MCGINTY          IRO     |

| NRC NOTIFIED BY:  THOMAS WHITE                 |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NBNL                     RESPONSE-BULLETIN      |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| BULLETIN 91-01 24-HOUR REPORT                                                |

|                                                                              |

| At 1100 [CDT] on 5/28/03, approximately 1/8 inch layer of water was          |

| discovered in the bottom of NAM [Negative Air Machine] 2000-4 in the C-310   |

| truck alley in violation of NCSA GEN-09. GEN-09 prohibits the use of NAMs on |

| spraying/wet operations where intake could contain droplets of moisture.     |

| This control prevents uranium from being washed off the filters into an      |

| unsafe configuration in the bottom of the NAM.                               |

|                                                                              |

| The NRC Resident Inspector has been notified of this event.                  |

|                                                                              |

| PGDP Assessment and Tracking Report No. ATR 03-1592, PGDP Event Report No.   |

| PAD-2003-012.                                                                |

|                                                                              |

| SAFETY SIGNIFICANCE OF EVENTS:                                               |

| The amount of fissile material accumulated in the bottom of the NAM, does    |

| not exceed residual quantities. This indicates, with high confidence, that   |

| less than a safe mass is present.                                            |

|                                                                              |

| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW            |

| CRITICALITY COULD OCCUR)                                                     |

| In order for a criticality to be possible, greater than a critical mass of   |

| uranium must be accumulated then become moderated.                           |

|                                                                              |

| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC)       |

| Double contingency is maintained by implementing two controls on mass.       |

|                                                                              |

| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |

| LIMIT AND % WORST CASE CRITICAL MASS):                                       |

| Less than an always safe mass of uranium.                                    |

|                                                                              |

| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |

| OF THE FAILURES OR DEFICIENCIES                                              |

|                                                                              |

| The first leg of double contingency is based on mass. NCSA GEN-09 requires   |

| that D/P measurements be performed for each NAM filter section each time the |

| machine is placed in service and immediately prior to taking the machine out |

| of service. This control provides a means for detecting material that has    |

| been removed from the filter into an unsafe geometry in the bottom of the    |

| NAM. These checks were performed; therefore, this control was not violated.  |

|                                                                              |

| The second leg of double contingency is based on mass. NCSA GEN-09 prohibits |

| the use of NAMs on spraying/wet operations where intake could contain        |

| droplets of moisture. This control prevents uranium from being washed off    |

| the filters and into an unsafe configuration in the bottom of the NAM. The   |

| control was violated since a water spray is used at the burp station to cool |

| the cylinder. However, since only a residual amount of uranium (less than an |

| always safe mass) was washed off the filter, the parameter has been          |

| maintained.                                                                  |

|                                                                              |

| Since double contingency is based on two controls on one parameter, and a    |

| control was violated, double contingency was not maintained.                 |

|                                                                              |

| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |

|                                                                              |

| 1.  Change filters according to CP4-GP-BG2108.                               |

| 2.  Decon the residual amount of uranium at the bottom of the NAM according  |

| to CP4-CU-CH2103.                                                            |

| 3.  While investigating this incident, a concern was identified as to        |

| whether or not the system configuration has been adequately analyzed for NCS |

| purposes.  The NAM shall remain out of service until the system              |

| configuration issue has been resolved, at which time the exclusion zone and  |

| postings may be removed.                                                     |

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|Power Reactor                                    |Event Number:   39888       |

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| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 05/29/2003|

|    UNIT:  [] [] [3]                 STATE:  AL |NOTIFICATION TIME: 05:43[EDT]|

|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        05/29/2003|

+------------------------------------------------+EVENT TIME:        02:39[CDT]|

| NRC NOTIFIED BY:  RAY SWAFFORD                 |LAST UPDATE DATE:  05/29/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |CAUDLE JULIAN        R2      |

|10 CFR SECTION:                                 |                             |

|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|                                                   |                          |

|                                                   |                          |

|3     N          Y       100      Power Operation  |100      Power Operation  |

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                                   EVENT TEXT                                   

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| DEGRADED ACCIDENT MITIGATION FEATURE                                         |

|                                                                              |

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

|                                                                              |

| "On 05/29/2003 at 0239 [CDT], during performance of 3-SR-3.5.1.7, HPCI [High |

| Pressure Coolant Injection] Main and Booster Pump Developed Head and         |

| Flowrate Test at Rated Reactor Pressure, following release of the HPCI Trip  |

| Push button, the HPCI Turbine Stop Valve, 3-FCV-73-18, did not return to the |

| OPEN position as required by the surveillance. The SR [Surveillance          |

| Requirement] was stopped.                                                    |

|                                                                              |

| "This is reportable as an 8 hour report in accordance with                   |

| 10CFR50.72(b)(3)(v)[(D) as 'Any event or condition that at the time of       |

| discovery could have prevented the fulfillment of the safety function of     |

| structures or systems that are needed to:  (D) Mitigate the consequences of  |

| an accident.'                                                                |

|                                                                              |

| "This is also reportable as a 60 day written report in accordance with       |

| 10CFR50.73(a)(2)(vii) as 'Any event where a single cause or condition caused |

| at least one independent train or channel to become inoperable ...in a       |

| single system designed to:  (D) Mitigate the consequence of an accident.'"   |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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