United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2010 > November 16

Event Notification Report for November 16, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/15/2010 - 11/16/2010

** EVENT NUMBERS **


46261 46318 46408 46411 46412 46419 46421 46424

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46261
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/20/2010
Notification Time: 17:26 [ET]
Event Date: 09/16/2010
Event Time: 13:43 [CDT]
Last Update Date: 11/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)

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

UNANALYZED CONDITION - DEGRADED FIRE BARRIER IDENTIFIED

"This is a late eight hour report submitted under 10CFR50.72(b)(3)(ii), 'Degraded or Unanalyzed Condition.'

"During walk downs for the Fire Penetration Seal Project on September 16, 2010 at 1343 [hrs. CDT], a degraded fire barrier was identified in the wall between the Unit 1 and Unit 2 sides of the Electrical Piping Area. The wall is listed as an Appendix R wall between Fire Area (FA) 29 and FA 30. The wall separates safety related redundant cables.

"There is an approximately one inch gap filled with loose fitting foam from the top of the wall to the concrete ceiling above it. In one place the foam has a gap approximately one inch wide. This has been identified as a missing fire barrier such that the required degree of separation for redundant safe shutdown trains is lacking.

"A fire watch was established as a compensatory measure on 9/16/10. The discovery of this non-compliance is being reported as an unanalyzed condition as defined by 10 CFR 50.72(b)(3)(ii)(B).

"The licensee has notified the NRC Resident Inspector of this event."

The fire watch remains in place.

* * * RETRACTION ON 11/15/2010 AT 1328 EST FROM STEPHEN SEILHYMER TO MARK ABRAMOVITZ * * *

"An eight hour report per 10 CFR 50.72(b)(3)(ii)(B) was conservatively reported on September 20, 2010 for a degraded fire barrier between Fire Area (FA) 29 and FA 30. Subsequent engineering analysis determined that the degraded fire barrier maintained the required degree of separation for redundant safe shutdown trains and plant safety was not significantly degraded. The 10 CFR 50.72(b)(3)(ii)(B) report is retracted.

"The NRC Resident [Inspector] has been informed."

Notified the R3DO (Cameron).

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46318
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: JOE O'HARA
Notification Date: 10/07/2010
Notification Time: 21:06 [ET]
Event Date: 10/07/2010
Event Time: 13:52 [CDT]
Last Update Date: 11/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DAVE PASSEHL (R3DO)

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 98 Power Operation 98 Power Operation

Event Text

DEGRADED FIRE BARRIER

"During a walkdown for the Fire Penetration Seal Project a degraded fire barrier was identified in the wall between the Unit 1 and Unit 2 Normal 480V Switchgear Rooms. The wall is listed as an Appendix R wall between Fire Area (FA) 37 and FA 38. The wall separates redundant safe shutdown cables.

"There is a 2 inch gap where the top of the wall meets the ceiling. The gap is filled with combustible foam - some loose and some stationary. This has been identified as a missing fire barrier such that the required degree of separation for redundant safe shutdown trains is lacking.

"A fire watch has been established as a compensatory measure and will remain in place until the fire barrier is repaired.

"The discovery of this non-compliance is being reported as an unanalyzed condition as defined by 10CFR50.72(b)(3)(ii)(B).

"The licensee has notified the NRC Resident Inspector of this event."

* * * RETRACTION ON 11/15/2010 AT 1328 EST FROM STEPHEN SEILHYMER TO MARK ABRAMOVITZ * * *

"An eight hour report per 10 CFR 50.72(b)(3)(ii)(B) was conservatively reported on October 7, 2010 for a degraded fire barrier between Fire Area (FA) 37 and FA 38. Subsequent engineering analysis determined that the degraded fire barrier maintained the required degree of separation for redundant safe shutdown trains and plant safety was not significantly degraded. The 10 CFR 50.72(b)(3)(ii)(B) report is retracted.

"The NRC Resident [Inspector] has been informed."

Notified the R3DO (Cameron).

To top of page
General Information or Other Event Number: 46408
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: QSA GLOBAL, INC.
Region: 1
City: BURLINGTON State: MA
County:
License #: 12-8361
Agreement: Y
Docket:
NRC Notified By: SALISU DAKUBU
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/09/2010
Notification Time: 15:42 [ET]
Event Date: 11/08/2010
Event Time: [EST]
Last Update Date: 11/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RONALD BELLAMY (R1DO)
GLENDA VILLAMAR (FSME)
LAURA PEARSON (ILTA)

This material event contains a "Category 2" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - RADIOACTIVE MATERIAL SHIPMENT FAILS TO ARRIVE

"A shipment containing 88.7 Ci Ir-192 that was scheduled to be delivered on 11/8/2010 did not arrive as scheduled. A trace was requested today. Details are as follows:

"On Friday 11/5/10, QSA Global, Inc (MA License 12-8361) shipped a CPIR100 to Kakivik Asset Management (NRC 50-27667-01) to be delivered C/O Northern Air Cargo in Anchorage, AK. It was shipped [by the carrier] P1 (Priority overnight) along with a small non-radioactive piece that contained a leak test kit. Both pieces were scheduled to be delivered to Northern Air Cargo on Monday 11/8/10. The leak test delivered without issue. However, the radioactive piece is still showing as arrived at [the carrier's] location in Newark, NJ.

"Today, Tuesday, 11/9/10, [the carrier] was contacted to put a trace on the radioactive material. They believe that the address label must have somehow come off the package. QSA provided a complete physical description of the IR100 overpack."

Source serial # - 66641B
Source Activity - 88.7 Ci / 3281.9 GBq
Surface reading - 18.0 mr/hr
Transport Index - 0.4

* * * UPDATE FROM JOSH DAEHLER TO DONG PARK AT 1025 EST ON 11/10/10 * * *

The following information was received via email:

"QSA has been notified by the carrier this morning that the package referenced [above] was located overnight and has been forwarded to its destination on a new tracking [number]."

Notified R1DO (Bellamy), FSME (Burgess), and ILTAB (Pearson).

THIS MATERIAL EVENT CONTAINS A "CATEGORY 2" LEVEL OF RADIOACTIVE MATERIAL

Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

To top of page
General Information or Other Event Number: 46411
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: MISSISSIPPI STATE UNIVERSITY
Region: 4
City:  State: MS
County:
License #: MS-EBL-02
Agreement: Y
Docket:
NRC Notified By: JAYSON MOAK
HQ OPS Officer: JOE O'HARA
Notification Date: 11/10/2010
Notification Time: 15:31 [ET]
Event Date: 10/15/2010
Event Time: [CST]
Last Update Date: 11/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RONALD BELLAMY (R1DO)
MICHELE BURGESS (FSME)
VINCENT GADDY (R4DO)

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

Event Text

AGREEMENT STATE REPORT - MISSING VARIAN GAS CHROMATOGRAPH CONTAINING TWO 15 MILLICURIE NICKEL - 63 SOURCES

"The licensee's RSO notified Department of Radiological Health (DRH) about their missing Varian electron capture detectors on 10/15/10, while conducting their six (6) month sealed source inventory and leak tests. The licensee's Receiving and Property Control Office picked the Varian gas chromatograph, Serial No. 10734, up for disposal from one of the licensee's labs and boxed it for shipment to Creative Recycling Systems, Inc., in Palmetto, Georgia. Creative Recycling Systems received the licensee's recycle trailer on 10/12/10. On 10/15/10, the licensee's property control office contacted Creative Recycling Systems, Inc., and requested notification if the detectors were ever found."

Creative Recycling Systems did not find the Varian electron capture detector containing two Ni-63 sources, serial numbers A2115 and T585, and it is assumed that it has been lost at the recycle facility. The licensee did survey a similar Varian device and found that survey readings were very close to background.

MS Incident #: MS-10006.

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

To top of page
General Information or Other Event Number: 46412
Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: MAYO CLINIC
Region: 3
City: ROCHESTER State: MN
County:
License #: 1047-206-55
Agreement: Y
Docket:
NRC Notified By: SHERRIE FLAHERTY
HQ OPS Officer: JOE O'HARA
Notification Date: 11/10/2010
Notification Time: 18:02 [ET]
Event Date: 11/10/2010
Event Time: 11:00 [CST]
Last Update Date: 11/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ANN MARIE STONE (R3DO)
PAUL MICHALAK (FSME)

Event Text

AGREEMENT STATE REPORT - UNDERDOSAGE TO INTENDED TREATMENT AREA

The following was received via e-mail:

"At approximately 11:00 am on November 10, 2010, the Minnesota Department of Health was notified of a medical event that occurred at Mayo Clinic. Mayo Clinic reports during a biliary LDR treatment using Iridium-192, the catheter and guide wire moved and the radioactive sources moved out of position approximately 7 cm distal to the treatment location (still in the bile duct). The oncologist noticed the guide wire had moved at approximately 10:30 am on November 10, 2010, at that point the RSO was notified. It was determined that the intended treatment site received only 1.24 Gy of the intended dose of 20.0 Gy, making this a reportable event.

"MDH will continue to investigate and will do an on-site visit during the week of November 15. More information to follow."


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.

To top of page
Power Reactor Event Number: 46419
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MIKE HOUGH
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/15/2010
Notification Time: 07:06 [ET]
Event Date: 11/15/2010
Event Time: 06:03 [EST]
Last Update Date: 11/15/2010
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):
ALAN BLAMEY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 M/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO LOSS OF A CIRCULATING WATER PUMP WITH ANOTHER PUMP OUT OF SERVICE FOR MAINTENANCE

"On 11/15/10 at 0603 [hrs. EST], the Unit 3 reactor was manually tripped after receiving a report that there was an overheating packing gland on the 3A2 Circulating Water Pump. The 3A1 Circulating Water Pump was already tagged out for maintenance. This required Unit 3 to be tripped due to only two Circulating Water Pumps in operation. The Unit 3 reactor was stabilized in Mode 3. Auxiliary Feedwater automatically actuated. A train of normal feedwater remains available to feed Steam Generators.

"During the Unit 3 reactor trip, the 3B Steam Dump to Atmosphere failed to close on operator demand per procedure. It was locally isolated with a manual isolation valve stopping the cooldown. The RCS was stabilized at 487.56?F and was borated as required by procedure. All boration systems operated as designed. The RCS returned to normal operating temperature and pressure."

During the trip, all rods inserted into the core. Other than the steam dump to atmosphere valve lifting, no other relief valves lifted. There is no known primary to secondary leakage. The electrical grid is normal and the plant is in a normal shutdown electrical line-up. Decay heat is being removed via the 3A and 3C steam dumps to atmosphere since the Main Steam Isolation Valves were closed. The plant is heating up to normal operating temperature at which time auxiliary feedwater will be secured.

The licensee has notified the NRC Resident Inspector.

To top of page
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).

To top of page
Power Reactor Event Number: 46424
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHNNIE EDWARDS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/16/2010
Notification Time: 23:43 [ET]
Event Date: 11/16/2010
Event Time: 22:10 [EST]
Last Update Date: 11/16/2010
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):
DEBORAH SEYMOUR (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 26 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP BASED ON DECREASING STEAM GENERATOR LEVEL

"At 2210 EST on 11/16/2010, the Unit 1 reactor was manually tripped based on decreasing S/G level in Loop 4. Prior to the reactor trip power was at 26% and ascending following completion of a scheduled refueling outage. Moisture Separator Reheater 1C1 safety valve lifted and would not reseat. Turbine was tripped at 2206 EST to isolate steam leak. Following the Turbine trip, automatic S/G level control did not maintain S/G level. Manual control was taken however, S/G level could not be recovered. A manual reactor trip was initiated due to low narrow range S/G level. All other plant systems responded as expected."

All rods fully inserted into the core during the trip. The reactor is at normal operating pressure and temperature and operators are removing decay heat via the steam dumps to condenser. As expected, the auxiliary feedwater system actuated during the transient. The grid is stable and the plant is in its normal shutdown electrical lineup. There is no known primary-to-secondary leakage. Plant response to the trip was considered normal and uncomplicated. Unit 2 was not affected by this event.

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Tuesday, August 11, 2015
Tuesday, August 11, 2015