Event Notification Report for February 11, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/08/2002 - 02/11/2002
** EVENT NUMBERS **
38676 38679 38683 38684 38685 38686 38687
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
Power Reactor Event Number: 38676
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FACILITY: LIMERICK REGION: 1 NOTIFICATION DATE: 02/06/2002
UNIT: [1] [] [] STATE: PA NOTIFICATION TIME: 22:37[EST]
RXTYPE: [1] GE-4,[2] GE-4 EVENT DATE: 02/06/2002
NRC NOTIFIED BY: PETE ORPHANOS LAST UPDATE DATE: 02/08/2002
EMERGENCY CLASS: NON EMERGENCY LAWRENCE DOERFLEIN R1
10 CFR SECTION:
AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION
UNIT SCRAM CODERX CRITINIT PWR INIT RX MODE CURR PWR CURR RX MODE
1 N Y 94 Power Operation 94 Power Operation
EVENT TEXT
HPCI DECLARED INOPERABLE
"During the completion of scheduled testing on the Unit 1 High Pressure
Coolant injection (HPCI) system, a valve designed to provide minimum flow
protection for the associated pump did not automatically open in the time
frame expected during pump shutdown. The valve did respond correctly to
Operator action.
"HPCI was declared inoperable as of 1722 hours on February 6th, 2002.
Troubleshooting on the minimum flow protection circuitry is currently in
progress.
"This report is being made in pursuant to 10CFR50.72(b)(3)(V)(D) for failure
of a single train accident mitigation system."
The NRC resident inspector has been informed of this event by the licensee.
* * * UPDATE 1508EST ON 2/8/02 FROM STAN GAMBLE TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"This is a retraction of the event notification made on 2/6/02 at 22:37
hours. This event (#38676) was initially reported as a safety system
functional failure under the requirement of 10CFR50.72(b)(3)(v)(D), after
the Unit 1 High Pressure Coolant Injection (HPCI) minimum flow valve did not
automatically open during system testing.
"Subsequent testing verified that the valve would have opened automatically
without operator action following the low flow alarm actuation. A delay in
response is expected when system flow is reduced to a value within the range
of the flow transmitter. This delay in response, and the short duration of
pump operation at a no flow condition is not detrimental to the HPCI pump.
"The system response was verified to be as designed considering the test
conditions. A condition did not exist at the time of discovery that could
have prevented the fulfillment of the safety function."
The licensee informed the NRC Resident Inspector. Notified R1DO(Doerflein).
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
Power Reactor Event Number: 38679
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FACILITY: FITZPATRICK REGION: 1 NOTIFICATION DATE: 02/07/2002
UNIT: [1] [] [] STATE: NY NOTIFICATION TIME: 14:26[EST]
RXTYPE: [1] GE-4 EVENT DATE: 02/07/2002
NRC NOTIFIED BY: SHAWN ALLEN LAST UPDATE DATE: 02/08/2002
EMERGENCY CLASS: NON EMERGENCY LAWRENCE DOERFLEIN R1
10 CFR SECTION:
AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION
UNIT SCRAM CODERX CRITINIT PWR INIT RX MODE CURR PWR CURR RX MODE
1 N Y 100 Power Operation 100 Power Operation
EVENT TEXT
HPCI DECLARED INOPERABLE FOLLOWING DISCOVERY OF UNKNOWN CONTAMINANT
IN OIL
"Declared High Pressure Coolant Injection System (HPCI) INOP due to unknown
contaminants in the oil system. Plant formulated an action plan to resample
the sump, identify the particles, and identify the source of the
contaminants. Entered 7 day LCO per Tech Spec 3.5.C.1.a."
The licensee informed the NRC Resident Inspector.
* * * UPDATE 1620EST ON 2/8/02 FROM ANDY HALLIDAY TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"Further analysis has shown that the foreign material found in the HPCI lube
oil sample taken 2/7/2002 did not cause HPCI to become inoperable, it could
have performed its design function before, during and after the time it was
declared inoperable.
"This is based on determination through engineering review that the type and
size of material found in the sample would not have prevented any part of
HPCI from failing to operate as required.
"Preliminary cause determination is that 4 liters of unfiltered oil were
added to the 150 gallon lube oil system during the previous monthly sample
evolution.
"For these reasons. JAF is concluding that HPCI remained operable from the
original LCO entry of 12:15; 2/7/02. and is retracting notification
#38679."
The licensee informed the NRC Resident Inspector. Notified R1DO(Doerflein).
General Information or Other Event Number: 38683
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REP ORG: OHIO BUREAU OF RADIATION PROTECTION NOTIFICATION DATE:
02/08/2002
LICENSEE: BATTELLE MEMORIAL INSTITUTE NOTIFICATION TIME: 13:43[EST]
CITY: COLUMBUS REGION: 3 EVENT DATE: 01/29/2002
COUNTY: STATE: OH EVENT TIME: [EST]
LICENSE#: OH03610250000 AGREEMENT: Y LAST UPDATE DATE: 02/08/2002
DOCKET:
PERSON ORGANIZATION
THOMAS KOZAK R3
FRED BROWN NMSS
NRC NOTIFIED BY: MICHAEL SNEE
HQ OPS OFFICER: JOHN MacKINNON
EMERGENCY CLASS: NON EMERGENCY
10 CFR SECTION:
NAGR AGREEMENT STATE
EVENT TEXT
AGREEMENT STATE EVENT
The licensee reported the loss of a internally contaminated duct. The duct
is 13-feet long and 4-inches in diameter and contaminated with U-234, U-235,
and U-238, with the highest concentration being U-234. The licensee
estimates that 1.5 microcuries of U-234 is in the duct. The duct was sent
to a construction debris landfill in Franklin County, Ohio along with other
construction debris.
Source/Material: Unsealed Material, Other
Radionuclide: U-234
Activity (Curies): 0.0000015
Agreement State Item number: OH-02-021
General Information or Other Event Number: 38684
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REP ORG: MARYLAND DEPT OF THE ENVIRONMENT NOTIFICATION DATE:
02/08/2002
LICENSEE: HOLY CROSS HOSPITAL NOTIFICATION TIME: 15:36[EST]
CITY: SILVER SPRINGS REGION: 1 EVENT DATE: 02/04/2002
COUNTY: MONTGOMERY STATE: MD EVENT TIME: 15:00[EST]
LICENSE#: MD-31-001-01 AGREEMENT: Y LAST UPDATE DATE: 02/08/2002
DOCKET:
PERSON ORGANIZATION
LAWRENCE DOERFLEIN R1
PAUL FREDRICKSON R2
NRC NOTIFIED BY: RAY MANLEY
HQ OPS OFFICER: STEVE SANDIN
EMERGENCY CLASS: NON EMERGENCY
10 CFR SECTION:
NAGR AGREEMENT STATE
EVENT TEXT
AGREEMENT STATE REPORT INVOLVING POTENTIAL PERSONNEL EXPOSURES
On 2/4/02 at 1500EST a female patient undergoing treatment for thyroid
cancer received 250 millicuries I-131 at the Holy Cross Hospital located at
1500 Forest Glen Road in Silver Springs, MD 20910. The patient subsequently
expired on 2/5/02 at 0630EST. The body was released by the hospital to the
Metropolitan Funeral Home located at 5517 Vine Street in Alexandria, VA for
cremation. Due to the relatively short period of time between
administration of the I-131 dose and the patient's demise radiation levels
were measured 67 mR/hr @ 1 meter. The decedent was transferred back to Holy
Cross Hospital and is in an area away from the general public awaiting final
disposition. Both NRC Region I (Duncan White) and NRC Region II are aware
of this event. Contamination surveys were performed at the Funeral Home
with negative results. An investigation is ongoing to determine any
personnel exposures associated with this incident.
Other Nuclear Material Event Number: 38685
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REP ORG: BRIGHAM YOUNG UNIVERSITY NOTIFICATION DATE: 02/08/2002
LICENSEE: BRIGHAM YOUNG UNIVERSITY NOTIFICATION TIME: 16:15[EST]
CITY: LAIE REGION: 4 EVENT DATE: 01/01/2002
COUNTY: HONOLUL STATE: HI EVENT TIME: [HST]
LICENSE#: AGREEMENT: N LAST UPDATE DATE: 02/08/2002
DOCKET:
PERSON ORGANIZATION
JOHN PELLET R4
M. WAYNE HODGES NMSS
NRC NOTIFIED BY: JIM FREEMAN
HQ OPS OFFICER: STEVE SANDIN
EMERGENCY CLASS: NON EMERGENCY
10 CFR SECTION:
BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X
EVENT TEXT
SELF-POWERED TRITIUM EXIT SIGNS DISCOVERED MISSING FOLLOWING FACILITY
RENOVATION
The auditorium at the Brigham Young University Campus in Laie, HI underwent
renovation between 6/2000 and 1/2002. The contractor removed nine (9)
self-powered tritium exit signs for storage and reinstallation following
completion of the work. After work was completed the signs could not be
located. The Safety Officer (SO) at the University believes that the signs
may have been installed at another business location. Based on other
self-powered exit signs currently in possession, the SO feels the missing
signs contained 10 Curie tritium sources each and were manufactured by SRB
Technologies, Inc. located in Winston-Salem, NC between 1992 and 1993. A
written report will be submitted for the loss of this general licensed
material in accordance with NUREG-1556.
Power Reactor Event Number: 38686
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FACILITY: HATCH REGION: 2 NOTIFICATION DATE: 02/09/2002
UNIT: [1] [] [] STATE: GA NOTIFICATION TIME: 00:30[EST]
RXTYPE: [1] GE-4,[2] GE-4 EVENT DATE: 02/08/2002
NRC NOTIFIED BY: ED BURKETT LAST UPDATE DATE: 02/09/2002
EMERGENCY CLASS: NON EMERGENCY PAUL FREDRICKSON R2
10 CFR SECTION:
ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA
UNIT SCRAM CODERX CRITINIT PWR INIT RX MODE CURR PWR CURR RX MODE
1 M/R Y 27 Power Operation 0 Hot Shutdown
EVENT TEXT
MANUAL REACTOR SCRAM - DEGRADED VACUUM DUE TO ACTIONS FOR HIGH
OFFGAS
HYDROGEN
"Plant Hatch Unit 1 was SCRAMMED at 2252 EST on 02-08-2002. The Reactor was
SCRAMMED from approximately 27% RTP and the Main Turbine subsequently
tripped. Degraded function of the Main Condenser Offgas Recombiner system
had resulted in high Hydrogen in the Offgas. The 'Failure of Recombiner'
Abnormal Operating procedure (AOP) had been entered at approximately 2100
and a power reduction begun from 100% RTP at about 2105. Per the AOP, the
inservice Steam jet Air Ejector was removed from service at 2220 (due to the
Offgas Hydrogen concentration reaching approximately 4%). Hatch Unit 1 was
subsequently scrammed due to degrading Condenser Vacuum. The mechanical
vacuum pump was placed in service after the SCRAM to maintain Condenser
Vacuum as the heat sink. The lowest Reactor Water Level noted during the
SCRAM (approximately 7" above Instrument zero) was above any ESF actuation
settings, so no ESFs were required or received. No Reactor Pressure increase
was noted during the SCRAM. At this time plans are to proceed to Cold
Shutdown for repairs to the Offgas Recombiner system and other maintenance.
Air purge had been placed inservice to purge the Hydrogen from the Offgas
system at around 2230, and remains inservice to reduce Hydrogen
concentrations."
The licensee notified the NRC Resident Inspector.
Power Reactor Event Number: 38687
FACILITY: DIABLO CANYON REGION: 4 NOTIFICATION DATE: 02/09/2002
UNIT: [] [2] [] STATE: CA NOTIFICATION TIME: 10:09[EST]
RXTYPE: [1] W-4-LP,[2] W-4-LP EVENT DATE: 02/09/2002
NRC NOTIFIED BY: DOUGLAS DYE LAST UPDATE DATE: 02/09/2002
EMERGENCY CLASS: NON EMERGENCY JOHN PELLET R4
10 CFR SECTION:
ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA
AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT
UNIT SCRAM CODERX CRITINIT PWR INIT RX MODE CURR PWR CURR RX MODE
2 M/R Y 100 Power Operation 0 Hot Standby
EVENT TEXT
MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER TO A STEAM GENERATOR
"At 0337, on 2/9/2002, Unit 2 reactor was manually tripped due to a failure
of feedwater regulating valve FW-2-FCV-540. The valve failed closed
isolating feedwater to steam generator 2-4. The reason for the failure is
currently unknown, investigation continues. All safety systems responded as
required. [All control rods fully inserted]. Auxiliary feedwater pumps 2-1,
2-2, 2-3 started as required in response to low steam generator water
levels.
"DCPP unit 2 is stable in Mode 3, heat removal is via steam dumping to the
normal condenser, auxiliary feedwater continues to supply the steam
generators." The unit will remain in Mode 3 until repairs are made.
The unit 2 steam generator 4 has had a long term tube leak (about 2 years)
on the order of about 3.82 gpd (TS limit 150 gpd) by most recent
calculation. Secondary activity is less than detectable and only a count
rate on steam jet air ejector is positive indication. Primary activity
pretrip was 3.47E-3 �Ci/ml.
The licensee notified the NRC Resident Inspector and will make a normal
press release.
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