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Event Notification Report for November 18, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/17/2010 - 11/18/2010

** EVENT NUMBERS **


46268 46420 46421 46425 46426 46428

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46268
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE BORGER
HQ OPS Officer: VINCE KLCO
Notification Date: 09/22/2010
Notification Time: 15:09 [ET]
Event Date: 09/22/2010
Event Time: 08:30 [EDT]
Last Update Date: 11/18/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
GLENN DENTEL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 94 Power Operation 94 Power Operation

Event Text

HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE DUE TO A MINOR LUBE OIL LEAK

"At 0830 [EDT] on 09/22/2010, the Unit 2 High Pressure Coolant Injection (HPCI) system was determined to be inoperable due to a minor lube oil leak on the 'A' supply filter. LCO 3.5.1 for the HPCI system was entered at 0830 [EDT] on 09/22/2010.

"The leak on the 'A' filter could not be immediately corrected. The 'B' filter was placed in service and leak checked satisfactorily. The LCO 3.5.1 action statements were closed at 1454 [EDT] on 09/22/2010.

"This incident is being reported as an event or condition that could have prevented fulfillment of a safety function required to mitigate the consequences of an accident in accordance with 10CFR50.72(b)(3)(v)(D)."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM RONALD FRY TO DONG PARK AT 1609 EST ON 11/18/10 * * *

"At 1501 on September 22, 2010, PPL Susquehanna, LLC reported that the Unit 2 High Pressure Coolant Injection (HPCI) system was inoperable due to a minor lube oil leak on the 'A' supply filter. Subsequent investigation and evaluation determined that HPCI was capable of performing all of its safety functions with the identified oil leak. The operability determination was based on the following:

"Investigation of the leak identified that the installed filter housing cover o-ring was undersized and had to be inappropriately stretched to fit in the o-ring groove in the housing cover. The cover is torqued to 75 ft-lbs by four bolts on the outer diameter of the cover, enclosing the o-ring in a metal to metal connection. There is no concern for the o-ring to extrude from the cover under this configuration. The worst case that can be postulated as a result of the undersized o-ring is a leak in which the drops break into a small stream. This type of leak is expected to result in less than 10 gallons of oil loss during the system's 6 hour mission time. The vendor recommended oil reserve level is approximately 124 gallons. The lube oil sump has a 155 gallon capacity and the remaining oil (approximately 145 gallons) is sufficient to support operability. As a result, the worst case leakage is not expected to affect operability of HPCI or result in system failure during the HPCI mission time. Operations verifies oil level weekly and prior to any planned run."

The licensee has notified the NRC Resident Inspector.

Notified R1DO (Gray).

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General Information or Other Event Number: 46420
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: OMAHA PUBLIC POWER DISTRICT
Region: 4
City: OMAHA State: NE
County:
License #: 01-39-04
Agreement: Y
Docket:
NRC Notified By: WAYNE GILSDORF
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/15/2010
Notification Time: 18:37 [ET]
Event Date: 11/15/2010
Event Time: 11:30 [CST]
Last Update Date: 11/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG PICK (R4DO)
PAUL MICHALAK (FSME)

Event Text

AGREEMENT STATE REPORT - FLY ASH DENSITY GAUGE SHUTTER FAILS OPEN

The following report was received via fax:

"The licensee uses fixed industrial gauges for measuring densities in fly ash hoppers at the Stations precipitator building. The industrial fixed gauges contain a Cesium 137 sealed source. The Cesium 137 sources were originally installed in April 1984 and at the time contained 50 milliCuries per source. The sources were manufactured and installed by Kay Ray, Inc. The gauge is Model No. 7080 and housing serial number 16785-G. The source capsule manufacturer was Amersham model no. CDC 800 and K-R ref. number serial number 15485 V. The Authorized User was performing the semi-annual 'Shutter Function Test' on Unit #3's precipitator sources. The 'external' source closure mechanism for the 3FA-1B & 2B hoppers did not operate as designed and the shutter did not close when the handle on the floor was operated. The external closure cable had detached from the shutter arms. In this condition, when the shutter closure mechanism was moved, the cable that operates the source shutter mechanism 20 feet above the floor did not move the shutter to the closed position. It should be noted that this cable is an older one which has been slated for replacement. This event happened at 11:30 am. The event was reported to the Lab Supervisor and the Radiation Safety Officer (RSO) at the Ft. Calhoun Power Station was notified. No personnel were exposed to radiation during this event."

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Power Reactor Event Number: 46421
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MICHAEL KOGELSCHATZ
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/16/2010
Notification Time: 05:48 [ET]
Event Date: 11/16/2010
Event Time: 00:01 [EST]
Last Update Date: 11/17/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
HAROLD GRAY (R1DO)

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

CONTROL ROOM ENVELOPE INOPERABLE DUE TO EXCESSIVE EMERGENCY CORE COOLING SYSTEM RELIEF VALVE LEAKAGE DURING ECCS PUMP SURVEILLANCE TESTING

"The Licensee identified that Emergency Core Cooling System (ECCS) leakage exceeded the allowable limit as described in the Updated Final Safety Analysis Report (UFSAR). This is being reported as an Unanalyzed Condition in accordance with 10CFR50.72(b)(3)(ii)(B) and 10CFR50.72(b)(3)(v) Control of Rad Release.

"The leakage from the Low Head Safety Injection discharge relief valve occurred during Low Head Safety Injection Pump surveillance testing. Efforts to resolve the lifting of the Low Head Safety Injection discharge relief valve are in progress.

"At 0001 [EST] on 11/16/10, Beaver Valley Power Station Unit 1 determined that leakage from the Low Head Safety Injection system in conjunction with a postulated Design Basis Accident (DBA) Loss Of Coolant Accident (LOCA) with transfer to Safety Injection Recirculation would result in dose exceeding the Dose Analysis for the Exclusion Area Boundary (EAB) and the Control Room. The projected dose would exceed the 10CFR50.67 EAB dose limit, and the 10CFR50 GDC 19 Control Room limit, assuming the leakage continued during the postulated DBA event.

"Beaver Valley Units 1 & 2 share a common Control Room Envelope, which has been declared inoperable as a result of this condition. Technical Specification Limiting Condition for Operation 3.7.10, Condition B, has been applied.

"The Senior NRC Resident has been informed of the condition [by the Licensee]."

Notified R1DO (Harold Gray).


* * * UPDATE FROM DAVID SHARBAUGH TO DONALD NORWOOD AT 1448 EST ON 11/17/2010 * * *

"Actions have been completed to prevent leakage from the degraded Low Head Safety Injection System relief valve at BVPS Unit 1. Following successful completion of the post-maintenance test, the BVPS Unit 1 Low Safety Injection System was declared operable and applicable Technical Specification Actions at both BVPS Units were exited at 1545 hours on 11/16/1010.

"The Senior NRC Resident Inspector has been notified."

Notified R1DO (Gray).

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Other Nuclear Material Event Number: 46425
Rep Org: ABERDEEN TEST CENTER
Licensee: U.S. ARMY
Region: 1
City: ABERDEEN PROVING GROUNDS State: MD
County:
License #: SUB-834
Agreement: Y
Docket:
NRC Notified By: JAMES DILLARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/17/2010
Notification Time: 10:10 [ET]
Event Date: 11/16/2010
Event Time: 11:00 [EST]
Last Update Date: 11/17/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(1) - UNPLANNED CONTAMINATION
Person (Organization):
HAROLD GRAY (R1DO)
MARK THAGGARD (FSME)
JAMNES CAMERON (R3DO)

Event Text

CONTAMINATION OUTSIDE BOUNDARY AREA DUE TO A PROJECTILE OFF FLIGHT PATH

The licensee was conducting live fire exercises at the Ford Farms section of the Aberdeen Test Center when a depleted uranium (DU) projectile went off its flight path and struck metal causing the projectile to shatter and become friable. Ford Farms is an indoor hard target facility that is targeted from weapons outside of the facility. The projectile shattered outside of Ford Farms thus the contamination is outside the facility.

Initial surveys indicate contamination levels as high as 400 cpm > background. The licensee has roped off the contaminated area and is sampling the air continuously while they formulate a cleanup plan. They estimate cleanup will take approximately two weeks with an additional week required for post-cleanup surveys.

The licensee has made notification to the USNRC Region I office.

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Power Reactor Event Number: 46426
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN WEISINGER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/17/2010
Notification Time: 18:26 [ET]
Event Date: 11/18/2010
Event Time: 03:00 [EST]
Last Update Date: 11/18/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (R1DO)

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

PLANNED TECHNICAL SUPPORT CENTER VENTILATION CORRECTIVE MAINTENANCE

"This ENS is being issued in advance of a planned activity.

"On November 18th 2010 at 0300, Limerick Generating Station [will apply] a clearance to perform corrective maintenance associated with MD-1 (Outside Air Damper). During the time that the block is applied, the TSC ventilation system will not be available to be restored in a time period required to staff and activate the TSC ERO [Emergency Response Organization].

"This work is expected to be complete on 11/18/10 at 1800. If an emergency is declared requiring TSC activation, the TSC will be staffed and activated using emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation becomes necessary the Station Emergency Director will relocate the TSC staff to an alternate TSC location in accordance with applicable site procedures.

"This notification is being made in accordance with 10CFR50.72(b)(3) due to the loss of an emergency response facility (ERF) because of unavailability of the emergency ventilation system.

"An update will be provided when the TSC ventilation has been restored to normal operation. The NRC resident has been notified."

* * * UPDATE FROM PAUL MARVEL TO DONG PARK AT 1729 EST ON 11/18/10 * * *

Planned work on the TSC ventilation system has been completed at 1700 on November 18, 2010. The TSC has been restored to normal status.

The licensee will notify the NRC Resident Inspector.

Notified R1DO (Gray).

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Power Reactor Event Number: 46428
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MARCIE BLOW
HQ OPS Officer: JOE O'HARA
Notification Date: 11/18/2010
Notification Time: 19:30 [ET]
Event Date: 11/18/2010
Event Time: 16:26 [CST]
Last Update Date: 11/18/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GREG PICK (R4DO)

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

POTENTIAL POST FIRE SAFE SHUTDOWN UNANALYZED CONDITION

"A Post Fire Safe Shutdown (PFSSD) circuit analysis identified that certain fuses installed within Train 'B' Exciter/Voltage Regulator cabinet NE106 are susceptible to failure in the event of postulated fire-induced hot shorts within the control room. Loss of power to this circuit will prevent operation of these functions. The emergency pre-positions and manual voltage adjustment circuits are not credited for PFSSD following a control room fire. However, field flashing is credited following a fire in the control room. Failure of field flashing after a postulated fire will prevent voltage generation on the 'B' diesel generator. This could result in the inability of the 'B' train EDG to supply its associated safety bus during the postulated fire.

"Compensatory measures are established for early detection and extinguishment of a fire associated with this circuit in the Control Room. Additional compensatory measures are being developed."

The licensee is not in any tech. spec LCO's as a result of this condition and has established fire watches as a compensatory measure.

The licensee notified the NRC Resident Inspector.

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