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Event Notification Report for August 17, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/14/2009 - 08/17/2009

** EVENT NUMBERS **


45248 45259 45264 45265

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Power Reactor Event Number: 45248
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RAYMOND MARTIN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/06/2009
Notification Time: 10:25 [ET]
Event Date: 08/06/2009
Event Time: 10:00 [EDT]
Last Update Date: 08/14/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MEL GRAY (R1DO)

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

EMERGENCY OPERATIONS FACILITY PLANNED MAINTENANCE

"At approximately 1000, on Thursday, August 6, 2009, the heating, ventilation, air conditioning (HVAC), and filtration system of the Millstone Power Station (MPS) Emergency Operations Facility (EOF) will be removed from service to perform maintenance to improve the reliability and functionality of the system.

"The EOF is located inside the site's boundary approximately one mile from the protected area of the plant. As a result of this maintenance, the EOF will be unavailable for approximately 12 days. If an emergency requiring the use of the EOF is declared during this maintenance period, the designated alternate EOF, which is also located on site, will be utilized. The Station Emergency Response Organization (SERO) has been informed of this condition.

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii). Millstone will notify the NRC upon completion of the planned maintenance activities and restoration of the EOF which is currently anticipated to occur on August 18, 2009.

"The licensee has notified the NRC Sr. Resident Inspector."

* * * UPDATE ON 8/14/2009 AT 1524 FROM MIKE MARTELL TO MARK ABRAMOVITZ * * *

The EOF was declared operable at 1324 EDT.

Notified the R1DO (Cook).

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General Information or Other Event Number: 45259
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: PAVETEX ENGINEERING AND TESTING INC
Region: 4
City: LUBBOCK State: TX
County:
License #: 05533
Agreement: Y
Docket:
NRC Notified By: RUBEN CORTEZ
HQ OPS Officer: JASON KOZAL
Notification Date: 08/12/2009
Notification Time: 18:01 [ET]
Event Date: 08/11/2009
Event Time: 16:30 [CDT]
Last Update Date: 08/12/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
ANDREW MAUER (FSME)
ILTAB VIA EMAIL ()

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

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER SUBSEQUENTLY RECOVERED

The following was provided by the State via e-mail:

"[An] 8 mCi Cs-137 source [was] stolen from PaveTex at 16:30 CST 8/11/2009 at the O'Reilly Auto Parts on US 87 in Big Spring, TX. [The] Source was in a Troxler model 4640 thin layer density gauge, serial no. 1280. [The State was] notified [at] 15:30 CST on 8/12 that the source was located by a member of the public at the TA Truck stop on I-20 at US-87 north of town and that [the] site RSO had sent someone to pick up [the] gauge."

Texas Incident # - I-8654

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.

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Power Reactor Event Number: 45264
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE JESTER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/15/2009
Notification Time: 00:51 [ET]
Event Date: 08/14/2009
Event Time: 19:58 [EDT]
Last Update Date: 08/15/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MARVIN SYKES (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

Event Text

HPCI INOPERABLE DUE TO AUTOMATIC CLOSURE OF INBOARD ISOLATION VALVE

"On 8/14/2009 at 19:58, the Unit 1 High Pressure Coolant Injection (HPCI) System inboard isolation valves automatically isolated. Inboard isolation was caused by an inadvertent high ambient temperature signal from the HPCI steam leak detection module. Local temperatures were confirmed to be normal and no steam leak was identified. With the HPCI system steam supply isolated, the HPCI system is inoperable in accordance with Technical Specification 3.5.1. HPCI is a single-train safety function system.

"The initial safety significance of this condition is considered to be minimal. The Reactor Core Isolation Cooling (RCIC) system, Automatic Depressurization System (ADS), and Low Pressure Emergency Core Cooling systems (ECCS) remain operable at this time. Actions have been taken to protect redundant safety systems. Unit 1 risk condition is currently yellow due to the concurrent inoperability of a single loop of Residual Heat Removal (RHR) Service Water for system maintenance.

"The HPCI system remains isolated and inoperable pending further troubleshooting of the inboard isolation.

"The NRC resident has been notified."

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Power Reactor Event Number: 45265
Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FINDLEY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/15/2009
Notification Time: 20:06 [ET]
Event Date: 08/15/2009
Event Time: 16:06 [CDT]
Last Update Date: 08/15/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JAMNES CAMERON (R3DO)

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 DUE TO A TURBINE TRIP

"At 1606 CDT on August 15, 2009, LaSalle Unit 2 automatically scrammed due to a turbine trip. The turbine trip occurred during weekly turbine trip testing. Two safety relief valves actuated [and reseated] in the relief mode on the turbine trip. The reactor water cleanup system isolated during the transient (not being reported as there was no isolation in multiple systems). The plant is stable with reactor pressure control to the main condenser via the main steam isolation valves. The plant is planning to remain in hot shutdown pending [turbine] electro-hydraulic (EHC) system troubleshooting and repair."

All control rods fully inserted during the scram. The site is aligning the ring bus for the normal shutdown electrical lineup. Reactor water level is being maintained using the main feedwater system and decay heat is being removed via the turbine bypass valves.

The licensee notified the NRC Resident Inspector.

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Thursday, March 29, 2012