United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for January 19, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/18/2006 - 01/19/2006

** EVENT NUMBERS **


42238 42250 42256 42266 42267 42269 42272

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Fuel Cycle Facility Event Number: 42238
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: STEVEN SKAGGS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 01/02/2006
Notification Time: 17:58 [ET]
Event Date: 01/02/2006
Event Time: 04:38 [CST]
Last Update Date: 01/18/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
MARK LESSER (R2)
WILLIAM RULAND (NMSS)

Event Text

REPORT OF SAFETY EQUIPMENT FAILURE

"At 0453 CST on 01/02/2006, the Plant Shift Superintendent (PSS) was notified that steam was observed leaking from the C-337A Position 1 West Autoclave. A 14 ton cylinder containing 0.711 % U235 assay uranium hexafluoride had been heating (TSR [Technical Safety Requirement] Mode 5) for approximately 5 minutes when the leak was observed. The autoclave pressure containment boundary is a TSR system required to be operable per TSR 2.2.3.1, 'Autoclave High Pressure Isolation System (HPIS),' when the autoclave is in Mode 5. The autoclave was placed in Mode 2, 'Autoclave Out-of-Service' in accordance with LCO Required Actions 2.2.3.1.C.

"This event is reportable as a 24 hour event in accordance with 10CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function."

The licensee noted that after steam was turned off to the autoclave, an inspection of the o-ring sealing surfaces did not identify any problems. No other sources of a steam leak could be found in the autoclave. The HPSI was declared inoperable due to a possible head-to-shell leak. The licensee will need to wait for a five day cool down time for the cylinder in the autoclave before it can be removed. Once the cylinder is removed, the autoclave can be re-pressurized in an attempt to determine the leak location.

The NRC Senior Resident Inspector and DOE have been notified of this event.

* * * UPDATE AT 15:03 EST ON 01/18/06 FROM SKAGGS TO KNOKE * * *

"This notification is being retracted."

"On January 11, 2006, the 1 west autoclave was subjected to an autoclave pressure decay test. The autoclave passed the test on both the inner and outer containment valves. This proved that the steam leak reported by operators was not from a breach of the autoclave containment boundary, and that the AHPIS was performing as designed during the heat cycle initiated on January 2, 2006. Following the pressure decay test, steam was valved into the autoclave in an effort to find the steam leak. Steam vapor was seen under the autoclave at the location reported by operators on January 2, 2006. The steam vapor was discovered to be coming from a condensate blow-down hose that had moved away from the condensate drain housing allowing steam vapor to escape. No other leaks were noted.

"The successful autoclave pressure decay test provides evidence that the AHPIS was operable and available while the autoclave was in TSR Mode 5 on January 2, 2006, and thus the reporting criteria was not met.

"The NRC Senior Resident Inspector for PGDP has been notified of this retraction."

Notified R2DO (Ogle) and NMSS Daytime EO (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: 01/18/2006
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."

* * * UPDATE FROM J BAARTMAN TO W GOTT AT 2019 EST ON 01/18/06 * * *

"The Unit 2 Plant Process Computer System (PPCS) was restored at 1801 CST on 01/18/06. The Unit 2 Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) have also been returned to service."

The licensee notified the NRC Resident Inspector.

Notified R3DO (M Phillips)

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General Information or Other Event Number: 42256
Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: CAREALLIANCE HEALTH SERVICES ROPER HOSPITAL
Region: 1
City: CHARLESTON State: SC
County:
License #: 646
Agreement: Y
Docket:
NRC Notified By: JIM PETERSON
HQ OPS Officer: JOHN KNOKE
Notification Date: 01/13/2006
Notification Time: 16:24 [ET]
Event Date: 01/12/2006
Event Time: [EST]
Last Update Date: 01/13/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD CONTE (R1)
C.W. (BILL) REAMER (NMSS)

Event Text

AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION

The State provided the following information via facsimile:

"The South Carolina Department of Health and Environmental Control was notified (telephone) on January 13, 2006, by the licensee, that a medical misadministration had occurred. A patient being treated with a Iridium 192 HDR after loading brachytherapy system received a fractionated dose that differed from the prescribed dose, for a single fraction, by 50 percent or more. The patient was undergoing the first of three treatments to the pelvic region. The prescribed dose for this first treatment was 700 centigray but the patient only received 233 centigray, approximately one third of the intended dose. Further details of the misadministration will be supplied by the licensee in the forthcoming written report. Updates to this event will be made through the NMED system."

SC Report ID No. - SC060001

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Power Reactor Event Number: 42266
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHARLES ROKES
HQ OPS Officer: JOHN KNOKE
Notification Date: 01/18/2006
Notification Time: 11:57 [ET]
Event Date: 01/18/2006
Event Time: 08:48 [EST]
Last Update Date: 01/18/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRIS HOTT (R1)

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

Event Text

LOSS OF POWER TO OFF-SITE EMERGENCY SIRENS

"On January 18, 2006, at 08:48 hours, Emergency Planning determined that greater than 15 of a total of 156 sirens were reported as unavailable due to weather related loss of power as a result of high winds. In accordance with the Indian Point reporting procedure, the loss of 16 or more sirens that can not be returned to service in one hour, constitutes a major loss of the offsite notification capability that requires an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(xiii). The condition was recorded in the Indian Point Energy Center Corrective Action Program as CR-IP2-2006-00246 and actions have been initiated to investigate and correct the condition."

As of 11:40 EST on 01/18/06 there were 31 of 156 sirens out of service.

The licensee notified the NRC Resident Inspector, as well as the Counties of Westchester, Putnam, Rockland, and Orange.

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Power Reactor Event Number: 42267
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BOYD VAN LANDINGHAM
HQ OPS Officer: JOHN KNOKE
Notification Date: 01/18/2006
Notification Time: 15:06 [ET]
Event Date: 01/18/2006
Event Time: 11:34 [CST]
Last Update Date: 01/18/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHARLES R. OGLE (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

LOSS OF OFFSITE PUBLIC PROMPT NOTIFICATION FOR GREATER THAN ONE HOUR

"Offsite Public Prompt Notification System, Sirens and Tone Alert Radios were inoperable for greater than one hour. The Primary Console for siren operation at Houston County was found to be non functional at [approximately] 0820 CST during periodic siren tests. The backup console did successfully operate the sirens. However, at 1030 CST the transport system for actuating system failed at Webb, AL and the Backup Console for siren operation as well as Tone Alert Radios became inoperable. The inoperability of the system lasted for one hour and five minutes, being restored at 1134 CST. Initial troubleshooting indicates the problem was with the fiber coaxial cable to the demultiplexer in the transport. The problem could not be repeated, and investigation continues. Repairs for the Primary Console for siren actuation are being facilitated."

The licensee notified the NRC Resident Inspector and Houston County.

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Power Reactor Event Number: 42269
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: CHARLES ROKES
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/18/2006
Notification Time: 17:29 [ET]
Event Date: 01/18/2006
Event Time: 12:45 [EST]
Last Update Date: 01/18/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRIS HOTT (R1)

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

Event Text

LOSS OF EMERGENCY RESPONSE CAPABILITY DUE TO WEATHER

"On January 18, 2006, at 12:45 hours, Westchester County Emergency Operations Center notified Indian Point that their local emergency service agencies would not be able to accomplish route alerting in the event of an emergency at Indian Point in accordance with the Emergency Plan due to weather related conditions in Westchester County. Westchester County advised that all Westchester County emergency response agencies are fully engaged in storm related responses and have no available manpower. At the time of the Westchester County notification, 18 of 79 sirens in Westchester County were without power due to weather. Westchester County was contacted by Indian Point and the use of outbound calling was discussed. Although Westchester County stated they would use outbound calling, they indicated a concern regarding the availability of the public switch network. New York State Emergency Management office was also contacted by Indian Point regarding this issue and they in turn contacted Westchester County to offer support. In addition, the other counties (Putnam, Rockland and Orange) were contacted regarding their ability to initiate route alerting. Each of the other counties confirmed their ability to perform route alerting. In accordance with NRC reporting guidelines (NUREG1022), if a significant natural hazard causes parts of the response infrastructure to be impaired to the extent that the State and local governments are rendered incapable of fulfilling their responsibilities in the Emergency Plan for the plant, the NRC must be notified. Therefore, based on Westchester County's stated condition, an 8-hour non-emergency notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii). The condition was recorded in the Indian Point Energy Center Corrective Action Program as CR-IP2-2006-00256 and actions have been initiated to investigate and correct the condition. The notification of the loss of sirens was reported at 11:57 hours, by Event Notification log No. 42266. At 16:41 hours, Westchester County advised Indian Point that local municipalities will be able to handle required route alerting responsibilities if there is an event at Indian Point."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42272
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: HENRY KELLY
HQ OPS Officer: BILL GOTT
Notification Date: 01/18/2006
Notification Time: 19:25 [ET]
Event Date: 01/18/2006
Event Time: 10:00 [EST]
Last Update Date: 01/18/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
MONTE PHILLIPS (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 84 Power Operation 100 Power Operation

Event Text

24-HOUR CONDITION OF LICENSE REPORT INVOLVING FIRE PROTECTION PROGRAM NON-COMPLIANCE

"This notification is being made pursuant to the Perry Nuclear Operating License section 2.C.6 (violation of the Fire Protection Program).

"Incorrect configuration of Division 1 remote shutdown panel wiring was identified during performance of surveillance testing. This incorrect configuration is associated with the Reactor Core Isolation Cooling motor operated exhaust valve. In the event of a fire in the control room, the motor operated exhaust valve would have the potential for spurious operation caused by fire induced shorts prior to isolation from the control room. Repairs and operator actions could have been taken to restore the valve. However, these repairs and operator actions are not currently identified in the Fire Protection Safe Shutdown analysis or associated operating procedures. Therefore, for this issue Perry does not comply with the Perry Fire Protection Program.

"Repairs have been completed and configuration has been restored."

The licensee will notify the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012