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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37002 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37062 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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 225�F 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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021