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Event Notification Report for June 22, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/19/2009 - 06/22/2009

** EVENT NUMBERS **


45128 45131 45134 45135 45142 45143 45145 45146 45147

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Power Reactor Event Number: 45128
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE HENRY
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 06/13/2009
Notification Time: 09:19 [ET]
Event Date: 06/13/2009
Event Time: 09:45 [EDT]
Last Update Date: 06/19/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GERALD MCCOY (R2DO)

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

TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE

"Planned maintenance activities are being performed today (June 13, 2009) on the Vogtle Nuclear Plant's Technical Support Center (TSC) power sources. This work activity is planned to be performed and completed expeditiously within approximately 3 days (78 hours). This maintenance activity is to perform a transformer replacement, perform preventative maintenance on several circuit breakers, perform preventative maintenance on the TSC HVAC unit, repair a leak on the Back-Up D/G [diesel generator] which provides a back-up power supply to the TSC HVAC, and other minor maintenance activities.

"If an emergency condition occurs that requires activation of the Technical Support Center during this work activity, contingency plans are in place to restore the TSC to fully functional status, with the time to restoration dependent on the stage of the work activity at the time the emergency occurs. Plans are to utilize the Shift Manager's Office in the Control Room as the Backup TSC for any declared emergency during the time the work activity is being performed. Procedure 91201-C, Activation and Operation of the Technical Support Center, provides instructions to direct TSC management to the Control Room to continue TSC activities if it is necessary to relocate from the primary TSC. At the beginning of the TSC outage, the ENN [Emergency Notification Network] and ERDS [Emergency Response Data System] will not be available until temporary power is being provided. This outage for the communications equipment will last from 2-4 hours, at which time they will be available.

"This event is reportable per 10 CFR 50.72 (b)(3)(xiii) as described in NUREG-1022, Rev. 2 since this work activity affects an emergency response facility for the duration of the evolution.

"The licensee has notified the NRC Resident Inspector."

The licensee provided notification of this issue prior to initiation of the maintenance per the licensee's 10 CFR 50.54(q) evaluation for the activity. The licensee intends to update this report when the temporary modification is completed such that the ERDS system is returned to service.

* * * UPDATE FROM MIKE HENRY TO HOWIE CROUCH @ 0735 EDT ON 6/15/09 * * *

The licensee has returned the ERDS system to service using temporary power. Preventive maintenance still continues on the TSC. The licensee has notified the NRC Resident Inspector.

Notified R2DO (McCoy).

* * * UPDATE ON 6/19/2009 AT 1153 FROM RICHARD COTTY TO MARK ABRAMOVITZ * * *

The ventilation system has been returned to its normal power supply at 1121 on 6/19/2009.

The licensee will notify the NRC Resident Inspector.

Notified the R2DO (Bartley).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45131
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: NICK RULLMAN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/13/2009
Notification Time: 19:20 [ET]
Event Date: 06/13/2009
Event Time: 11:30 [PDT]
Last Update Date: 06/19/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
GEOFFREY MILLER (R4DO)

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

DEGRADED CONDITION DUE TO REACTOR COOLANT PRESSURE BOUNDARY LEAK

"This notification is made pursuant to 10CFR50.72(b)(3)(ii) to report degradation of a principal safety barrier. During ASME Section XI (Table 2500-1 Code Category B-P, Item Number B15.10) refuel outage system leak testing of the reactor vessel and reactor coolant pressure boundary, leakage of approximately 1 drop per minute was detected from the bonnet vent leak-off connection on the reactor recirculation pump inlet isolation valve (RRC-V-23A) in the reactor coolant recirculation loop A. This condition is consistent with example (A)(2) provided in NUREG-1022, rev. 2 'Event Reporting Guidelines 10CFR50.72 and 50.73.' This example indicates that reporting under the above criteria is required for 'Welding or material defects in the primary coolant system which cannot be found acceptable under ASME Section XI, Table IWB-3410-1, 'Acceptance Standards.'

"A cause evaluation will be performed and a 60-day follow-up report provided pursuant to the corresponding 10CFR50.73 reporting requirement."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM FRED SCHILL TO VINCE KLCO AT 1955 EDT ON 6/19/09 * * *

"Subsequent evaluation of the point where leakage was observed reveals that the 1 drop per minute leakage from RRC-V-23A was actually emanating from the packing chamber leak-off connection and not from the bonnet vent leak-off connection as reported. The packing chamber leak-off connection provides a means to monitor leakage from the packing. It does not provide a pressure containing function at its location on the valve and, therefore, is not part of the Reactor Coolant Pressure Boundary (RCPB) as defined in Part 50.2.

"Since the packing chamber leak-off connection is not a pressure-retaining structure it is not part of the RCPB, therefore the condition reported in event report #45131 is not a degradation of a principle safety barrier and is not reportable pursuant to Part 50.72(b)(3)(ii)(A). For this reason, the subject event report is hereby retracted."

The licensee notified the NRC Resident Inspector.

R4DO (Cain) notified.

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General Information or Other Event Number: 45134
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: BECKMAN COULTER INSTRUMENTS
Region: 4
City: BREA State: CA
County:
License #: 0441-30
Agreement: Y
Docket:
NRC Notified By: KATHLEEN HARKNESS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/16/2009
Notification Time: 15:10 [ET]
Event Date: 06/10/2009
Event Time: [PDT]
Last Update Date: 06/16/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHUCK CAIN (R4DO)
ANDREA KOCK (FSME)

Event Text

AGREEMENT STATE - LEAKING LIQUID SCINTILLATION COUNTER SOURCE

The following information was received from the State of California Radiologic Health Branch via e-mail:

"On June 10, 2009, the RSO for Beckman Coulter Instruments reported that a 21.5 year old Cs-137 source removed during decommissioning from a Beckman Coulter LSC (Liquid Scintillation Counter): model LS 5801 counter (s/n 7015110) was found to have 0.013 microcuries removable contamination. The reportable limit is 0.005 microcuries. It was removed from the LS counter by a Beckman Field Service Technician and returned to the Beckman Coulter facility in Fullerton for disposal, where the leak test was performed. No other contamination was found inside the LS device. The source part number is 598860, lot # ST1022018 - reference date was 12/18/87. The most probable cause of the leakage was the source holder was cracked due to age. Beckman Coulter has determined that the useful life is 8 years for these sources. The company is replacing all sources older than 8 years as corrective action."

The State provided additional information indicating that the original source activity was 30 microcuries.

CA Report Number 5010-061009

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General Information or Other Event Number: 45135
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: MEMORIAL HOSPITAL
Region: 1
City: JACKSONVILLE State: FL
County:
License #: 2567-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/16/2009
Notification Time: 17:09 [ET]
Event Date: 06/16/2009
Event Time: [EDT]
Last Update Date: 06/16/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ART BURRITT (R1DO)
ANDREW PERSINKO (FSME)

Event Text

AGREEMENT STATE REPORT - MEDICAL EVENT DUE TO DOUBLE ADMINISTRATION OF DIAGNOSTIC DOSE

The following information was received from the State of Florida Bureau of Radiation Control via facsimile:

"Patient received two doses of Thalium-201 (Liquid form - 7.2 milliCurie) for a diagnostic Cardiovascular Procedure in the Nuclear Medicine Department. Two nuclear medicine technologists were working in the same room. Second technologist misunderstood that the first tech had already delivered the first dose. Jacksonville area office will investigate."

Estimated maximum internal organ dose received by patient is 9.36 Rem.

Florida Report FL09-052

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Power Reactor Event Number: 45142
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: FRED CORLEY
HQ OPS Officer: VINCE KLCO
Notification Date: 06/18/2009
Notification Time: 19:26 [ET]
Event Date: 06/18/2009
Event Time: 11:15 [EDT]
Last Update Date: 06/19/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
JONATHAN BARTLEY (R2DO)
ANDREW PERSINKO (FSME)

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

INCOMPLETE TESTING OF RADIOACTIVE WASTE SHIPMENT CONTAINERS

"On June 17, 2009, Catawba prepared a radioactive waste shipment cask for transportation to the Barnwell low level waste disposal facility. The shipment consisted of miscellaneous spent filters and the shipment was made on the same day. On June 18, 2009, Catawba discovered that all of the required conditions of approval in the Certificate of Compliance for the shipping container were not observed in making the shipment. Specifically, Catawba failed to conduct all of the required leak rate tests for the container prior to shipment. According to procedure, leak rate tests of the container's primary lid, secondary lid, and vent line are required to be performed. Contrary to this requirement, leak rate tests of the secondary lid and vent line were not performed. This event will require a written report to the NRC within 60 days pursuant to 10 CFR 71.95(c).

"Catawba is making this ENS notification as a courtesy notification. There is no requirement for Catawba to notify any government agency of this event. However, the State of South Carolina Department of Health and Environmental Control (SC DHEC) will ultimately be made aware of this event by Energy Solutions at Barnwell. There is no evidence that the affected shipping container has actually leaked or is leaking. The secondary lid and vent line were successfully leak rate tested at Barnwell following notification and a request by Catawba management on June 18, 2009.

"Catawba has notified the NRC Senior Resident Inspector of this event."

* * * UPDATE FROM WAYNE JARMAN TO JOE O'HARA AT 1442 ON 6/19/09 * * *

The licensee intends to notify the state warning point as well as York, Gaston, and Mecklenburg Counties.

Notified the R2DO(Bartley).

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Power Reactor Event Number: 45143
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GREG LOOSE
HQ OPS Officer: VINCE KLCO
Notification Date: 06/18/2009
Notification Time: 22:04 [ET]
Event Date: 06/18/2009
Event Time: 21:39 [EDT]
Last Update Date: 06/19/2009
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
ART BURRITT (R1DO)
COLLINS (RAR1)
LEEDS (ET)
FREDERICK BROWN (NRR)
ANTHONY McMURTRAY (IRD)
WIGGINS (NRR)
KETTLES (DHS)
CANUPP (FEMA)

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

EMERGENCY DECLARED DUE TO INDICATED FIRE IN EMERGENCY RESPONSE FACILITY SUBSTATION

At 2139, the licensee declared a Notification of Unusual Event in response to a fire alarm and CO2 activation in the emergency response facility (ERF) substation. The licensee entered emergency action level (EAL) 4.1. The fire brigade responded to assess for damage. No damage was found. The incident was attributed to a spurious activation of the CO2 system. The licensee terminated the unusual event at 2236.

The licensee notified the NRC Resident Inspector. The NRC did not change agency response mode for this event.

* * * UPDATE FROM JAMES DAUGHTERY TO HOWIE CROUCH @ 0135 EDT ON 6/19/08 * * *

The CO2 discharge was isolated to the Emergency Response Facility Substation Building, and the building has been ventilated. Investigation into the cause of the spurious CO2 actuation is ongoing.

Notified the R1DO (Burritt) via email.

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Power Reactor Event Number: 45145
Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ED BURKETT
HQ OPS Officer: JOE O'HARA
Notification Date: 06/20/2009
Notification Time: 15:47 [ET]
Event Date: 06/20/2009
Event Time: 14:17 [EDT]
Last Update Date: 06/20/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JONATHAN BARTLEY (R2DO)

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

Event Text

AUTOMATIC REACTOR SCRAM FROM HIGH REACTOR PRESSURE SCRAM SIGNAL

"Plant Hatch Unit 2 experienced a full reactor scram from the main generator protection circuitry (generator runback circuit). Preliminary indications are that a main generator high temperature signal was received, initiating the generator protection (runback) circuitry and a high reactor pressure scram signal was received during the turbine/generator runback. Investigations into the cause of the generator high temperature signal are ongoing.

"Reactor water level was recovered using the reactor feed system, and reactor pressure was controlled using main turbine bypass valves. All control rods inserted, as expected, during the scram. Other than the cause of the main generator high temperature signal, all systems functioned as expected."

Unit is currently at 837 psig; 540 degrees F in Mode 3. Electrical system is in a normal lineup.

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 45146
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: RANDALL DEWEERDT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/21/2009
Notification Time: 07:42 [ET]
Event Date: 06/21/2009
Event Time: 03:08 [CDT]
Last Update Date: 06/21/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTINE LIPA (R3DO)

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 UNIT 2 EMERGENCY RESPONSE DATA SYSTEM (ERDS) DUE TO A PLANT PROCESS COMPUTER ISSUE

"On June 21, 2009, it was identified that Unit 2 ERDS was unavailable for approximately 3 hours and 1 minute (0208-0509 hours CDT). This was due to the loss of the Unit 2 Plant Process Computer (PPC) interface with ERDS. Unit 2 ERDS was restored when the Unit 2 PPC interface with ERDS was restored. The cause of the Unit 2 PPC interface interruption is under investigation.

"This event is reportable under 10 CFR 50.72(b)(3)(xiii) as a major loss of communications capability.

"The Duty NRC Resident Inspector has been notified."

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Power Reactor Event Number: 45147
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID O'DONNELL
HQ OPS Officer: VINCE KLCO
Notification Date: 06/21/2009
Notification Time: 20:58 [ET]
Event Date: 06/21/2009
Event Time: 17:50 [EDT]
Last Update Date: 06/21/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
CHRISTINE LIPA (R3DO)

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

Event Text

AUTOMATIC REACTOR SCRAM RELATED TO A MAIN TURBINE TRIP

"On June 21, 2009, at approximately 1750 hours, an automatic Reactor Protection System (RPS) actuation occurred at the Perry Nuclear Power Plant, Unit 1. At the time of the event, the plant was in Mode 1 at 100% power. All control rods are inserted into the core and the plant is currently stable, in Mode 3 (Hot Shutdown) with reactor pressure at approximately 930 psig. No Emergency Core Cooling Systems were required or utilized to
respond to the event and there were no other reportable actuations. Reactor coolant level is being maintained in its normal band by the feedwater system and decay heat is being removed by the condenser. The plant is in a normal electrical line-up with all three Emergency Diesel Generators operable and available if needed.

"The cause of the reactor scram is currently under investigation. Preliminary indications are that the cause of the RPS actuation is related to a main turbine trip. The NRC Resident Inspector has been notified."

No safety relief valves lifted during the event and a reactor cooldown is in progress.

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