Event Notification Report for October 3, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/02/2002 - 10/03/2002
** EVENT NUMBERS **
39238 39239 39240 39241 39242
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| POWER REACTOR EN NUMBER:39238 |
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LICENSEE: FIRSTENERGY NUCLEAR OPERATING COMPANY
SITE: DAVIS BESSE 1 EN NUMBER:39238
DOCKET: 05000346 EVENT DATE: 10-02-02
RX TYPE: PWR EVENT TIME: 13:44
VENDORS: B&W-R-LP NOTIFY DATE: 10-02-02
EMERGENCY CLASS: N/A REGION: 3 STATE: OH TIME: 14:20
OPS OFFICER: MIKE NORRIS
10 CFR SECTION: APRE OFFSITE NOTIFICATION
DDDD SAFEGUARDS REPORTS
UNIT SCRAM RX INIT INITIAL MODE CURR CURRENT MODE
CODE CRIT PWR PWR
1 N N 0 Refueling 0 Refueling
1 HOUR SAFEGUARDS REPORT
Attempted introduction of contraband into controlled access area.
The NRC Resident Inspector was notified.
Contact Headquarters Operations Officer for additional details.
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| POWER REACTOR EN NUMBER:39239 |
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LICENSEE: DETROIT EDISON CO.
SITE: FERMI 2 EN NUMBER:39239
DOCKET: 05000341 EVENT DATE: 10-02-02
RX TYPE: BWR EVENT TIME: 14:53
VENDORS: GE-4 NOTIFY DATE: 10-02-02
EMERGENCY CLASS: N/A REGION: 3 STATE: MI TIME: 17:24
OPS OFFICER: MIKE NORRIS
10 CFR SECTION: AESF VALID SPECIF SYS ACTUATION
ARPS RPS ACTUATION - CRITICAL
UNIT SCRAM RX INIT INITIAL MODE CURR CURRENT MODE
CODE CRIT PWR PWR
2 A/R Y 100 Power Operation 0 Hot Shutdown
REACTOR SCRAM DUE TO TURBINE TRIP FROM A LOSS OF CONDENSER VACUUM
"On Wednesday, October 2, 2002 at 1453 hours, the reactor
scrammed from 100% power. Condenser vacuum was lost when
circulating pump No. 2 failed. Condenser pressure went above the
turbine trip setpoint. The main turbine, tripped and the reactor
scrammed. All rods fully inserted.
"Reactor level is stable in the normal band (197 inches).
Reactor Level 3 (173 inches) was reached and level was restored
to normal.
"No ECCS systems actuated. No safety/relief valves opened. All
systems functioned normally. Reactor level is being maintained
using one reactor feed pump through the startup level control
valve. Cool down is through the main turbine bypass valves to
the main condenser. The following 'Level 3' isolations occurred
as expected:
Group 4 - RHR Shutdown Cooling and Head Spray
Group 13 - Drywell Sumps
Group 15 - Traversing Incore Probe Systems
"NRC Senior Resident Inspector has been notified.
"This report is being made in accordance with 10 CFR
50.72(b)(2)(iv)(B), Any event that results in actuation of the
reactor protection system (RPS) when the reactor is critical, and
10 CFR 50.72(b)(3)(iv)(A), Specified System Actuation."
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| POWER REACTOR EN NUMBER:39240 |
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LICENSEE: ENERGY NORTHWEST
SITE: COLUMBIA GENERATING STATION 2 EN NUMBER:39240
DOCKET: 05000397 EVENT DATE: 09-26-02
RX TYPE: BWR EVENT TIME:
VENDORS: GE-5 NOTIFY DATE: 10-02-02
EMERGENCY CLASS: N/A REGION: 4 STATE: WA TIME: 17:58
OPS OFFICER: MIKE NORRIS
10 CFR SECTION: NONR OTHER UNSPEC REQMNT
UNIT SCRAM RX INIT INITIAL MODE CURR CURRENT MODE
CODE CRIT PWR PWR
2 N Y 100 Power Operation 100 Power Operation
24 HOUR CONDITION OF LICENSE REPORT
The following is a facsimile received from the Region 4 Duty
Officer.
"This facsimile is being sent to confirm a telephonic report of
October 1, 2002 that was made pursuant to the Columbia Generating
Station Operating License (NPF-21) condition 2.F, which states:
'With the exception of 2.C(2) the licensee shall report any
violations of the requirements contained in Section 2.C, and E of
this license within 24 hours by telephone and confirm by
telegram, mailgram, or facsimile transmission to the NRC Regional
Administrator, Region V or that administrator's designee, no
later than the first working day following the violation, with a
written followup report within 14 days.
'The subject of the report is the discovery that all the
provisions of the Commission-approved physical security plan were
not maintained in effect for a period of approximately 2 hours on
September 26, 2002 when personnel gates to the independent Spent
Fuel Storage Installation (ISFSI) protected area were unlocked,
open, and unattended. During this time, the operable ISFSI
intrusion detection system did nor detect any entry into the
ISFSI protected area. A written follow-up report regarding this
issue will be submitted on or before October 15, 2002.'
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| POWER REACTOR EN NUMBER:39241 |
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LICENSEE: PPL SUSQUEHANNA LLC
SITE: SUSQUEHANNA 1 2 EN NUMBER:39241
DOCKET: 05000387 05000388 EVENT DATE: 10-03-02
RX TYPE: BWR BWR EVENT TIME: 03:15
VENDORS: GE-4 GE-4 NOTIFY DATE: 10-03-02
EMERGENCY CLASS: UNU REGION: 1 STATE: PA TIME: 03:33
OPS OFFICER: JOHN MacKINNON
10 CFR SECTION: AAEC EMERGENCY DECLARED
UNIT SCRAM RX INIT INITIAL MODE CURR CURRENT MODE
CODE CRIT PWR PWR
1 N Y 100 Power Operation 100 Power Operation
2 M/R Y 1 Startup 0 Hot Shutdown
UNUSUAL EVENT DECLARED PER EAL 14.1- FIRE LASTING GREATER THAN 15
MINUTES & ACTIVATION OF THE FIRE BRIGADE.
"At 0230 on 10/3/02, the control room was notified that there was
a fire at Startup Transformer T-20. Unit 2 was in the process of
starting up and was at a pressure of 435 psig and range 8 on the
IRMs. T-20 lost power which caused the recirc pumps on Unit 2 to
trip. With no recirculation, operators placed the mode switch to
shutdown. All rods were inserted. Unit 1 was at 100% power at
the time and continued to operate. The Station Fire Brigade was
activated. The deluge system extinguished the fire in 10
minutes"
Non-Vital power is being supplied to T-20 Startup Transformer Bus
from Startup Transformer T-10 via cross tie breaker. Offsite
fire department was called but was not needed. All Emergency
Core Cooling systems and the Emergency Diesel Generators are
fully operable if needed.
The Unusual event will be terminated after an assessment of what
caused the Startup Transformer T-20 fire/failure.
The licensee notified the State of PA, surrounding counties and
the NRC Resident Inspector of the declaration of an Unusual
Event.
***UPDATE ON 10/03/02 AT 0605ET BY SID MORGAN TAKEN BY
MACKINNON ***
EAL 14.1 was exited and the Unusual Event terminated at 05:52 ET.
Unusual event was terminated after damage assessment of Startup
Transformer T-20 was completed. R1DO (Pete Esselgroth), NRR EO
(Bill Dean) & FEMA (Sweetser) notified.
The NRC Resident Inspector was notified of the termination of the
Unusual event by the licensee.
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| POWER REACTOR EN NUMBER:39242 |
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LICENSEE: PPL SUSQUEHANNA LLC
SITE: SUSQUEHANNA 2 EN NUMBER:39242
DOCKET: 05000388 EVENT DATE: 10-03-02
RX TYPE: BWR EVENT TIME: 02:30
VENDORS: GE-4 NOTIFY DATE: 10-03-02
EMERGENCY CLASS: N/A REGION: 1 STATE: PA TIME: 05:15
OPS OFFICER: JOHN MacKINNON
10 CFR SECTION: ASHU PLANT S/D REQD BY TS
ARPS RPS ACTUATION - CRITICAL
UNIT SCRAM RX INIT INITIAL MODE CURR CURRENT MODE
CODE CRIT PWR PWR
2 M/R Y 1 Startup 0 Hot Shutdown
MANUAL REACTOR SCRAM DUE TO LOSS OF POWER TO RECIRC PUMPS.
"At 0230 on 01/3/02, the control room was notified that there was
a fire at Startup Transformer T-20. Unit 2 was in the process of
starting up and was at a pressure of 435 psig and range 8 on the
IRMs. T-20 lost power which caused the recirc pumps on Unit 2 to
trip. With no recalculation while in Mode 2, Tech Specs requires
the unit to be in Mode 3 within 12 hours. Operations placed the
mode switch to shutdown. All rods were inserted. Unit 1 was at
100% power at the time and continued to operate. The Station
Fire Brigade was activated. The deluge system extinguished the
fire in 10 minutes. An Unusual Event was declared under EAL
14.1 at 03:15.
"This is a 4 hr Non-Emergency notification under 10 CFR
50.72(b)(2)(I) for a Tech Spec required shutdown and a 4 hr
Non-Emergency notification under 10 CFR 50.72(b)(2)(iv)(B) for an
RPS actuation."
A press release will be made.
The NRC Resident Inspector was notified of this event by the
licensee.
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021