Event Notification Report for April 18, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/17/2000 - 04/18/2000
** EVENT NUMBERS **
36858 36897 36898 36899 36900 36901 36902
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 36858 |
+------------------------------------------------------------------------------+
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| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 04/03/2000|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 10:43[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/03/2000|
+------------------------------------------------+EVENT TIME: 08:45[CDT]|
| NRC NOTIFIED BY: STEVE GHEEN |LAST UPDATE DATE: 04/17/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| HIGH ENERGY LINE BREAK ANALYSES (HELB) REQUIRE DOORS IN AREAS CONTAINING |
| MAIN STEAM LINES NOT BE BLOCKED OR OBSTRUCTED |
| |
| "DOORS 155/177 OBSTRUCTED BY SCAFFOLDING CAUSING DOORS TO BE PARTIALLY |
| BLOCKED. DUE TO HELB CONSIDERATIONS, DOORS NEED TO BE ABLE TO SWING OPEN |
| FULLY. SCAFFOLDING WAS MOVED AT 0925 CDT." |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
| |
| * * * RETRACTED AT 1130 EDT ON 4/17/00 BY WILLIAM MATHER TO FANGIE JONES * * |
| * |
| |
| "Northern States Power Company's Nuclear Analysis Department (NAD) completed |
| calculations based on the doors being blocked and as a result of these |
| calculations is withdrawing the Event Notification #36858." The analysis |
| indicates that there is no significant effect on peak pressure during the |
| analyzed event. |
| |
| The licensee notified the NRC Resident Inspector. The NRC Operations |
| Officer notified the R3DO (Patrick Hiland). |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36897 |
+------------------------------------------------------------------------------+
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| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/17/2000|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 04:57[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 04/17/2000|
+------------------------------------------------+EVENT TIME: 02:51[EDT]|
| NRC NOTIFIED BY: JEFF GROFF |LAST UPDATE DATE: 04/17/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|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 N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CLOSURE OF A RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING OUTBOARD ISOLATION |
| VALVE RESULTING IN LOSS OF AN RHR PUMP AND SUBSEQUENT LOSS OF SHUTDOWN |
| COOLING FOR 21 MINUTES |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 0251 on 04/17/00, the E1150-F008 'RHR Shutdown Cooling (SDC) Outboard |
| Isolation Valve' closed causing the RHR 'B' pump to trip due to loss of |
| suction flow path. At the time of the trip, the RHR 'B' pump was in |
| operation for [SDC]." |
| |
| "[SDC] was restored at 0312. During the event, Unit 2 was in Mode 5 -- |
| Refueling -- with the vessel cavity flooded up to greater than 20' 6" above |
| the vessel flange with the fuel pool gates removed. No temperature rise in |
| the vessel was noted during the time SDC was out of service. No core |
| alterations were in progress at the time." |
| |
| "Prior to the closure of the E1150-F008 valve, [the] Division 2 core spray |
| system was being tagged out of service for [refueling] outage maintenance. |
| Part of the tag-out was to remove fuses for the core spray AC/DC inverter. |
| Upon removing power to the inverter, a reactor high pressure signal caused a |
| trip system B, group 4 -- Shutdown Cooling/Head Spray Isolation, which |
| closes the E1150-F008 valve. After the isolation, the core spray AC/DC |
| inverter was returned to service, the E1150-F008 valve opened, and RHR 'B' |
| pump was placed back into [the] SDC mode." |
| |
| "This event is being reported under 10CFR50.72(b)(2)(ii), any event or |
| condition that results in the manual or automatic actuation of any |
| engineered safety feature." |
| |
| The licensee notified the NRC resident inspector. |
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|Hospital |Event Number: 36898 |
+------------------------------------------------------------------------------+
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| REP ORG: COMMUNITY HOSPITAL OF LANCASTER |NOTIFICATION DATE: 04/17/2000|
|LICENSEE: COMMUNITY HOSPITAL OF LANCASTER |NOTIFICATION TIME: 09:48[EDT]|
| CITY: LANCASTER REGION: 1 |EVENT DATE: 04/16/2000|
| COUNTY: LANCASTER STATE: PA |EVENT TIME: 14:30[EDT]|
|LICENSE#: 37-12495-01 AGREEMENT: N |LAST UPDATE DATE: 04/17/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN WHITE R1 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+CHARLIE MILLER IRO |
| NRC NOTIFIED BY: MARY FEKETE | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAAA 20.1906(d) SURFACE CONT/ EXT RAD | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| RECEIPT OF A PACKAGE WITH SURFACE CONTAMINATION GREATER THAN THE 2,000 |
| DPM/100 cm� LIMIT |
| |
| On 04/16/00, a package arrived from Syncore (a pharmacy located in |
| Harrisburg, Pennsylvania), and calculations following a wipe test of the |
| package revealed surface contamination of 13,600 DPM/cm�. This was |
| discovered at 0230 on 04/16/00. The licensee reported that the package |
| contained technetium-99m and that the licensee normally receives 50 mCi in |
| each package. At the time of this event notification, the package had not |
| been opened, and there was no report of a breach. The licensee quarantined |
| the package in a storage area and notified Syncore at 0245 on 04/16/00. |
| |
| The licensee reported that the contamination is more likely to be around |
| 2,400 DPM/cm� because the efficiency of the well counter is based on cesium |
| and the isotope involved was identified to be technetium-99m. |
| |
| (Call the NRC operations officer for a licensee contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36899 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: INTERNAT. RAD & INSPECT. SVCS. INC. |NOTIFICATION DATE: 04/17/2000|
|LICENSEE: INTERNAT. RAD & INSPECT. SVCS. INC |NOTIFICATION TIME: 11:44[EDT]|
| CITY: CATOOSA REGION: 4 |EVENT DATE: 04/14/2000|
| COUNTY: STATE: OK |EVENT TIME: 11:30[CDT]|
|LICENSE#: 35-30246-01 AGREEMENT: N |LAST UPDATE DATE: 04/17/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DALE POWERS R4 |
| |BRIAN SMITH MNSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: WIELAND | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SOURCE DISCONNECT ON CAMERA OWNED BY INTERNATIONAL RADIOGRAPHY & INSPECTION |
| SERVICES INC. |
| |
| A radiography camera being used for an inspection by International |
| Radiography & Inspection Services Inc. at the Matrix Fabrication Division |
| site in Catoosa, Ok. had a source disconnect while being cranked out. The |
| source, which contained 72 curies of Iridium-192, was manufactured by AEA |
| Technologies and mounted in a SPEC camera. During the time of the source |
| disconnect, the area around the camera was secured. The licensee RSO went |
| to the site, did a source recovery and returned the camera to their |
| facility. There were no exposures >40 mrem. The licensee has packaged the |
| equipment and will FedEx it to AEA Technologies for their analysis of the |
| problem. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36900 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/17/2000|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 12:35[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 04/16/2000|
+------------------------------------------------+EVENT TIME: 12:00[EDT]|
| NRC NOTIFIED BY: STEVE MERRILL |LAST UPDATE DATE: 04/17/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN R2 |
|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 68 Power Operation |68 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING DISCOVERY OF SEA TURTLE IN PLANT INTAKE |
| CANAL |
| |
| "At approximately 12:00 on 4/16/00, a loggerhead sea turtle was recovered |
| from the plant's intake canal. The turtle was alive, but in need of |
| rehabilitation, and was subsequently sent to a facility at Sea World. As |
| required by the plant's sea turtle permit, the Florida Department of |
| Environmental Protection (DEP) was notified of the event. The notification |
| of the DEP necessitates a four (4) hour phone call to the NRC. |
| |
| "The licensee recognizes that this notification is being made outside the |
| allotted four (4) hour window. The root cause will be investigated through |
| the Condition Report process." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36901 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/17/2000|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 15:56[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/17/2000|
+------------------------------------------------+EVENT TIME: 13:09[EDT]|
| NRC NOTIFIED BY: TOM COTTER |LAST UPDATE DATE: 04/17/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN WHITE R1 |
|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 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO LOSS OF CONDENSER VACUUM |
| |
| "At 13:04 on 4/17/00, BVFS Unit 1 experienced a loss of the turbine |
| auxiliary steam header pressure. The loss of auxiliary steam pressure |
| resulted in a decrease in condenser vacuum, rapidly approaching the low-low |
| vacuum turbine trip setpoint. At 1309, the reactor was tripped manually. |
| Steam Generator 1C feed valve FCV-1FW-498 was isolated during recovery due |
| to minor leakby. Auxiliary Feedwater and all other equipment responded as |
| expected. The initial problem was caused by a failure of the auxiliary steam |
| supply pressure control valve air diaphragm packing. This valve is air to |
| open and spring operated to close. Air pressure was lost through the failed |
| packing causing the valve to fail in the closed position. Auxiliary steam |
| was restored during plant stabilization. The plant is in Hot Standby and all |
| systems are functioning properly. Heat removal is via the normal condenser |
| steam dump system." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36902 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/17/2000|
| UNIT: [] [2] [] STATE: WI |NOTIFICATION TIME: 16:02[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/17/2000|
+------------------------------------------------+EVENT TIME: 14:40[CDT]|
| NRC NOTIFIED BY: JOHN SELL |LAST UPDATE DATE: 04/17/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SOURCE RANGE NEUTRON MONITOR COULD BE AFFECTED BY 10 CFR PART 50, APPENDIX R |
| ISSUE |
| |
| "The cabling for Unit 2 source range monitor 2N-32 was found to be impacted |
| by a postulated fire in either the CCW pump room or the Unit 2 MCC room in |
| the 8' PAB. Per 10 CFR 50 Appendix R at least one nuclear instrument (2N-31, |
| 2N-32 or 2N-40) must be available to monitor source range flux while |
| shutting down the unit. [Monitor] 2N-32 is relied upon for a fire in [fire |
| zone] FZ 142 and 166 due to cable losses on the 2N-31 and 2N-40 |
| instruments. Loss of 2N-32 will cause a total loss of SR monitoring |
| capability which places the plant outside the Appendix R design basis." |
| |
| The NRC resident inspector will be informed of this notification by the |
| licensee. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021