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