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Event Notification Report for July 25, 2003






                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           07/24/2003 - 07/25/2003



                              ** EVENT NUMBERS **



40006  40014  40015  40016  



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|General Information or Other                     |Event Number:   40006       |

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| REP ORG:  LANG BROTHERS, Inc.                  |NOTIFICATION DATE: 07/21/2003|

|LICENSEE:  LANG BROTEHRS, Inc.                  |NOTIFICATION TIME: 09:39[EDT]|

|    CITY:  Parkersburg              REGION:  2  |EVENT DATE:        07/21/2003|

|  COUNTY:                            STATE:  WV |EVENT TIME:        07:30[EDT]|

|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  07/21/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |ANNE BOLAND          R2      |

|                                                |DOUG BROADDUS        NMSS    |

+------------------------------------------------+ROBERTA WARREN       TAT     |

| NRC NOTIFIED BY:  JACK HEFNER                  |                             |

|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| STOLEN TROXLER MOISTURE DENSITY GAUGE                                        |

|                                                                              |

| On Monday morning, July 21, 2003 around 0730 EDT it was discovered that a    |

| Troxler Model # 3440 (serial # 18908) moisture density gauge had been stolen |

| from a work site in Parkersburg, WV.  The Troxler moisture gauge had been    |

| double locked inside a cabinet.  Workers reporting to the job site had found |

| that both locks had been pried off and the moisture density gauge was        |

| missing.  The gauge was in its case. The moisture density gauge was last     |

| seen Friday evening, July 18, 2003. The moisture density gauge is owned by   |

| Lang Brothers, Inc. which is located in Bridgeport, WV.  The Radiation       |

| Safety Officer (RSO) did not have the license number of the stolen moisture  |

| density with him.  He did say that he would notify the local police that the |

| moisture density gauge had been stolen.  Troxler Model # 3440 contains 10    |

| millicuries of cesium-137 and 40 millicuries of americium-241/beryllium      |

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|Power Reactor                                    |Event Number:   40014       |

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| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 07/24/2003|

|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 09:32[EDT]|

|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        07/24/2003|

+------------------------------------------------+EVENT TIME:        05:57[EDT]|

| NRC NOTIFIED BY:  CHRIS SKINNER                |LAST UPDATE DATE:  07/24/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |DANIEL HOLODY        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       50       Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| AUTOMATIC REACTOR SCRAM DUE TO POWER SUPPLY FAILURE                          |

|                                                                              |

| "A power supply failed for three of four main steam line flow instruments    |

| for the feedwater level control system. Feedwater level control system       |

| responded to the sensed reduction in main steam flow by reducing feedwater   |

| flow.  The feedwater flow reduction resulted in the reactor recirculation    |

| system pumps downshifting to slow speed.  At 0557, the reactor protection    |

| system automatically tripped on Oscillation Power Range Monitors due to a    |

| power/flow mismatch.  The operators did not observe any power oscillations.  |

| The plant is currently stable with reactor pressure being controlled by the  |

| main steam bypass valves and reactor level is being maintained by the        |

| feedwater system. "                                                          |

|                                                                              |

| "The reason for the loss of the power supply failure is unknown at this      |

| time."                                                                       |

|                                                                              |

| Reactor power was initially at 100% when the power failure occurred. After   |

| the reactor recirculation pumps downshifted to slow speed reactor power was  |

| at 50% when the automatic reactor scram initiated.  All rods fully inserted  |

| into the core.  All emergency core cooling systems and the emergency diesel  |

| generators are fully operable if needed.                                     |

|                                                                              |

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

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|Fuel Cycle Facility                              |Event Number:   40015       |

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| FACILITY: HONEYWELL INTERNATIONAL, INC.        |NOTIFICATION DATE: 07/24/2003|

|   RXTYPE: URANIUM HEXAFLUORIDE PRODUCTION      |NOTIFICATION TIME: 15:57[EDT]|

| COMMENTS: UF6 CONVERSION (DRY PROCESS)         |EVENT DATE:        07/23/2003|

|                                                |EVENT TIME:        23:00[CDT]|

|                                                |LAST UPDATE DATE:  07/24/2003|

|    CITY:  METROPOLIS               REGION:  3  +-----------------------------+

|  COUNTY:  MASSAC                    STATE:  IL |PERSON          ORGANIZATION |

|LICENSE#:  SUB-526               AGREEMENT:  Y  |ANNE MARIE STONE     R3      |

|  DOCKET:  04003392                             |JOHN HICKEY          NMSS    |

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

| NRC NOTIFIED BY:  MICHAEL GINZEL               |                             |

|  HQ OPS OFFICER:  NATHAN SANFILIPPO            |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|JSAF 40.60(b)(2)         SAFETY EQUIPMENT FAILUR|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| LEAK IN FIRE PROTECTION SYSTEM TO HF [HEXAFLUORIDE] MITIGATION TOWERS        |

|                                                                              |

| During a training exercise at the HF mitigation towers of the Honeywell      |

| Metropolis Site, a leak was discovered in the Fire Protection System that    |

| feeds water to the towers.  The leak occurred in underground water piping    |

| between the Feeds Material building and the Fluorine Production Plant.       |

| Personnel made initial leak discovery by water coming up to the surface.     |

| The Fluorine Production Plant was not in operation at the time of the leak.  |

| Upon discovery, plant personnel isolated the leak by closing system valves.  |

| The Fluorine Production Plant has been isolated from the Fire Protection     |

| System by these closures.  Compensatory measures (fire watch, temporary      |

| piping) are in place to ensure fire protection in the Fluorine Production    |

| Plant during repair of the piping.  All safety systems for licensed material |

| at the plant fed by the Fire Protection System are still operable.           |

|                                                                              |

| The repair is estimated to take 2-3 days. There was no chemical or           |

| radiological release.  The licensee is investigating the cause of the leak.  |

|                                                                              |

|                                                                              |

| The licensee notified their NRC contact at Paducah GDP.                      |

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|Power Reactor                                    |Event Number:   40016       |

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| FACILITY: COLUMBIA GENERATING STATIREGION:  4  |NOTIFICATION DATE: 07/24/2003|

|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 17:25[EDT]|

|   RXTYPE: [2] GE-5                             |EVENT DATE:        07/08/2003|

+------------------------------------------------+EVENT TIME:        10:08[PDT]|

| NRC NOTIFIED BY:  CRAIG SLY                    |LAST UPDATE DATE:  07/24/2003|

|  HQ OPS OFFICER:  NATHAN SANFILIPPO            +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |TROY PRUETT          R4      |

|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   |

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

|2     N          Y       73       Power Operation  |73       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| REACTOR CORE ISOLATION COOLING [RCIC] RENDERED INOPERABLE DURING             |

| SURVEILLANCE TESTING                                                         |

|                                                                              |

| The following is a portion of a fax submitted by the licensee:               |

|                                                                              |

| "This ENS notification is made to report that on July 8, 2003 at 10:08 PDT   |

| Reactor Core Isolation Cooling was rendered inoperable when its inboard      |

| containment isolation valve inadvertently closed during the performance of a |

| routine surveillance procedure.  The surveillance test was discontinued and  |

| plant operators entered the appropriate Technical Specification Action       |

| Statements.  The RCIC system was restored to its normal standby lineup and   |

| declared operable within one hour.                                           |

|                                                                              |

| "Initially the event was not considered reportable to the NRC based on       |

| guidance contained in NUREG 1022, 'Event Reporting Guidelines,' and NRC      |

| Regulatory Issue Summary (RIS) 2001-14, 'Position on Reportability           |

| Requirements for Reactor Core Isolation Cooling System Failure.'  RIS        |

| 2001-14 indicates that RCIC failures are not reportable unless the RCIC      |

| system is specifically credited in the plant's Final Safety Analysis Report  |

| for mitigating the consequences of a control rod drop accident (CRDA).  The  |

| initial conclusion was that RCIC at Columbia Generating Station was          |

| mentioned but not credited in the FSAR Chapter 15 Control Rod Drop Analysis. |

| After further review, it has been decided that the current licensing basis   |

| and docketed correspondence is not clear regarding RCIC credit for CRDA      |

| mitigation.  Therefore, Columbia Generating Station has decided to           |

| conservatively report this event under 10 CFR 50.72(b)(3)(v)(D).  A          |

| follow-up LER will be issued under 10 CFR 50.73(a)(2)(v)(D)."                |

|                                                                              |

| The licensee's corrective action is under review.                            |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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