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Event Notification Report for March 31, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/30/2005 - 03/31/2005

** EVENT NUMBERS **


41444 41463 41529 41548 41549 41550 41551

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 41444
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: RANDY CAMPBELL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/26/2005
Notification Time: 00:59 [ET]
Event Date: 02/15/2005
Event Time: 20:55 [EST]
Last Update Date: 03/30/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PAMELA HENDERSON (R1)
JAMES TRAPP (R1)

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

POSSIBLE FAILURE TO MEET DESIGN BASIS REQUIREMENTS OF POSITIVE PRESSURE IN THE CONTROL TOWER ENVELOPE FOLLOWING A DESIGN BASIS ACCIDENT.

The licensee provided the following information:

"During operator rounds it was discovered that a double door for the control tower habitability envelope was propped open [from painting earlier in the day]. This condition would have resulted in not meeting the design basis requirements of maintaining a positive pressure inside the control tower envelope following a design basis accident. The doors were immediately closed."

"An issue report was generated and a prompt investigation was commenced in accordance with station policies."

The NRC resident Inspector was notified.

*** RETRACTION FROM A. MILLER TO J. KNOKE AT 13:15 EST ON 03/30/05 ***

The licensee provided the following information:

"An ENS notification (EN# 41444) was made at approximately 00:59 on 2/20/2005 regarding a potentially unanalyzed condition associated with a double door for the Control Tower Habitability Envelope, which was propped open. It was initially thought that this condition could have resulted in not meeting the design basis requirements for the Control Tower Envelope. However, an analysis of an air flow measurement across the open door has shown that the unfiltered air in-leakage into the Control Tower Habitability Envelop would not exceed the value assumed in the design basis accident analysis for Control Room Habitability. Since this event did not result in an unanalyzed condition, this event is being retracted."

The licensee notified NRC Resident Inspector.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 41463
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 03/06/2005
Notification Time: 15:25 [ET]
Event Date: 03/06/2005
Event Time: 15:00 [EST]
Last Update Date: 03/30/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DANIEL HOLODY (R1)

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

POST-ACCIDENT MONITORING INSTRUMENTATION INOPERABLE

The following information was provided by the licensee via facsimile (licensee text in quotes):

"At 1500, on March 6, 2005, the Control Room declared both required divisions for three functions (Primary Containment Pressure, Primary Containment Hydrogen and Oxygen Analyzer, and Drywell Atmosphere Temperature) of Post Accident Monitoring Instrumentation (a Safety System) inoperable. The control room was notified of 'Non Quality' (non-Q) parts installed in both required divisions of a Post Accident Monitoring Instrumentation Recorder. The appropriate LCO Conditions were entered for one or more functions with two required channels inoperable. This equipment has passed all surveillance requirements and has been functional since installation.

"Plans are being developed to replace the non-qualified parts.

"This is being reported as an event or condition that could have prevented fulfillment of a safety function required to mitigate the consequences of an accident in accordance with 10CFR50.72(b)(3)(v)(D)."

The licensee notified the NRC Resident Inspector.


* * * UPDATE ON 03/30/05 @ 1128 BY JIM HUFFORD TO CHAUNCEY GOULD * * * RETRACTION

The following information was provided by the licensee via facsimile (licensee text in quotes):

"On March 6, 2005, PPL Susquehanna, LLC reported a perceived loss of safety function for three functions of Post Accident Monitoring Instrumentation on Unit 1. The notification was made pursuant to the reporting requirements of 10CFR50,72(b)(3)(v)(d). Engineering analysis has subsequently determined that the use of non-Q fuse holders in the Quality application did not adversely affect the safety-related functions which they supported. The fuse holders were removed, subjected to testing, and determined to be electrically and functionally equivalent 'to Quality fuse holders maintained at the station. This analysis conclusion provides the basis for retraction of the ENS report of March 6."

The NRC Resident Inspector was notified.

The Reg 1 RDO (Jim Trapp) was informed.

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General Information or Other Event Number: 41529
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: PERKIN ELMER LIFE SCIENCES
Region: 1
City: BOSTON State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BOB WALKER
HQ OPS Officer: BILL GOTT
Notification Date: 03/27/2005
Notification Time: 08:16 [ET]
Event Date: 03/26/2005
Event Time: 04:14 [EST]
Last Update Date: 03/27/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN ROGGE (R1)
DANIEL GILLEN (NMSS)
SUE GAGNER (PAO)
JACK CRLENJAK (IRD)

Event Text

AGREEMENT STATE REPORT - FIRE INVOLVING RADIOACTIVE MATERIAL

At 0414 on 03/26/05, a fire broke out in a laboratory of the Perkin Elmer Life Sciences in Boston, MA, that contained 8 Curies Carbon 14. The C-14 was stored in multiple locations. Local fire fighters and hazmat team responded. The fire was extinguished at approximately 0800. There was evidence of contamination inside the building and on the firefighters protective clothing. The levels were 3 - 4 times background. Two firefighters were treated at the hospital for smoke inhalation. The licensee has taken bioassay samples from the two individuals. Wipes outside the facility had no contamination. The cause of the fire is unknown.

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Power Reactor Event Number: 41548
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: BILL GOTT
Notification Date: 03/30/2005
Notification Time: 09:35 [ET]
Event Date: 03/30/2005
Event Time: 07:35 [CST]
Last Update Date: 03/30/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
KENNETH RIEMER (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

TECHNICAL SPECIFICATION SHUTDOWN DUE TO CONTAINMENT FAN COIL UNITS DECLARED INOPERABLE

The following information was obtained from the licensee via facsimile (licensee text in quotes):

"The site determined that previous repairs to 21, 22, and 23 Containment Fan Coil Unit (CFCU) Heat Exchangers were not in compliance with applicable ASME codes. The three CFCUs were declared inoperable per Generic Letter 90-05 for ASME Class II Piping. Shutdown of Unit 2 to Mode 3 commenced at 0735. Code repairs are being performed and the technical specification required shutdown (LCO 3.0.3/3.6.1.B) is expected to be stopped once one CFCU train is returned to operability and the other is isolated to meet technical specification LCO 3.6.1. 'Containment.'"

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41549
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE SAUER
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/30/2005
Notification Time: 14:43 [ET]
Event Date: 03/30/2005
Event Time: 09:00 [EST]
Last Update Date: 03/30/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
JAMES TRAPP (R1)

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

FITNESS FOR DUTY REPORT - UNDER INFLUENCE OF ALCOHOL

A non-licensed employee was determined to be under the influence of alcohol during a new employee pre-screening evaluation. The employee never had access to the plant. Contact the Headquarters Operations Officer for additional details.

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Power Reactor Event Number: 41550
Facility: HADDAM NECK
Region: 1 State: CT
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MICHAEL E BACA
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/30/2005
Notification Time: 17:57 [ET]
Event Date: 03/30/2005
Event Time: 16:35 [EST]
Last Update Date: 03/30/2005
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
1 N N 0 Decommissioned 0 Decommissioned

Event Text

OFFSITE NOTIFICATION DUE TO DISCOVERY OF LEGACY OIL SPILL

During demolition of the auxiliary building, a 3 cubic yard front end loader picked up a load of dirt which was discolored and had a strong smell of diesel fuel oil. Excavation was suspended for investigation. At this time the extent of the contaminated area is unknown as well as the potential for ground water contamination.

The licensee notified the National Response Center (Report # 754298) as well as the Connecticut Department of Environmental Protection. The licensee will notify NRC Region I.

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Power Reactor Event Number: 41551
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JEFF YEAGER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/30/2005
Notification Time: 18:13 [ET]
Event Date: 03/30/2005
Event Time: 16:00 [EST]
Last Update Date: 03/30/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
KENNETH RIEMER (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

IDENTIFICATION OF DESIGN AND OPERATING PROCEDURE DEFICIENCIES

The following information was provided by the licensee (licensee text in quotes):

"On March 7, 2005, a condition assessment and resolution document was initiated to document several possible design and operating procedure deficiencies affecting Appendix R and Station Blackout (SBO) events. The deficiencies were identified during development of a proposed modification affecting existing Appendix R and SBO power supplies. On March 30, 2005, it was determined that the applicable Appendix R success criteria could not be assured under all of the postulated scenarios described in the Updated Final Safety Analysis Report (UFSAR). Specifically, during the scenarios where Combustion Turbine Generator (CTG) 11-1 (the dedicated Appendix R alternate power source) or other station CTGs are operating in parallel with the grid, availability of the alternate power source under Appendix R and SBO scenarios cannot be assured. Therefore, this event is being reported under 50.72(b)(3)(ii)(B). Actions to address the potentially affected Appendix R and SBO scenarios were put in place on March 7, 2005, when the deficiencies were identified. The NRC Resident Inspector has been notified."

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