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Event Notification Report for August 13, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/12/2010 - 08/13/2010

** EVENT NUMBERS **


46166 46169 46171

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General Information or Other Event Number: 46166
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: RF MICRO DEVICES
Region: 1
City: GREENSBORO State: NC
County: GUILFORD
License #: 041-1759-OG
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSON
HQ OPS Officer: VINCE KLCO
Notification Date: 08/10/2010
Notification Time: 14:14 [ET]
Event Date: 11/23/2009
Event Time: [EDT]
Last Update Date: 08/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARC FERDAS (R1DO)
MICHELE BURGESS (FSME)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT INVOLVING UNACCOUNTED FOR IONIZERS

The following information was received by fax:

"[The North Carolina Radiation Protection Section] received a telephone call and an e-mail from the [Radiation Safety Officer] RSO with RF Micro Devices [RFMD] in Greensboro that they had just resolved on issue with NRD,LLC that there were 24 Ionizers that were unaccounted for in RFMD inventory as of November 4, 2009 when they shipped by [common carrier]. [There were] 34 model P2021 ionizers (1.3 ounces each) in one box weighing 5 pounds to NRD,LLC for disposal. NRD,LLC is located at 2937 Alt. Blvd., Grand Island, NY 14072. The package was shipped by [common carrier] with a package reference # 677000/99562. NRD,LLC signed for 1 box, but only reported 10 ionizers were received on Nov. 23. 2009. At this point RFMD and NRD began discussions as to what happened to the other 24 ionizers(serial numbers A2GL910 thru A2GL933). Both sites have investigated, but cannot account for these ionizers.

"Please note-These ionizers are listed by NRD,LLC as Nuclecel Static Eliminators-Model P-2021 containing 10 mCi each of polonium 210 with a 1 year shelf life."

North Carolina Incident Number: 10-38

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

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Power Reactor Event Number: 46169
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: C. STEFFES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/12/2010
Notification Time: 08:04 [ET]
Event Date: 08/12/2010
Event Time: 03:58 [CDT]
Last Update Date: 08/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JAMNES CAMERON (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

UNIT 1 REACTOR AUTOMATIC SCRAM DUE TO TURBINE TRIP

"While performing a main condenser flow reversal at 0358 [CDT] on August 12, 2010 the Unit 1 reactor received an automatic scram on turbine stop valve closure. Turbine stop valve closure was initiated from a turbine trip on low vacuum. Reactor water level decreased to approximately -3 [inches], which resulted in automatic Group II and III isolations as expected. All systems responded properly to the event. Unit One remains in Mode 3, maintaining reactor pressure with reactor water level in the normal level band. The cause of the event is still under investigation.

"Unit 2 was unaffected by the event and remains at 100% power.

"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)."

All rods fully inserted. Normal feedwater is supplying the reactor with decay heat removal via the turbine bypass valves. No safety relief valves lifted during the transient. The transient was initiated during the condenser flow reversal when one of the flow reversal valves failed to fully reverse the flow. This resulted in inadequate heat transfer to circ water at full power operation causing the condenser vacuum to increase. In addition, the condenser vacuum trip of the turbine appears to have initiated before it was actually required. Overall, the scram was characterized as uncomplicated and all systems functioned as required.

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Power Reactor Event Number: 46171
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/12/2010
Notification Time: 23:50 [ET]
Event Date: 08/12/2010
Event Time: 19:52 [CDT]
Last Update Date: 08/13/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JAMNES CAMERON (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 76 Power Operation 76 Power Operation
2 N Y 82 Power Operation 82 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO ENVIRONMENTAL CONDITIONS RESULTING IN ELEVATED ULTIMATE HEAT SINK TEMPERATURE

"At 2050 [CDT] on 8/12/10, LaSalle Unit 1 and Unit 2 commenced a Plant Shutdown. At 1952 [CDT] on 8/12/10, LaSalle Ultimate Heat Sink exceeded the 101.25?F limit per Technical Specification LCO 3.7.3, Condition B. Per Technical Specification LCO 3.7.3, Required Action B.1, both Unit 1 and Unit 2 are to be in Mode 3 (Hot Shutdown) in 12 hours. Per Technical Specification LCO 3.7.3 Required Action B.2, both Unit 1 and Unit 2 are to be in Mode 4 (Cold Shutdown) in 36 hours. Technical Specification LCO 3.7.3, Ultimate Heat Sink requires that both Unit 1 and Unit 2 to be in MODE 3 by 8/13/10 at 0752 [CDT] and MODE 4 by 8/14/10 at 0752 [CDT].

"Unit 1 was initially at 76% Power due to a response to elevated Main Condenser In-Leakage, not related to the Ultimate Heat Sink High Temperature. Unit 2 was initially at 82% Power due to elevated Condensate Temperature and in response to worsening Main Condenser Backpressure. For Unit 2, both of these parameters were related to the elevated Ultimate Heat Sink Temperature.

"The Ultimate Heat Sink Temperature is currently 101.33?F. All Systems are responding as expected."

This condition is a result of the hot environmental conditions and is not due to any equipment problems or other operating issues at the site.

The licensee has notified the NRC Resident Inspector.

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