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Event Notification Report for November 23, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/22/2010 - 11/23/2010

** EVENT NUMBERS **


46431 46432 46433 46434 46435

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Power Reactor Event Number: 46431
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DAVID BARNETT
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/22/2010
Notification Time: 23:32 [ET]
Event Date: 11/22/2010
Event Time: 17:47 [CST]
Last Update Date: 11/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BILLY DICKSON (R3DO)

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

Event Text

VALVES IDENTIFIED OPEN IN MODE 2 THAT SHOULD HAVE BEEN CLOSED

"At 1547 CST, November 22, 2010, the reactor mode was changed from Mode 4 to Mode 2 with the main steam drain valves, which are primary containment isolation valves, tagged open with power removed from their respective breakers. The valves were tagged to comply with S/D [Shutdown] operating procedure requirements. The valves should have been restored prior to making the mode change. The main steam line drain isolation valves MO-2373 and MO-2374 were restored at 1747 CST and verified at 1755 CST. Startup was held for determination of further actions needed. Reactor startup recommenced at 2200 CST. Currently the reactor is not critical."

The licensee notified the NRC Resident Inspector. The licensee notified the Minnesota State Duty Officer.

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Other Nuclear Material Event Number: 46432
Rep Org: VA CARIBBEAN HEALTHCARE ADMIN.
Licensee: DEPARTMENT OF VETERAN AFFAIRS, NATIONAL HEALTH PHYSICS PROG.
Region:
City: SAN JUAN State:
County: PUERTO RICO
License #:
Agreement: N
Docket:
NRC Notified By: THOMAS HUSTON
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/23/2010
Notification Time: 14:24 [ET]
Event Date: 10/31/2010
Event Time: [EST]
Last Update Date: 11/23/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
DON JACKSON (R1DO)
BILLY DICKSON (R3DO)
GLENDA VILLAMAR (FSME)

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

Event Text

VA CARRABEAN HEALTH CARE SYSTEM IN SAN JUAN, PUERTO RICO - LOST TRITIUM EXIT SIGNS

The Department of Veterans Affairs, Veterans Health Administration, National Health Physics Program reported the loss of generally licensed devices (self-illuminating tritium exit signs).

"This report is required by 10 CFR 31.5(a)(10) and 10 CFR 20.2201(a)(1). Four (4) tritium exit signs are declared to be missing by the VA Caribbean Healthcare System, San Juan, Puerto Rico. The signs had been possessed under general licensing provisions of 10 CFR 31.5.

"The signs were model number SLXTU1RB15 manufactured by Foreverlite, Inc., and contained about 9.5 curies of tritium each. The signs had been removed from use by the facility earlier this year [March 19, 2010] and placed into temporary storage at the facility pending transfer to an authorized recipient. There are no indications that the signs were damaged or that these circumstances have resulted in any radiation exposure to individuals.

"A 30-day written report of the event will be provided to the NRC as required in 10 CFR 20.2201(a)(2)."

It was not determined the signs were missing until October 2010. A thorough search was conducted but failed to locate the missing signs.

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Power Reactor Event Number: 46433
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MARK EGHIGIAN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/23/2010
Notification Time: 14:53 [ET]
Event Date: 11/23/2010
Event Time: 11:45 [EST]
Last Update Date: 11/23/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BILLY DICKSON (R3DO)

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

OTHER GOVERNMENT AGENCY NOTIFICATION DUE TO SEWAGE LEAK

"On 11/23/10 at 1145 EST, a verbal report to the Michigan Department of Natural Resources & Environment (MDNRE) was made relating to a sewage leak to the ground from the Training Building restrooms. The onsite Facilities Maintenance Journeyman discovered mud and stones while clearing a drain to relieve a blockage. An immediate repair of the broken drain is being implemented. The plant is currently in Mode 4, in Refueling Outage 14 (RF14). Since a verbal report was made to the MDNRE, this is considered a News Release / Notification of Other Government Agency, and is reportable under 10CFR50.72(b)(2)(xi)."

The licensee notified the NRC Resident Inspector. The licensee also notified the Monroe County Health Department.

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Power Reactor Event Number: 46434
Facility: SURRY
Region: 2 State: VA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JERRY ASHLEY
HQ OPS Officer: PETE SNYDER
Notification Date: 11/23/2010
Notification Time: 15:31 [ET]
Event Date: 10/26/2010
Event Time: 23:56 [EDT]
Last Update Date: 11/23/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DANIEL RICH (R2DO)

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

Event Text

INVALID ACTUATION OF HIGH CONSEQUENCE LIMITING SAFEGUARDS AND SAFETY INJECTION SYSTEMS

"This telephone notification is being made for an invalid actuation under 10 CFR 50.73(a)(2)(iv)(A) following the reporting guidance of 10 CFR 50.73(a)(1).

"With Unit 1 at cold shutdown (about 105 degrees Fahrenheight and depressurized), an invalid actuation of the Unit 1 'A' train of the High Consequence Limiting Safeguards (HI CLS) system and Unit 1 'A' train of the Safety Injection (SI) system occurred at 23:56 during setup for 'H' Bus Logic Testing. Plant systems and components responding to the HI CLS and SI 'A' train signals started and functioned successfully as designed (with the exception of those systems and components procedurally rendered inoperable due to the RCS being below 350 degrees Fahrenheight and 450 psig). The HI CLS and SI 'A' trains were reset and the affected systems were restored to their pre-event configurations.

"Specific trains and systems that actuated for the 'A' train of HI CLS and SI are described below:
"- With the unit at cold shutdown, one high head pump was running (the two redundant pump controls were in the pull to lock position in compliance with Technical Specifications). The 'A' train High Head Safety Injection motor operated valves re-aligned such that the running high head pump provided flow to the RCS cold legs from the Refueling Water Storage Tank (RWST). During this time the pressurizer level increased from approximately 23 percent to about 42 percent.
"- Auxiliary Feedwater (AFW) Pump motor operated valves opened but no flow was delivered to the steam generators since the AFW pumps were in pull to lock.
"- The 'A' train containment isolation valves closed, isolating the 'A' Residual Heat Removal (RHR) heat exchanger. However, shutdown cooling was previously aligned to the 'B' train RHR and therefore shutdown cooling was uninterrupted. Containment isolation valves were later restored to a normal alignment.
"- One train of Auxiliary Ventilation actuated and was restored to normal after the Safety Injection signal was reset.
"- Emergency Diesel Generator (EDG) No. 1 started but did not load since its associated Emergency Bus remained energized by offsite power. The EDG was stopped and returned to automatic.

"An apparent cause evaluation is in progress."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46435
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KIMBERLY BASS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/23/2010
Notification Time: 15:35 [ET]
Event Date: 11/10/2010
Event Time: 00:24 [EST]
Last Update Date: 11/23/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DANIEL RICH (R2DO)

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

Event Text

TELEPHONE NOTIFICATION IN LIEU OF WRITTEN LER - INVALID ACTUATION OF MOTOR DRIVEN AUXILIARY FEEDWATER PUMP

"Event: Invalid actuation of the 'B' Motor Driven Auxiliary Feedwater (MDAFW) pump.

"Report Type: This 60-day telephone notification is being made under 10CFR50.73(a)(2)(iv)(A) and 10CFR50.73(a)(1).

"Description: On November 10, 2010, the 'A' Main Feedwater Pump (MFP) was started per plant operating procedures. When the 'A' MFP was started, there was a partial activation of the Auxiliary Feedwater System with the start of the 'B' MDAFW.

"The plant was in Mode 3 after completing refueling outage 16 during this event. Actual plant conditions and parameters did not exist that required an automatic start of the 'B' MDAFW pump. Therefore, this actuation is classified as invalid. The system started and functioned successfully.

"This invalid actuation was entered into the corrective action program as NCR-432566."

The licensee notified the NRC Resident Inspector.

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Tuesday, August 11, 2015