Event Notification Report for November 21, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/20/2000 - 11/21/2000
** EVENT NUMBERS **
37483 37535 37536 37537 37538 37539
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37483 |
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| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 11/02/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 16:08[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 11/02/2000|
+------------------------------------------------+EVENT TIME: 12:00[CST]|
| NRC NOTIFIED BY: JIM SCHOTTEL |LAST UPDATE DATE: 11/20/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| INSTRUMENT AIR CONTAINMENT PENETRATION FAILED LEAKAGE TESTING |
| |
| "Currently Clinton is in RF-7. During performance of LLRTs of the Instrument |
| Air penetration (1 MC-057), AOV 1IA005 (outboard isolation valve) would not |
| close upon demand. The solenoid was later found to be sticking. Therefore, |
| this valve was an as-found failure. Subsequently, the testing of the inboard |
| containment isolation valve in this same penetration (1IA006), showed a |
| leakage of 27,500 sccm at the air regulator assembly. When other known |
| leakage pathways are combined with this leakage, the secondary bypass |
| leakage criteria of 0.08 La (28,883 sccm) is violated (Tech Spec Section |
| 3.6.1.3 SR 3.6.1.3.9), |
| |
| "These valves were repaired, and subsequently successfully passed their |
| LLRTs. |
| |
| "Further analysis of these failures will be performed during the |
| investigation of Condition Report 2-00-10-273." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * RETRACTION 1815 11/20/2000 FROM JEFF NADEN TAKEN BY BOB STRANSKY * * |
| * |
| |
| "Upon completion of further evaluation of the LLRT results for penetration |
| 1MC-057, it was determined that the actual leakage through this penetration |
| was approximately 751 sccm. This leakage in combination with other known |
| leakage pathways does not exceed the secondary bypass leakage criteria of |
| 0.08 La. As a result of this finding Clinton Power Station is retracting the |
| 10CFR50.72 notification made on 11/2/00." |
| |
| The NRC resident inspector has been informed of this retraction. Notified |
| R3DO (Creed). |
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|Power Reactor |Event Number: 37535 |
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| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 11/20/2000|
| UNIT: [1] [] [] STATE: CA |NOTIFICATION TIME: 07:45[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/20/2000|
+------------------------------------------------+EVENT TIME: 03:52[PST]|
| NRC NOTIFIED BY: JOY SKAGGS |LAST UPDATE DATE: 11/20/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |TOM ANDREWS R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 46 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| REACTOR TRIP - SPURIOUS RATE TRIP |
| |
| A reactor trip signal was generated from the power range neutron flux rate |
| signal. With one power range NI out of service, personnel performing |
| incore flux maps operated a test meter on another power range NI. A |
| spurious rate trip signal was generated, resulting in a 2 of 4 coincidence |
| causing a reactor trip. All equipment functioned as designed. All three |
| Auxiliary feedwater pumps started on low S/G level. All control and |
| shutdown bank control rods fully inserted. |
| |
| The licensee will inform the NRC resident inspector and the local sheriff's |
| office. |
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|Power Reactor |Event Number: 37536 |
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| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 11/20/2000|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 14:00[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/20/2000|
+------------------------------------------------+EVENT TIME: 10:28[EST]|
| NRC NOTIFIED BY: CHRISTOPHER HYNES |LAST UPDATE DATE: 11/20/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| OFFSITE NOTIFICATION DUE TO DOWNED TRANSMISSION LINE ACROSS OHIO RIVER |
| |
| "At 1028 hours on 11/20/2000, with both Beaver Valley units at full power, |
| several alarms were received at both units and control room lights |
| flickered. There were no actuations of components or electrical protection |
| devices at the site. Reports were received that an electrical power line, |
| which crosses the Ohio river, was down in the river and draped over the |
| auxiliary intake structure. This structure is located outside the Beaver |
| Valley protected area and contains emergency backup river water systems for |
| both units. There were no fires near the auxiliary intake structure. There |
| were no injuries to plant personnel. The control room also received reports |
| of a small brush fire which was caused by the downed line on the opposite |
| side of the Ohio river, which is outside the owner controlled property. |
| |
| "Operators were dispatched, and reported that the downed line is a static |
| wire from the top of a high tension tower. The static wire contacted |
| scaffolding being built at the auxiliary intake structure, causing some |
| sparking. The high voltage line has been deenergized. |
| |
| "Control room shift supervisors contacted the Beaver county Emergency |
| Management Agency to report the downed line and the fire across the river. |
| This report is submitted as a courtesy as the local emergency management |
| agency was notified. The downed line does not affect the operation to either |
| Beaver Valley unit. Offsite power sources are fully available." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
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|Fuel Cycle Facility |Event Number: 37537 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/20/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:03[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/20/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:15[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/20/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED R3 |
| DOCKET: 0707002 |DONALD COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DALE NOEL | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 4-HOUR NRC BULLETIN 91-01 REPORT |
| |
| "At 1015 hours on 11/20/00, Nuclear Criticality Safety (NCS) personnel |
| determined that NCSA-0705-076 was deficient in that it had not adequately |
| considered conditions created by a 1 1/2" dike installed in several areas of |
| the X-705 decontamination building. Holes in some dry active waste (DAW) |
| containers may allow spilled solution to be absorbed into the containers and |
| exceed the 1 1/2" favorable thickness allowed by the NCSA. DAW containers |
| were removed from the areas in question to establish compliance with the |
| double contingency principle. |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: |
| "The safety significance of this event is low because no leak of uranium |
| bearing solution has occurred. However the potential existed for absorbent |
| materials to collect an unsafe amount of material in the event of a leak |
| within a diked area. The contingency of unprotected absorbent materials was |
| analyzed to be subcritical in NCSE-0705-076 provided that a spill of an |
| unsafe amount of fissile solution does not occur. Elevating absorbent |
| materials to the wrong height represents a loss of one double contingency |
| control. |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED: |
| "For a criticality to occur, the following chain of events would be |
| required. First, a leak of an unsafe concentration or unsafe mass of uranium |
| bearing solution must occur in an Inadvertent Container Area. Secondly, the |
| area must have a dike and the solution must collect in the area to a height |
| greater than one inch (dikes are typically 1 1/2"). Third, absorbent |
| materials which are required to be covered and elevated (e.g. a DAW barrel) |
| must be present in same diked area. Fourth, the solution must absorb into |
| the materials in an amount greater than the minimum critical mass. |
| |
| "CONTROLLED PARAMETERS: |
| "The controlled parameter related to this event is geometry. Control #6 of |
| NCSA-0705-076 requires that absorbent materials protected by covering be |
| elevated above the floor by one inch. This height is insufficient if dikes |
| are present in the area. NCSA-0705-076 is deficient because it fails to |
| consider diked areas when establishing the required elevation height. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL: |
| "No leak or spill of uranium bearing material has occurred. There is no |
| estimate of how much material could have spilled in the event of a leak. |
| NCSAs for the X-705 building approve the processing of up to 100% enriched |
| material. |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: |
| "NCSA-0705-076 fails to establish the correct height for elevating absorbing |
| materials such as DAW barrels in Inadvertent Container Areas. Storage of |
| absorbent materials in accordance with control #6 will be placed on hold |
| until NCSA-0705-076 can be revised. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| At 1230 hours, barrels were removed from the areas in question and |
| compliance established." |
| |
| The NRC resident inspector has been informed of this notification. |
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|General Information or Other |Event Number: 37538 |
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| REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 11/20/2000|
|LICENSEE: ZIPPER ZEMAN ASSOCIATES |NOTIFICATION TIME: 14:07[EST]|
| CITY: LYNNWOOD REGION: 4 |EVENT DATE: 11/19/2000|
| COUNTY: STATE: WA |EVENT TIME: [PST]|
|LICENSE#: WN-I-507-1 AGREEMENT: Y |LAST UPDATE DATE: 11/20/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GAIL GOOD R4 |
| |DONALD COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TERRY FRAZZEE (via email) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT |
| |
| "This is notification of an event in Washington state as reported to the WA |
| Department of Health, Division of Radiation Protection. |
| |
| "STATUS: new |
| |
| "Licensee: Zipper Zeman Associates |
| City and state: Lynnwood, WA |
| License number: WN-I-507-1 |
| Type of license: Portable Gauge |
| |
| "Date of event: November 19, 2000 |
| Location of Event: Centralia, WA |
| |
| "ABSTRACT: An authorized user was working at a temporary job site on |
| Saturday, November 18 and stayed overnight at a local motel to continue work |
| the next day. The authorized user secured a CPN model MC-1 portable gauge, |
| serial number MD81104670, containing 10 millicuries of cesium 137 and 50 |
| millicuries of americium 241/beryllium into its locked case. The locked |
| case was then chained and locked into the canopy covered bed of a 1988 |
| Toyota four-wheel drive pick-up. The pick-up was last seen at 10 PM on |
| Saturday night. At 9 AM on Sunday, November 19, the authorized user |
| discovered that the pick-up had been stolen. The theft was reported to the |
| Centralia police, the licensee and the Department's emergency line (206 |
| NUCLEAR). As of this report (11 AM, November 20), the vehicle and gauge are |
| still missing. |
| |
| "What is the notification or reporting criteria involved? WAC 246-221-240 |
| (Reports of stolen, lost or missing radiation sources.)" |
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|Power Reactor |Event Number: 37539 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/21/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 01:12[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/20/2000|
+------------------------------------------------+EVENT TIME: 23:10[EST]|
| NRC NOTIFIED BY: MIKE RASTLEY |LAST UPDATE DATE: 11/21/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 75 Power Operation |72 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| HPCI INOPERABLE - TURBINE EXHAUST LINE FLOODED |
| |
| HPCI turbine exhaust drain pot level switch has malfunctioned. This has |
| potentially led to a condition where exhaust line from the turbine is |
| flooded. GE SIL 580 recognizes that a slug of water can create a momentary |
| high pressure and rupture both exhaust line rupture diaphragms if HPCI |
| should initiate. |
| |
| HPCI system has been declared inoperable and the licensee entered a 7 day |
| LCO. |
| |
| The NRC resident inspector has been notified. |
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