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Event Notification Report for December 6, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/03/2004 - 12/06/2004

** EVENT NUMBERS **


41241 41242 41243 41244 41245 41246

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Power Reactor Event Number: 41241
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TIM RIEGER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/03/2004
Notification Time: 17:13 [ET]
Event Date: 12/03/2004
Event Time: 15:55 [EST]
Last Update Date: 12/03/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES TRAPP (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 53 Power Operation

Event Text

PRESS RELEASE REGARDING PLANT SHUTDOWN TO REPAIR SECONDARY STEAM PRESSURE INSTRUMENT LINE

"At 1555 hours on 12/03/04, Indian Point Unit 2 commenced a plant shutdown at 200 MW/Hour. Plant shutdown will be completed within 5 to 6 hours. This shutdown is due to a crack on an unisolable secondary steam pressure instrument line on the H.P. [high pressure] turbine (PT-412B). The reactor is expected to remain critical at approximately 4% power on auxiliary feedwater. The plant is expected to be restarted within 24 hours following repair to the (3/4 inch) instrument line."

The licensee noted that the crack was visually observed during rounds but was not yet blowing steam.

The licensee plans to issue a press release. The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 41242
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: STEVEN WEBSTER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 12/04/2004
Notification Time: 02:50 [ET]
Event Date: 12/03/2004
Event Time: 22:30 [EST]
Last Update Date: 12/04/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PAUL FREDRICKSON (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

EARLY WARNING SIREN SYSTEM FAILURE

"Actual failure was 100% (106 sirens) due to loss of power to station on-site/off-site radio repeaters. Failure occurred at 22:30 12-03-04. System was restored on temporary power at 23:06 12-3-04. State and local counties notified of failure at 23:26 12-4-04. System returned to normal power a 01:00 12-4-04. Station resident inspectors notified (J. Zeiler and M. King). System verified communications at 92% availability"

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Power Reactor Event Number: 41243
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: P. FALLON
HQ OPS Officer: ARLON COSTA
Notification Date: 12/04/2004
Notification Time: 05:07 [ET]
Event Date: 12/04/2004
Event Time: 04:17 [EST]
Last Update Date: 12/04/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
KENNETH O'BRIEN (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 56 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO AN AUTO VOLTAGE REGULATOR TRIP

"On December 4, 2004 at 0417 [EST], the Reactor Scrammed as the result of an AVR [Automatic Voltage Regulator] trip. AVR Channels A and B were both operating at the time. The AVR trip caused a Main Generator trip which caused a Main Turbine trip. The Main Turbine trip causes a direct Reactor SCRAM on Turbine Valve position. RPS functioned properly and all rods inserted [fully]. MSIVs remain open with Reactor Level being maintained in the normal band of 173 to 214 inches. Reactor Pressure is being maintained with the Main Turbine Bypass valves. Isolations expected for Reactor Level 3 occurred and have been reset."

Previous to the reactor scram, the AVR alarm was being monitored. All other safety systems functioned as required. Similar event occurred 09/04/04 (EN#41017).

The licensee notified the NRC Resident Inspector.

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Fuel Cycle Facility Event Number: 41244
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: ERIC WALKER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 12/05/2004
Notification Time: 07:42 [ET]
Event Date: 12/04/2004
Event Time: 06:50 [CST]
Last Update Date: 12/05/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
PAUL FREDRICKSON (R2)
GARY JANOSKO (NMSS)

Event Text

HIGH PRESSURE TRANSMITTER FAILURE

"At 0650 on 12-04-04, the Plant Shift Superintendent (PSS) was notified of a failure of the C-333A Autoclave 1 North High Cylinder Pressure System (HCPS). During a normal cylinder heating cycle an operator noted that the cylinder pressure, read on a recorder in the Operations Monitoring Room (OMR), unexpectedly fell from 70 to 0 psia. The PSS declared the system inoperable and TSR LCO 2.2.4.14B actions were implemented to place the autoclave in Mode 2 (autoclave open, non-applicable mode). The High Cylinder Pressure System (TRS 2.2.4.14) is designed to minimize the potential of a primary system failure (cylinder rupture) during a pressure increase event by automatically isolating the steam supply to the autoclave prior to reaching the Maximum Allowable Working Pressure (MAWP) of the cylinder. The event is reportable as a 24 hour event, as required by 10 CFR 76.120(c)(2)(1); An event in which equipment is disabled or fails to function as designed when the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specific limits, mitigate the consequences of an accident, or restore this facility to a preestablished safe condition after an accident. The equipment was required by TSR to be available and operable and no redundant equipment was available to perform the required safety function.

"The NRC Resident Inspector has been notified of this event."

PGDP Problem Report No. ATR-04-4819, PGDP Event Report No. PAD-2004-28.

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Power Reactor Event Number: 41245
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ERIC POWELL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/05/2004
Notification Time: 15:54 [ET]
Event Date: 12/05/2004
Event Time: 10:15 [EST]
Last Update Date: 12/05/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JAMES TRAPP (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

REACTOR COOLANT LEAKAGE OUTSIDE OF CONTAINMEMT

"This is an 8-hour notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. The event is being reported under paragraph (b)(3)(v) of 10CFR50.72.

"On 12/05/04 at 1015 the control room was notified of leakage from a gasketed flange area on the 11 Residual Heat Removal Heat Exchanger. The leak rate has been conservatively quantified at 0.68 gpm, which is greater than the UFSAR limit of 2100 cc/hr (0.009 gpm) for ECCS leakage outside containment.

"With leakage greater than the UFSAR allowed limits, GDC-19 limits for control room habitability cannot be assured. Actions are in progress to torque the flange bolts to reduce the leakage.

"The licensee has notified the NRC Resident inspector of this event.

"Salem Unit One is in Mode 4 with the Residual Heat Removal system in service removing reactor decay heat. No ECCS system actuations occurred. No one was injured as a result of the leak."

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Power Reactor Event Number: 41246
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF NIEBERDING
HQ OPS Officer: JOHN MacKINNON
Notification Date: 12/06/2004
Notification Time: 00:17 [ET]
Event Date: 12/05/2004
Event Time: 21:35 [EST]
Last Update Date: 12/06/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
PAUL FREDRICKSON (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO MOISTURE SEPARATOR REHEATER (MSR) HIGH LEVEL TRIP SIGNAL.


"Reactor Trip caused by Turbine trip. Turbine trip caused by a Moisture Separator Reheater 1B high level. Maintenance personnel were working in vicinity of level switches at time of trip. Root cause investigation in progress. All systems operated as designed on Reactor trip."

Maintenance personnel working in the vicinity of Moisture Separator Reheater 1B were setting up radiography equipment when the MSR 1B high level trip was generated. All rods fully inserted. Both Motor Driven Auxiliary Feedwater pumps actuated as expected. All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. Catawba Unit 2 is operating at 100% power and the electrical grid is stable.


The NRC Resident Inspector was notified of this event by the licensee.

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