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Event Notification Report for April 25, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/22/2005 - 04/25/2005

** EVENT NUMBERS **


41575 41613 41615 41623 41624 41625 41627 41628 41629 41631

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 41575
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MICHAEL NEMCEK
HQ OPS Officer: ARLON COSTA
Notification Date: 04/08/2005
Notification Time: 05:32 [ET]
Event Date: 04/07/2005
Event Time: 20:28 [EST]
Last Update Date: 04/24/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KENNETH O'BRIEN (R3)

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

Event Text

POTENTIAL INABILITY TO SAFE SHUTDOWN DUE TO INOPERABLE EMERGENCY DIESEL GENERATORS

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

"All three divisions of Emergency Diesel Generators were declared inoperable due to performing at risk design changes on the operable diesel. The design change was removed from the division one diesel and it was declared available at 2045 on 4/7/05. All three diesels remain inoperable."

Perry 1 is currently shutdown in refueling mode 5 and no core alterations are in progress. The licensee will notify the NRC Resident Inspector.

* * * RETRACTION FROM KEN MEADE TO PETE SNYDER AT 0852 EDT ON 4/24/05 * * *

"Update to Event Notification (ENF 41575) Retraction:

"An 8-hour notification was made on April 7, 2005 under 10CFR50.72(b)(3)(v) for the loss of the safety function. The report was made due to declaring division 1 diesel generator inoperable at 2028 hours on April 7, 2005 with Division 2 and 3 inoperable for unrelated refuel outage activities. Division 1 diesel generator was declared inoperable as a result of performing an at-risk design change on the exhaust system, i.e., installing insulation blankets on the exhaust piping. The at-risk design change was removed from the division one diesel generator by 2045 hours on April 7, 2005. No other actions were taken during the course of events that would have otherwise rendered the Division 1 diesel generator inoperable.

"An evaluation was completed on April 8, 2005 confirming that the additional weight of the insulation on the exhaust piping had no impact on diesel generator operability. Division 1 diesel generator was subsequently declared operable at 0534 hours on April 9, 2005.

"Since there was no loss of safety function, there is no reportable condition. Since there was no reportable condition. ENF 41575 is retracted."

The licensee has notified the NRC Resident Inspector. Headquarters Operations Officer notified R3DO (Hills).

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General Information or Other Event Number: 41613
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CALIFORNIA STATE POLYTECHNIC UNIVERSITY
Region: 4
City: POMONA State: CA
County:
License #: 0496-19
Agreement: Y
Docket:
NRC Notified By: DAVID LITTLE
HQ OPS Officer: MIKE RIPLEY
Notification Date: 04/19/2005
Notification Time: 16:11 [ET]
Event Date: 01/04/2005
Event Time: [PST]
Last Update Date: 04/19/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL SHANNON (R4)
MICHELE BURGESS (NMSS)
TAS (EMAIL) ()

Event Text

CALIFORNIA AGREEMENT STATE REPORT - MISSING TRITIUM EXIT SIGNS

The following information was provided by the State via facsimile:

"[The University] reported the loss of six generally licensed tritium exit signs. They do a quarterly inventory and noticed six were missing when they did their inventory on 01-04-05. The previous inventory had been on 06-20-04. They suspect students may have stolen the signs. The current activity estimate for all six signs is 27.6 Curies, with the highest sign having an estimated current activity of 7.5 Curies."

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General Information or Other Event Number: 41615
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: BURCAW GEOTECHNICAL GROUP
Region: 1
City: RUSKIN State: FL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/19/2005
Notification Time: 20:06 [ET]
Event Date: 04/19/2005
Event Time: 19:45 [EDT]
Last Update Date: 04/19/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID SILK (R1)
JOE GIITTER (NMSS)
TAS (E-MAIL) ()

Event Text

FLORIDA AGREEMENT STATE REPORT OF MISSING TROXLER GAUGE

The Florida Bureau of Radiation Control reported a missing Troxler moisture density gauge. The agreement state licensee, Burcaw Geotechnical Group, was using the gauge at a site located in Ruskin, Florida. The gauge overpack, which was thought to contain the gauge, was picked up at the end of the work day and placed into a truck. While in transit, the driver realized that he had not been verified the gauge was actually in the overpack. He checked the overpack and found it to be empty. He returned to the job site and conducted a search but could not locate the gauge.

The licensee informed the Florida Bureau of Radiation Control. The Bureau of Radiation Control requested the licensee to contact the police and report the gauge missing. The Troxler gauge (serial #34752) contained a 40 milliCurie Am-241/Be source and a 10 milliCurie Cs-137 source.

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Fuel Cycle Facility Event Number: 41623
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PIKETON State: OH
County: PIKE
License #: GDP-2
Agreement: Y
Docket: 0707002
NRC Notified By: ERIC SPAETH
HQ OPS Officer: PETE SNYDER
Notification Date: 04/22/2005
Notification Time: 10:55 [ET]
Event Date: 04/21/2005
Event Time: 20:13 [EST]
Last Update Date: 04/22/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
CAUDLE JULIAN (R2)
RICH CORREIA (NMSS)

Event Text

AUTOCLAVE SHUTDOWN DUE TO HIGH CONDENSATE


"On 04/21/05 at 2013 hours, Autoclave #2 in the X-343 Facility experienced a Steam Shutdown due to high condensate level alarms (A) and (B) actuating. The autoclave was in an applicable TSR mode (Mode II, Heating) at the time of the alarm actuations. The autoclave was placed in Mode VII (Shutdown) and declared INOPERABLE by the Plant Shift Superintendent (PSS). An investigation is underway to determine the cause of the actuations. No release of radioactive material occurred as a result of this incident. This event is being reported in accordance with UE2-RA RE1030, Appendix D. J. 2. Safety System Actuations. NRC, Region II has been notified of this event."

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Power Reactor Event Number: 41624
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN TAYLOR
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/22/2005
Notification Time: 14:01 [ET]
Event Date: 04/22/2005
Event Time: 06:00 [EST]
Last Update Date: 04/22/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
DAVID SILK (R1)

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

Event Text

CONTRACT EMPLOYEE TESTED POSITIVE DURING A FOR-CAUSE FITNESS FOR DUTY TEST

A contract foreman tested positive for alcohol during a for-cause alcohol test. The employee had not performed any work and was not allowed access to the site. The employee's access to the site was terminated.

The NRC Resident Inspector was informed.

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Power Reactor Event Number: 41625
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: RORY SMITH
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/22/2005
Notification Time: 15:24 [ET]
Event Date: 04/22/2005
Event Time: 14:13 [EST]
Last Update Date: 04/22/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
JOEL MUNDAY (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

POTENTIALLY CONTAMINATED PERSON TAKEN OFFSITE VIA AMBULANCE

"Individual received laceration to right leg while working in Unit 1 RB (Reactor Building). Individual transported to Oconee Memorial hospital with potential contamination."

Ambulance came from Oconee Memorial Hospital. It is site practice to send a Rad Tech along with any potentially contaminated person.

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

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Power Reactor Event Number: 41627
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GREG BAKER
HQ OPS Officer: BILL GOTT
Notification Date: 04/23/2005
Notification Time: 10:26 [ET]
Event Date: 04/23/2005
Event Time: 07:30 [CST]
Last Update Date: 04/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
DAVID HILLS (R3)

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 N 0 Refueling 0 Refueling

Event Text

FITNESS FOR DUTY: ALCOHOL

A non-licensed contract employee was determined to be under the influence of alcohol during a for cause test. The employee's access to the plant has been suspended. Contact the Headquarters Operations Officer for additional details.

The licensee will notify the Resident Inspector.

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Power Reactor Event Number: 41628
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/23/2005
Notification Time: 14:58 [ET]
Event Date: 04/23/2005
Event Time: 10:45 [EST]
Last Update Date: 04/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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

PLANT LOST ERDADS (EMERGENCY RESPONSE DATA ACQUISITION DISPLAY SYSTEM) DATA LINK CAPABILITY

"On April 23, 2005, at 10:45 hours St. Lucie Plant last the ERDADS NRC Data Link capability. The System Engineer reports that the ERDADS periphery switch failed to swap to the "A" CPU from the "B" CPU on a auto failover that occurred at 10:45. The switch has been manually swapped and the Data Link has been restored. A work order has been prepared to investigate and repair the cause for this failure."


The NRC resident Inspector was notified.

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Power Reactor Event Number: 41629
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JOHN ARONSON
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/23/2005
Notification Time: 18:43 [ET]
Event Date: 04/23/2005
Event Time: [MST]
Last Update Date: 04/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
MICHAEL SHANNON (R4)

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

Event Text

DISCOVERED TWO AXIAL INDICATIONS ON INSIDE DIAMETER OF REACTOR VESSEL HEAD PENETRATION

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up will be made via the ENS or under the reporting requirements of 10CFR50.73.

"On April 23, 2005, at approximately 11:35 Mountain Standard Time (MST) engineering personnel performing preplanned in-service examinations of reactor vessel head vent penetration in accordance with procedure requirements discovered two axial indications in the Palo Verde Nuclear Generating Station Unit 2 reactor vessel head vent penetration. The indications are located on the inner diameter surface of the pipe adjacent to the J-weld to the head and are part of the RCS pressure boundary. The indications are characterized as axial, estimated less than 0.080 inch deep, approximately 0.1 inch long, and oriented at approximately 90 degrees from each other. The indications are not through-wall. There is no evidence of RCS pressure boundary leakage.

"Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.4.14 permits no reactor coolant system (RCS) pressure boundary leakage and there is no evidence of pressure boundary leakage. Nevertheless, the indications are being conservatively identified as abnormal degradation of the reactor coolant system pressure boundary and will necessitate taking corrective action to restore the barrier's capability. Therefore, the ENS notification of this event is in accordance with 10CFR50.72(b)(3)(ii)(A). The Unit had been shutdown for its 12th refueling outage and was being maintained de-fueled for maintenance.

"No ESF actuations occurred and none were required. There were no structures, systems, or components that were inoperable at the time of discovery that contributed to this condition. There were no failures that rendered a train of a safety system inoperable and no failures of components with multiple functions were involved. The event did not result in the release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public.

" An investigation of this event will be conducted in accordance with PVNGS corrective action program."


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

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Power Reactor Event Number: 41631
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/24/2005
Notification Time: 21:39 [ET]
Event Date: 04/24/2005
Event Time: 21:30 [EST]
Last Update Date: 04/24/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID SILK (R1)
MOHAMED SHANBAKY (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

SPDS (SAFETY PARAMETER DISPLAY SYSTEM) IS DOWN FOR PLANNED MAINTENANCE

"At 2130 hours on 04/24/2005 the Unit 1 SPDS system will be removed from service for planned maintenance (cable rework). The duration of work is expected to be 32 hours (scheduled for completion at 0530 hours on 04/26/2005).

"ERDS will remain operable during the work window but several points will not be available. For example 23 of 58 ERDS points will be unavailable while SPDS is out of service. However, the ERDS system will still be operable and transmit the remaining points.

"Loss of Emergency Assessment Capability - A review of the ability of the Emergency organization to function without SPDS was performed. Alternate sources for many of the points in SPDS were identified and are contained on an Emergency Plan format in PICSY (plant integrated computer system). Those points not available from PICSY can be obtained from the control room. With these compensatory actions and the communications in place between the facilities, there will not be a major loss of emergency assessment capability.

"Since the Unit 1-SPDS computer system will be unavailable for greater than 8 hours, this is considered a Loss of Emergency Assessment Capability and reportable under 10CFR50.72(b)(3)(xiii)."


The NRC Resident Inspector was notified.

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