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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37536       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37537       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37538       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.)"                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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                                   
+------------------------------------------------------------------------------+
| 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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