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Event Notification Report for July 15, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/14/2011 - 07/15/2011

** EVENT NUMBERS **


46996 47038 47048 47050 47051 47052

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Fuel Cycle Facility Event Number: 46996
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: R. J. COOK
HQ OPS Officer: PETE SNYDER
Notification Date: 06/28/2011
Notification Time: 23:10 [ET]
Event Date: 06/28/2011
Event Time: 00:05 [CDT]
Last Update Date: 07/14/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
MARK FRANKE (R2DO)
ROBERT JOHNSON (NMSS)

Event Text

FAILURE OF #2 FIRE WATER PUMP TO REALIGN

"At 0005 CDT, on 06-28-2011, the Plant Shift Superintendent was notified that the C-631 High Pressure Fire Water (HPFW) pumps #2 and #3 automatically started in response to low HPFW header pressure created by a line leak and rendered inoperable. Following isolation of the water leak the #2 and #3 pumps were shut down and were being configured for automatic start. The RCW operator observed the 'Auto Start' Indicator for the #2 pump was not illuminated. The pump was declared inoperable and power was removed from the #2 pump for troubleshooting and repair by electrical maintenance (EM). When power was removed from the pump the HPFWS could not perform its intended safety function of providing 4875 gpm. Two HPFW system pumps are required to be operable according to TSR LCO 2.4.4.8. EM reset a disconnect interlock switch which reenergized the 'Auto Start' controls and the pump was declared operable and returned to service.

"This event is reportable under 10 CFR 76.120(c)(2) as an event in which equipment required by the TSR is disabled or fails to function as
designed.

"The NRC Senior Resident Inspector has been notified of this event."

* * * UPDATE FROM KEVIN BEASLEY TO PETE SNYDER AT 1613 EDT 6/29/11 * * *

"Due to the uncertain nature of the leak on the 16 inch underground High Pressure Fire Water (HPFW) distribution main, it is not known at this time if the two operable HPFW pumps would have been able to satisfy the maximum sprinkler system demand of 4875 gpm. Upon completion of excavating the area of the leak, Engineering will evaluate the failure mode to determine if system requirements were maintained."

The licensee notified the NRC Resident Inspector.

Notified R2DO (M. Franke) and NMSS (R. Johnson).

* * * RETRACTION FROM CALVIN PITTMAN TO KARL DIEDERICH AT 1423 EDT 07/14/11 * * *

"Upon further evaluation it was determined that the (High Pressure Fire Water System) HPFWS was capable of fulfilling its intended safety function at all times during the incident. The safety function of the High Pressure Fire Water System established in SAR 3.15.7.2 is to provide sufficient fire suppression capability for the cascade process buildings to minimize the likelihood of a large fire. Fire scenarios were evaluated to establish the system design basis. A lube oil spill fire on the operating floor resulted in the highest sprinkler flow rate demand of 3200 gpm. A 500 gpm hose stream demand is added to the sprinkler system flow rate to obtain a maximum fire water flow rate of 3700 gpm for the evaluation basis fire event. As stated in the TSR 2.4.4.8 Basis Statement, the requirements for HPFWS operability established in TSR 2.4.4.8 are conservative with respect to the system evaluation presented in SAR 3.15.7.2. TSR SR 2.4.4.8-4 requires an annual flow rate verification of each HPFW pump. The most recent flow rate tests performed in Nov. 2010 demonstrate the capacity of each pump exceeds the evaluation basis flow demands. During the short time where only HPFW pump #3 was operable, this pump could have supplied more than the 3700 gpm required to satisfy the evaluation basis flow demand. The HPFWS remained capable of fulfilling its intended safety function.

"In addition, when HPFW pumps #2 and #3 were running in response to the leak on the underground distribution system, system pressure was approximately 134 psig. Using the pump curves established by the annual TSR surveillance test discussed above, this equates to a flow rate of approximately 5900 gpm. Any sprinkler system activation on the HPFWS would drop the system pressure to around 125 psig, slightly lowering the flow rate through the leak. During the time frame the leak was active, the HPFWS remained capable of fulfilling its intended safety function. The combined pump capacity of pumps #2 and #3 (10,600 gpm) demonstrated by the annual surveillance test exceeds the combined demand from the leak (5900 gpm) and the evaluation basis flow requirements (3700 gpm). Therefore, the HPFWS remained operable throughout the incident of the
underground piping leak and the following time period of only one pump operable. Thus, reporting per 10 CRF 76.120 was not required and the subject notification can be retracted."

The NRC Senior Resident Inspector has been notified of this retraction by the licensee.

Notified R2DO (Freeman) and NMSS (Rahimi).

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Agreement State Event Number: 47038
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: BRIGHAM AND WOMEN'S HOSPITAL
Region: 1
City: BOSTON State: MA
County:
License #: 44-0004
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: VINCE KLCO
Notification Date: 07/08/2011
Notification Time: 15:45 [ET]
Event Date: 05/01/2011
Event Time: [EDT]
Last Update Date: 07/08/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DANIEL HOLODY (R1DO)
RICHARD TURTIL (FSME)

Event Text

AGREEMENT STATE REPORT- UNDEREXPOSURE

The following information was received from the Commonwealth by facsimile:

"The RSO reported that a patient was 60% underexposed by an Ir-192 remote after-loader. The prescribed dose is not known. The error occurred because the physicist did not calculate the effect of the tube used to deliver the after-loader source. The target organ was the skin."

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: 47048
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: ED CARRERAS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/14/2011
Notification Time: 16:19 [ET]
Event Date: 07/14/2011
Event Time: 13:19 [EDT]
Last Update Date: 07/14/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES DWYER (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

OFFSITE NOTIFICATION DUE TO INADVERTANT SIREN ACTUATION

"At about 1319 on July 14, 2011, Dauphin County 911 (Pennsylvania) was advised by a local resident that siren number 121 sounded for 3 minutes. Dauphin County (Pennsylvania) contacted the TMI main control room to inform Exelon of an inadvertent siren actuation at about 1350 on July 14, 2011.

"Pennsylvania Emergency Management Agency (PEMA) later notified (about 1430 on July 14, 2011) the TMI main control room of the same issue.

"This notification is being made in accordance with 10CFR50.72(b)(2)(xi) because offsite agencies were notified regarding the inadvertent actuation of part of the public notification system.

"Siren Maintenance was notified and is troubleshooting the issue."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47050
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: MARK MCGHEE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/14/2011
Notification Time: 20:09 [ET]
Event Date: 07/14/2011
Event Time: 14:11 [MST]
Last Update Date: 07/14/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CHUCK CAIN (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
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

NEWS RELEASE REGARDING ARREST OF ILLEGAL IMMIGRANT WORKING AT PALO VERDE

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.

"This event is being reported as a newsworthy concern to the public under 10 CFR 50.72(b)(2)(xi).

"Palo Verde Nuclear Generating Station (PVNGS) was notified that the Maricopa County Sheriff's Office (MCSO) issued a news release at 1411 on July 14, 2011, regarding entrance to the PVNGS site property by an individual who MCSO alleged to be an undocumented immigrant.

"The individual had entered Palo Verde's Security Owner Controlled Area on July 13, 2011, but was not granted access to the site's Protected Areas surrounding the three units and Independent Spent Fuel Storage Installation. PVNGS Security contacted MCSO to validate the identification card furnished by the individual at the Security Owner Controlled Area. MCSO determined the identification card to be suspicious, responded to the site, detained the individual, and transported him off-site for questioning.

"The station notified NRC Resident Inspectors and Region IV staff of the condition on July 13, 2011.

"Arizona Public Service is planning to issue a news release and is responding to media inquiries regarding the matter."

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Power Reactor Event Number: 47051
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: DAVE SPARGO
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/14/2011
Notification Time: 20:24 [ET]
Event Date: 07/14/2011
Event Time: 19:13 [CDT]
Last Update Date: 07/14/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
CHUCK CAIN (R4DO)
ELMO COLLINS (RA)
ERIC LEEDS (NRR)
SCOTT MORRIS (IRD)
DENNIS ALLSTON (ILTA)
LINDA HOWELL (R4)
DAVE HILL (DHS)
DWIGHT FULLER (FEMA)

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

UNUSUAL EVENT DECLARED DUE TO SUSPECTED INTRODUCTION OF CONTRABAND INTO THE PROTECTED AREA

The licensee declared an Unusual Event due to indications that potentially dangerous contraband had been introduced into the protected area. After further investigation, the licensee determined that the indication of contraband was due to incorrect interpretation of screening equipment imaging. The licensee exited its Unusual Event declaration at 1942 CDT. The licensee continues to investigate the circumstances leading to this event declaration.

The licensee notified State and local authorities and will notify the NRC Resident Inspector

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Power Reactor Event Number: 47052
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KARL HANTHO
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/14/2011
Notification Time: 21:50 [ET]
Event Date: 07/14/2011
Event Time: 20:53 [EDT]
Last Update Date: 07/15/2011
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JAMES DWYER (R1DO)
DAVE LEW (DRA)
BRUCE BOGER (NRR)
SCOTT MORRIS (IRD)
DAVE HILL (DHS)
DWIGHT FULLER (FEMA)

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

UNUSUAL EVENT DECLARED BASED ON REACTOR COOLANT LEAK GREATER THAN 10 GPM

"At 2053 on July 14, 2011 Salem unit 2 declared an Unusual Event due to reactor coolant system leakage greater than 10 gallons per minute. While performing a monthly Emergency Core Cooling System vent of the high head safety injection piping a motor operated valve was opened and a leak developed on the high head piping greater than 10 gallons per minute. The leak rate was approximately 11-15 gallon per minute. The leak was terminated when the motor operated valve was closed. The time of the leak was about 6 minutes."

At this time the leak is believed to be from a crack on the Boron Injection Tank (BIT) relief valve line which is connected to the high head piping. A total of approximately 90 gallon of reactor coolant leaked into the BIT room. The licensee has declared the high head safety injection inoperable and is proceeding to shutdown under Tech Spec 3.0.3.

The license has notified appropriate State and local authorities. The licensee will notify the NRC Resident Inspector.

* * * UPDATE FROM KARL HANPHO TO VINCE KLCO ON 7/15/11 AT 0025 EDT* * *

"Salem Unit 2 declared an Unusual Event due to Reactor Coolant System (RCS) leakage being greater than 10 gpm and pressurizer level decreasing. Leakage was estimated to be approximately 15 gpm. The leakage was determined to be from a weld on the high head charging injection relief valve connection. This leaking weld impacts both trains of high head charging/safety injection. Both trains of high head charging/safety injection were declared inoperable at 2038 [EDT] on July 14, 2011, entering TS 3.0.3. Salem Unit 2 began the Technical Specification shutdown in accordance with TS 3.0.3 at 2136 [EDT]. The technical specification shutdown is being reported in accordance with 10CFR50.72(b)(2)(i) and RAL 11.1.1.a.

"In addition since the leakage from the weld on the high head charging/safety injection piping exceeded the analyzed limit for ESF leakage outside containment, this event is also being reported in accordance with 10CFR50.72(b)(3)(v) and RAL 11.2.2.b as a condition that prevents the ability to mitigate the consequences of an accident.

"Salem unit 2 is currently at 27% and reducing power."

The licensee notified the states of New Jersey and Delaware, Lower Alloways Township and the NRC Resident Inspector.

Notified the R1DO (Dwyer), NRR-EO (Giiter) and IRD (Morris).

* * * UPDATE FROM KARL HANPHO TO CHARLES TEAL ON 7/15/11 AT 0345 EDT* * *

Salem Unit 2 has exited the Unusual Event as of 0339 EDT. The criteria for exit was the leakage rate was below the 10 gpm rate. The plant is in Mode 3 and is preparing to cooldown.

The licensee will notify the NRC Resident Inspector.

Notified the R1DO (Dwyer), NRR EO (Giitter), IRD (Morris), DHS(Hill), and FEMA (Blankenship).

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Thursday, March 29, 2012