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Event Notification Report for January 12, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/11/2006 - 01/12/2006

** EVENT NUMBERS **


42246 42247 42250 42251 42252

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Power Reactor Event Number: 42246
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MIKE HIMEBAUCH
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/10/2006
Notification Time: 15:51 [ET]
Event Date: 01/10/2006
Event Time: 11:00 [EST]
Last Update Date: 01/11/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
KENNETH O'BRIEN (R3)

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

Event Text

LOSS OF ENS AND COMMERCIAL LINE COMMUNICATION DUE TO FIBER OPTIC LINE BREAK

"At approximately 1100 EST on 1/10/06, the capability of the ENS and commercial telephones to communicate with offsite authorities was found to be not functioning. In addition, the capability of the ERDS system to communicate with the NRC is not functioning. Communications to offsite authorities have been verified using microwave communications (RERP phone lines). The cause of the problem has been determined to be an offsite cable break within the telecommunication provider's network. All onsite communications (including onsite telephones) are functioning properly. Offsite telecommunication company personnel are working to repair the broken cable. Currently, repairs are estimated to be complete by 1800 EST. The NRC Senior Resident Inspector has been notified.

"This report is being made pursuant to 10CFR50.72(b)(3)(xiii), as an event that results in a major loss of offsite communications capabilities."

* * * UPDATE FROM MIKE HIMEBAUCH TO JEFF ROTTON AT 1753 ON 01/10/06 * * *

"This is a follow-up to NRC Event No. 42246: Offsite repairs of the broken telecommunications cable which caused a loss of capability to communicate with offsite authorities using ENS, commercial telephones and ERDS has been completed. Proper operation of ENS, commercial telephone lines and ERDS to communicate with offsite authorities has been verified. All offsite communication systems have been returned to normal."

The licensee will notify the NRC Resident Inspector. Notified R3DO (O'Brien)

* * * UPDATE PROVIDED FROM JEFF YEAGER TO JEFF ROTTON AT 2050 EST ON 01/10/06 * * *

"At 1850 on 1/10/06, the capability of the ENS and commercial telephones to communicate with offsite authorities was again found to be not functioning. Discussion with telecommunication personnel indicate that troubleshooting and repair to the broken cable is continuing and will take approximately 4 hours. During this time, the communications with outside authorities will be intermittent.

"Therefore, this report is being made pursuant to 10CFR50.72(b)(3)(xiii), as an event that results in a major loss of off-site communications capabilities."

The licensee notified the NRC Resident Inspector, and state and local emergency response organizations. Notified R3DO (O'Brien)

* * * UPDATE PROVIDED FROM JEFF YEAGER TO BILL HUFFMAN AT 0406 EST ON 01/11/06 * * *

"Offsite repairs of the broken telecommunications cable which caused a loss of capability to communicate with offsite authorities using ENS, commercial telephones and ERDS has been completed. Proper operation of ENS, commercial telephone lines and ERDS to communicate with offsite authorities has been verified. All offsite communication systems have been returned to normal."

State and Local governments notified. The NRC Resident Inspector will be notified. R3DO (O'Brien) notified.

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Other Nuclear Material Event Number: 42247
Rep Org: AK STEEL CORPORATION
Licensee: AK STEEL CORPORATION
Region: 3
City: ROCKPORT State: IN
County:
License #:
Agreement: N
Docket:
NRC Notified By: STEVE CUSTER
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/10/2006
Notification Time: 17:15 [ET]
Event Date: 01/09/2006
Event Time: 11:30 [CST]
Last Update Date: 01/11/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
KENNETH O'BRIEN (R3)
C.W. (BILL) REAMER (NMSS)

Event Text

FAILURE OF SHUTTER TO CLOSE ON FIXED DENSITY GAUGE USED TO MEASURE STEEL THICKNESS

At 1130 hours on 01/09, the air cylinder on a gate operating the shutter for a fixed gauge failed to close. The gauge, a SenTek device, model not identified, is generally licensed and contains a 1000 mCi Am-241 source. The device was removed from service and heavy steel plate was positioned to shield the source. Additionally, the affected area was isolated and posted. No unmonitored personnel exposures occurred. A SenTek technician arrived onsite and corrected the malfunctioning shutter as of 0900 hours 01/10/06.

* * * UPDATE 1340 EST ON 1/11/06 FROM STEVE CUSTER TO S. SANDIN * * *

Further investigation determined that the fixed gauge is a model THAM2 manufactured by ABB AccuRay. The initial report is required per 10 CFR 30.50(b)(2). AK Steel will be submitting a followup written report within 30 days. Notified R3DO(O'Brien) and NMSS (Morell).

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Power Reactor Event Number: 42250
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BRIAN JOHNSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/11/2006
Notification Time: 14:16 [ET]
Event Date: 01/11/2006
Event Time: 07:43 [CST]
Last Update Date: 01/11/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
KENNETH O'BRIEN (R3)

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

Event Text

MODIFICATION TO THE UNIT 2 PROCESS COMPUTER THAT WILL IMPACT ERDS AND SPDS

"The Unit 2 Plant Process Computer System (PPCS) will be taken out of service for an approximate 2 week period to implement a planned modification. The current PPCS is being replaced and the computer outage is required to allow cutover to the new PPCS. During this time period ERDS and SPDS will not be available. Unit 2 ERDS and SPDS parameters will be monitored by control board indications. Compensatory actions have been developed.

"This is an 8-hour reportable event per 10 CFR50.72(b)(3)(xiii) Major Loss of Assessment Capability. The operation of plant systems will not be affected due to this planned action.

"The Unit 2 PPCS outage started at 0743 CST on 1/11/2006. The licensee has informed the NRC Resident Inspectors of the modification and schedule. The NRC was previously notified of this planned outage via letter dated November 7, 2005."

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Power Reactor Event Number: 42251
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STAN SINCLAIR
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/11/2006
Notification Time: 16:39 [ET]
Event Date: 01/11/2006
Event Time: 15:01 [EST]
Last Update Date: 01/11/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JOEL MUNDAY (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO SMALL DISCHARGE OF UNKNOWN OILY SUBSTANCE

"Approximately one gallon of an oily substance was spilled into the plant discharge cove of Lake Wylie. The source of the substance is unknown. Notification of the event has been made to South Carolina DHEC (Columbia and Fort Lawn offices) and the National Response Center (Report #784895)."

The substance had been noticed earlier today in a yard drain sump, but was not removed prior to heavy rains on site forcing it into the discharge cove. The licensee will be notifying North Carolina and South Carolina Emergency Operations Centers, and the Emergency Operations Centers for York, Gaston, and Mecklenburg counties.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42252
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: JULIE HOLT
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/11/2006
Notification Time: 20:43 [ET]
Event Date: 01/11/2006
Event Time: 12:48 [PST]
Last Update Date: 01/11/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
REBECCA NEASE (R4)
MICHAEL MAYFIELD (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

SHUTDOWN COOLING INOPERABILITY DUE TO SMALL DISCHARGE HEADER LEAK

"On Wednesday, January 11, 2006, at approximately 1248 PST, with San Onofre Unit 2 in Mode 5 (loops not filled), Southern California Edison (SCE) declared both trains of the Shutdown Cooling (SDC) System inoperable. This action was taken following discovery and evaluation of an approximate 1.5 inch crack and minor leak (about 10 drops per minute) in a line located at the Low Pressure Safety Injection (LPSI) common discharge header (the LPSI pumps are also used as the SDC system pumps). Although both trains of the SDC system remain functional and one train is in service, SCE declared both SDC trains inoperable because the affected pipe might not be ASME Code qualified as a result of this crack.

"SCE is conservatively reporting this event in accordance with 10CFR50.72(b)(3)(v)(B) as a condition that could prevent the remove residual heat. SCE is continuing to evaluate this condition.

"SCE is following the actions required by Technical Specifications 3.4.8, and will repair the pipe crack during the current refueling outage, after the reactor core has been off-loaded to the spent fuel pool. SCE expects to place the plant in Mode 6 tomorrow.

"At the time of this report, Unit 2 is in Mode 5 and Unit 3 is in Mode 1 at 100% power. The NRC Senior Resident Inspector, NRC Region IV, and the Nuclear Reactor Regulation Project Manager have been briefed of this event and will be provided with a copy of this report."

Shutdown cooling has been running for approximately one week and the leak was initially discovered sometime on 01/10/06 during an inspection in which Boric acid accumulation was discovered . A work request was written to perform a more thorough inspection that was performed on 01/11/06. The crack is on an 8 inch line that returns to RCS Loop 2A which is normally isolated during high pressure shutdown conditions and reactor power operation.

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