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Event Notification Report for June 7, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/06/2000 - 06/07/2000

                              ** EVENT NUMBERS **

37002  37060  37061  37062  37063  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37002       |
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| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 05/15/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 11:47[EDT]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        05/15/2000|
+------------------------------------------------+EVENT TIME:        04:48[PDT]|
| NRC NOTIFIED BY:  J.W. GASTON                  |LAST UPDATE DATE:  06/06/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       62       Power Operation  |62       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| OUTBOARD MAIN STEAM ISOLATION (MSIV) VALVE FOUND CLOSED.                     |
|                                                                              |
| At 0448 PDT on 05/15/00, the outboard main steam isolation valve #           |
| MSIV-V-28A was found in the closed position (green indicating light on).     |
| Follow-up verification of the 'A' main steam line flow (0%) and the plant    |
| computer valve position verified that the valve was closed.  The plant       |
| computer indicated that the valve closed at 0254 PDT and it was discovered   |
| closed at 0448 PDT.  No work was being performed on the main steam system or |
| in the area of the main steam system when the valve closed.  The plant       |
| computer indicated that the valve had fast closed.  The plant entered the    |
| Limiting Condition of Operation for Primary Containment Isolation Valve and  |
| placed the control switch for the MSIV in the closed position.  There was no |
| valid ESF Actuation signal that caused the valve closure.  The plant was     |
| operating at 62% power and did not experience a transient as a result of the |
| MSIV closure (no flux tilt).  Licensee investigation into the cause of the   |
| closure is continuing.                                                       |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * *  UPDATE ON 6/6/00 @ 1155 BY MCBRIDE TO GOULD * * *  RETRACTION         |
|                                                                              |
| The event notification report associated with the above event is hereby      |
| retracted. The event and conditions associated with the event do not meet    |
| NUREG 1022, Rev. 1, reporting criteria. Only a single component, MSIV-V-28A, |
| actuated (closed). The single component (MSIV) is not sufficient to mitigate |
| the consequences of single events. There was not a manual or automatic ESE   |
| system actuation. An ESF signal (valid or invalid) was not generated.        |
| Therefore, in accordance with the statements of considerations for NUREG     |
| 1022, Rev. 1,( 10CFR50.72(b)(2)(ii), there was not a sufficient number of    |
| channels (zero) in a multichannel ESF actuation system to meet the           |
| definition of actuation of enough channels to complete the minimum actuation |
| logic for a train or the system. For these reasons, this event does not meet |
| the reporting criteria of 10CFR50.72(b)(2)(ii) and is hereby retracted.      |
|                                                                              |
| The NRC Resident Inspector was notified.     The Reg 4 RDO (Pellet) was      |
| notified.                                                                    |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37060       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 06/06/2000|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 06:02[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/06/2000|
+------------------------------------------------+EVENT TIME:        02:36[CDT]|
| NRC NOTIFIED BY:  JOHN VAN SICKEL              |LAST UPDATE DATE:  06/06/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECONDARY CONTAINMENT DECLARED INOPERABLE DUE TO LOSS OF WATER SEAL CAUSED   |
| BY PIPE CORROSION                                                            |
|                                                                              |
| "A 4 inch diameter floor drain outlet pipe inside the Standby Gas Treatment  |
| Sump was identified by Operating personnel to be corroded through near the   |
| wall of the sump. This piping is designed to act as a Secondary Containment  |
| boundary which is used to form a loop seal between the Reactor Building and  |
| the SBGT room. Normally, the piping would come out from the wall and make a  |
| 90 degree turn to near the bottom of the sump, and open under water.         |
| However, with the erosion occurring near the wall of the sump, a breech of   |
| secondary containment exists. Due to the amount of corrosion, the opening    |
| was estimated to be 12.57 square inches. Additionally, damaged seals on two  |
| other doors (#225 and #128) located on airlocks associated with Secondary    |
| Containment accounted for another 7 square inches, for a total of 19.57      |
| square inches. Openings in excess of 12.7 square inches in this              |
| configuration have not been tested/evaluated. Therefore, Secondary           |
| Containment was considered inoperable. Operations entered Technical          |
| Specification LCO 3.6.4.1, condition A, for Secondary Containment inoperable |
| in Mode 1 at 0236[CDT]. Required action A.1 is to restore Secondary          |
| Containment to operable status in 4 hours.                                   |
|                                                                              |
| "Operations took actions to prohibit access through the two seal damaged     |
| doors/airlocks by posting them to prevent access. Once administrative        |
| control of the doors was established, the known opening in secondary         |
| containment was reduced to the corroded pipe in the SBGT sump, or 12.57      |
| square inches. This is less than the 12.7 square inches allowed. Technical   |
| Specification LCO 3.6.4.1, condition A, was exited at 0258[CDT]."            |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37061       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 06/06/2000|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 12:47[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/06/2000|
+------------------------------------------------+EVENT TIME:        10:20[EDT]|
| NRC NOTIFIED BY:  DENNIS MAY                   |LAST UPDATE DATE:  06/06/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM MOSLAK           R1      |
|10 CFR SECTION:                                 |                             |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE            |
|                                                                              |
| After completion of HPCI pump surveillance testing, a check for freedom of   |
| movement and proper reset action of the overspeed trip tappet was performed. |
| As a result of this check, an adjustment was found to be necessary for the   |
| turbine stop valve reset time.  Attempts to make this adjustment resulted in |
| inoperability of the reset function of the overspeed trip.  HPCI was         |
| declared inoperable and Technical Specification limiting condition for       |
| operation 3.5E(3) was entered.  HPCI will still start if called upon but if  |
| it trips on overspeed HPCI will become inoperable.                           |
|                                                                              |
| Reactor Core Isolation Cooling, Emergency Diesel Generators, and all other   |
| Emergency Core Cooling Systems are fully operable if needed.  The electrical |
| grid is stabile.                                                             |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37062       |
+------------------------------------------------------------------------------+
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| REP ORG:  SOUTH COAST MEDICAL CENTER           |NOTIFICATION DATE: 06/06/2000|
|LICENSEE:  SOUTH COAST MEDICAL CENTER           |NOTIFICATION TIME: 19:04[EDT]|
|    CITY:  LAGUNA BEACH             REGION:  4  |EVENT DATE:        06/06/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:        14:30[PDT]|
|LICENSE#:  0920-30               AGREEMENT:  Y  |LAST UPDATE DATE:  06/06/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |WILLIAM BRACH        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOSE BRUNO                   |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAAA 20.1906(d)           SURFACE CONT/ EXT RAD |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| WIPE TEST OF PACKAGE EXTERIOR RESULTED IN A COUNT LEVEL OF 4442 DPM          |
|                                                                              |
| A package containing technetium - 99m (NaTcO4) delivered by NYCOMED Amersham |
| to South Coast Medical Center was found to have surface contamination level  |
| above the 22 DPM per square centimeter limit.  The wipe of the outer surface |
| of the package (metal canister) was placed in a well counter and the counter |
| indicated the that total count on the  wipe was 4442 +/-149 DPM.  The outer  |
| dimensions of the metal canister are 15 centimeters by 25 centimeters by 29  |
| centimeters. The licensee will contact NYCOMED Amersham located in Anaheim,  |
| CA, and ask them to pickup the package.  The package was not opened.         |
| Activity of the technetium-99m (NaTcO4) was originally 25 millicuries and    |
| the quantity is 2.4838 milliliters.                                          |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37063       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 06/07/2000|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 01:32[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        06/06/2000|
+------------------------------------------------+EVENT TIME:        23:10[CDT]|
| NRC NOTIFIED BY:  RUITER                       |LAST UPDATE DATE:  06/07/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       35       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT HAD A MANUAL REACTOR TRIP FROM 35% POWER.                              |
|                                                                              |
| At 2243 on 06/06/2000 an alarm for high reactor coolant pump "A" bearing     |
| water temperature came in on the plant process computer.  At 2310 the        |
| reactor coolant pump "A" bearing water temperature exceeded 225F and a      |
| manual reactor trip was initiated and the "A" reactor coolant pump was       |
| secured.  Following the reactor trip all three auxiliary feed water pumps    |
| started and equipment response was as expected.  All rods fully inserted and |
| no safety relief valves lifted.  Currently the turbine driven aux feed is    |
| secured, but the motor driven aux feed is still operating.  They are         |
| investigating if the cause was a temperature indicating problem or a bearing |
| failure.                                                                     |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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