Event Notification Report for June 5, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/04/2012 - 06/05/2012

** EVENT NUMBERS **


47833 47963 47964 47965 47966 47990 47992

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Part 21 Event Number: 47833
Rep Org: MITSUBISHI HEAVY INDUSTRIES, LTD.
Licensee: MITSUBISHI HEAVY INDUSTRIES, LTD
Region: 1
City: ARLINGTON State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: EI KADOKAMI
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/13/2012
Notification Time: 15:58 [ET]
Event Date: 02/21/2012
Event Time: [EDT]
Last Update Date: 06/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
BLAKE WELLING (R1DO)
KATHLEEN O'DONOHUE (R2DO)
DAVID HILLS (R3DO)
VINCENT GADDY (R4DO)
PART 21 GROUP (EMAI)

Event Text

PART 21 INTERIM REPORT - STEAM GENERATOR TUBE WEAR

This interim Part 21 is in regard to San Onofre Nuclear Generating Station, Unit 2, Steam Generator replacement.

"During the first refueling outage following steam generator replacement, eddy current testing identified ten total tubes with depths of 90 to 28 percent of the tube wall thickness. Some of the affected tubes were located adjacent to retainer bars. The retainer bars are part of the floating anti-vibration bar (AVB) structure that stabilizes the u-bend region of the tubes.

"Other tubes in the two steam generators had detectable wear associated with support points elsewhere in the AVB structure. Each steam generator has 9727 tubes with an 8 percent (778 tubes) design margin for tube plugging.

"Discovery Date: February 13, 2012

"Evaluation completion schedule date: May 31, 2012"

"Those Mitsubishi Heavy Industries customers potentially affected by this issue have been notified and will receive a copy of this interim report."

Reference Document: UET-20120089
Interim Report No: U21-018-IR (0)

Notified R1DO (Joustra), R2DO (Nease), R3DO (Peterson), R4DO (O'Keefe), and Part 21 Group via email.

* * * UPDATE FROM MITSUBISHI HEAVY INDUSTRIES, LTD VIA FAX ON 6/4/12 AT 1145 EDT * * *

The vendor changed the number of tubes identified with wear depths of 90 to 28 percent from ten tubes to six tubes and only some of the tubes were adjacent to retainer bars.

Notified R1DO (Cahill), R2DO (Vias), R3DO (Passehl), R4DO (Gepford) and Part 21 Groups via email.

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Agreement State Event Number: 47963
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: UNKNOWN
Region: 4
City: OKLAHOMA CITY State: OK
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/25/2012
Notification Time: 11:32 [ET]
Event Date: 05/25/2012
Event Time: [CDT]
Last Update Date: 05/25/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EMAIL ()

Event Text

AGREEMENT STATE REPORT - URANIUM SOURCE FOUND AT METAL CHECK RECYCLING FACILITY

"On May 22, 2012 we [Oklahoma Department of Environmental Quality (OKDEQ)] were contacted by the Director of Radiology at INTEGRIS Southwest Medical Center in Oklahoma City. The Director informed us that an individual had presented at their Emergency Room complaining that he had been exposed to radiation at the Metal Check, Inc. scrap metal yard located at 5700 South High Avenue, Oklahoma City, OK. According to [the Director], the individual was a heavy equipment mechanic who had been sent to Metal Check to repair a piece of their equipment. While working there he was told by some of the Metal Check employees not to enter a certain part of the facility because it contained radioactive pipe. The mechanic immediately left Metal Check and went to the Medical Center."

"That afternoon [an inspector with OKDEQ] went to Metal Check and spoke with the owner and the manager. They agreed to allow [the inspector] to survey the pipe in question and showed [the inspector] the area where it was stored and where the mechanic was working. It appeared to [the inspector] that the pipe was located approximately 40 feet from where the equipment was being repaired, making it impossible for the mechanic to receive any significant dose from this material. [The manager] showed [the inspector] a small bin approximately six feet long by four feet high by four feet deep filled with miscellaneous pieces of scrap metal. The top of the bin was surveyed with a Ludlum Model 19 microR meter (S/N 70537, cal. Aug. 18, 2011) which produced a reading of approximately 1100 microR/hr. This was very high for NORM [naturally occurring radioactive material] pipe and [the inspector] also noted that the radiation level was not uniform along the length of the bin, having a definite spike approximately two feet from the left end. This led [the inspector] to conclude that there was a localized source somewhere in the bin at that point. [The inspector] then contacted [his supervisor] and related what [he] had found at the facility. [The inspector] suggested returning the next day with an additional person and additional instruments, and attempting to locate the postulated radiation source.

"The following morning [the inspector and an associate] returned to Metal Check and began to unload the bin. Almost immediately [they] found what appeared to be a badly corroded metal bucket which had been crushed around an object inside it. A survey of the object with the same Model 19 used the previous day produced a reading of 2.2 mR/hr on contact with the bucket. A Thermo Fisher Interceptor portable gamma spec was used to collect a gamma spectrum from the object, which the instrument identified as shielded Uranium. A second spectrum was collected through a hole in the bucket surrounding the object; this was identified as natural Uranium. A portion of the object was wiped through a hole in the bucket; analysis of the wipe by the DEQ Environmental Lab confirmed the presence of U-235 and U-238, and their daughters. The object was roughly disk-shaped, approximately 12 inches in diameter and one inch thick. One side had a second, smaller disk, approximately 10 inches in diameter, centered on the larger and approximately 2 inches thick. No markings or labels were visible. [The inspectors] estimate the weight of the object at approximately 40 lbs. Three pieces of NORM pipe were also found with high radiation levels (1 mR/hr). All four objects were removed from the bin which was then surveyed again, producing readings of approximately 300 to 400 microR/hr. Rachel Browder and Michelle Hammond of the NRC were informed of the situation later that day by phone. The uranium object was placed in a locked room at the Metal Check facility pending further guidance from NRC."

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Agreement State Event Number: 47964
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: ALCOA
Region: 1
City: ALCOA CENTER State: PA
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/25/2012
Notification Time: 13:29 [ET]
Event Date: 05/18/2012
Event Time: [EDT]
Last Update Date: 05/25/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1DO)
FSME VIA EMAIL ()

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

Event Text

AGREEMENT STATE REPORT - MISSING TRITIUM EXIT SIGNS

The following information was obtained from the Commonwealth of Pennsylvania via fax:

"Alcoa was doing some renovations and had a previous inventory of nine (9) general license [GL] tritium exit signs. During the renovation it was discovered that only seven (7) were accounted for.

"Details of the two missing exit signs: Evenlite, Inc. Model #201, serial numbers 1388F and 389F, each containing 10.5 Ci of tritium.

"CAUSE OF THE EVENT: Though these GL tritium exit signs comply with NRC regulations for labeling to alert the user that they contain radioactive material, the size of the label is woefully inadequate to prevent unintentional loss of the GL device. This event is another example.

"ACTIONS: No reactive inspection is planned at this time. It is expected these two tritium exit signs have or will end up in an unlicensed Commonwealth of Pennsylvania landfill."

PA Report ID No.: PA120015

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

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

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Agreement State Event Number: 47965
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: CANONSBURG HOSPITAL
Region: 1
City: CANONSBURG State: PA
County:
License #: PA-0393
Agreement: Y
Docket:
NRC Notified By: JOE MELNIC
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/25/2012
Notification Time: 14:19 [ET]
Event Date: 01/20/2012
Event Time: [EDT]
Last Update Date: 05/25/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1DO)
FSME VIA EMAIL ()

Event Text

AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING IODINE-125 PROSTATE SEEDS

The following information was obtained from the Commonwealth of Pennsylvania via fax:

"A patient was undergoing treatment with I-125 prostate seeds on January 20, 2012. The patient was prescribed to receive 110 Gy for a determined prostate volume of 21.08 cc. On March 16, 2012 the patient had a follow up CT scan where the prostate volume was determined to be 47 cc and the D90 to the prostate to be 75 Gy. The oncologist questioned the results and ordered an additional CT scan. On May 16, 2012, a second CT scan was performed to confirm the first CT scan. On May 21, 2012, the radiology oncologist calculated the prostate volume to be 33.59 cc and confirmed the D90 to be 75 Gy. The radiation oncologist has no explanation for the edema.

"Cause of the Event: Implant performed using ultrasound, post implant verification via CT.

"Actions: There will be a reactive inspection [by the Commonwealth of Pennsylvania]. The radiation oncologist ordered external beam radiation therapy and feels that the total dose is sufficient. Additional follow up with the patient will occur."

PA Report ID No.: PA120018

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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Agreement State Event Number: 47966
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: BASF CORPORATION
Region: 4
City: GEISMAR State: LA
County:
License #: LA-2304-L01
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/25/2012
Notification Time: 16:33 [ET]
Event Date: 04/26/2012
Event Time: [CDT]
Last Update Date: 05/25/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME VIA EMAIL ()

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

Event Text

AGREEMENT STATE REPORT - LEVEL/DENSITY GAUGE SHUTTER MALFUNCTION

The following information was obtained from the State of Louisiana via fax:

"On April 26, 2012, the Louisiana Department of Environmental Quality (LDEQ) received notification that a shutter malfunctioned on an Ohmart Corporation Level/Density gauge at BASF Corporation. BASF Corporation has a RAM License LA-2304-L01 and Agency Interest Number 2049. The gauge was a Model SH-F1, containing a Cs-137 sealed source, serial number 6274GK with 50 mCi of activity. Ohmart sent out a field engineer to repair the following devices: 1) Ohmart Model SH-F1 level/density gauge, serial number 67471 to replace shutter and rotor; 2) Ohmart Model SH-F1 level/density gauge, serial number 6292GK to lubricate and restore proper shutter function; 3) Ohmart Model SH-F1 level/density gauge, serial number 6247GK, source holder remains stuck in the open position and the gauge is scheduled to be replaced and disposed of at a licensed facility. This incident is reference by LDEQ T139229."

LA Report ID No.: LA120001

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

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Part 21 Event Number: 47990
Rep Org: MITSUBISHI HEAVY INDUSTRIES, LTD.
Licensee: MITSUBISHI HEAVY INDUSTRIES, LTD.
Region: 1
City: ARLINGTON State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MIKE SCHULTZ
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/19/2012
Notification Time: 12:33 [ET]
Event Date: 02/13/2012
Event Time: [EDT]
Last Update Date: 06/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
STEVEN VIAS (R2DO)
DAVE PASSEHL (R3DO)
HEATHER GEPFORD (R4DO)
PART 21 GRP (EMAIL) ()

Event Text

PART 21 - STEAM GENERATOR TUBE WEAR ADJACENT TO RETAINER BARS

The following information was obtained from Mitsubishi Heavy Industries, LTD on April 19, 2012 was inadvertently added to Event Notification #47833 as an update to that event. The vendor's intent was to issue two interim reports; one for San Onofre Nuclear Generating Station (SONGS) Unit 2 and one for SONGS Unit 3. The information was obtained via fax:

"On January 31, 2012, San Onofre Unit 3 shut down due to indications of a steam generator tube leak. Steam generator tube inspections confirmed one small leak on one tube in one of the two steam generators. Continuing inspections of 100% of the steam generator tubes in both Unit 3 steam generators discovered unexpected wear, including tube to tube as well as tube to tube support structural wear. Inspection, testing, and analysis of SG tube integrity in both Unit 3 SGs is ongoing. In-situ pressure testing identified eight Unit 3 SG tubes that did not meet the target performance criteria in Technical Specification for tube integrity. One of the failed tubes was the leaking tube that required the Unit 3 shutdown.

"Discovery date: February 21, 2012

"Evaluation completion schedule date: August 31, 2012"

Interim Report: U21-019-IR
Reference Document: UET-20120105

Original notifications (per EN# 47833) were made to R1DO (Joustra), R2DO (Nease), R3DO (Peterson), R4DO (O'Keefe), and Part 21 Group via email.

Notified R1DO (Cahill), R2DO (Vias), R3DO (Passehl), R4DO (Gepford) and Part 21 Groups via email.

* * * UPDATE FROM MITSUBISHI HEAVY INDUSTRIES, LTD VIA FAX ON 6/4/12 AT 1145 EDT * * *

The vendor reported that eight Unit 3 SG tubes did not meet the target performance criteria in Technical Specifications for tube integrity.

Notified R1DO (Cahill), R2DO (Vias), R3DO (Passehl), R4DO (Gepford) and Part 21 Groups via email.

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Power Reactor Event Number: 47992
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: JOHN FICKLE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/04/2012
Notification Time: 21:59 [ET]
Event Date: 06/04/2012
Event Time: 15:14 [CDT]
Last Update Date: 06/04/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
HEATHER GEPFORD (R4DO)

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

REACTOR COOLANT SYSTEM IN A DEGRADED CONDITION DUE TO AN INSTRUMENT RACK SEISMIC DESIGN ISSUE

"During a review of plant installed instrumentation racks inside containment, two instrument racks were identified that were over the analyzed weight for the seismic analysis. The instruments on these racks are used for reactor coolant pressure transmitters that are part of the Reactor Coolant System (RCS) pressure boundary, as they are connected via instrument lines to the RCS with no remote closure capabilities. A failure of these racks during a seismic event due to the excessive weight could result in an unisolable leak from the RCS within containment based on engineering judgment. This results in the RCS principal safety boundary being in a degraded nonconforming condition as the Updated Safety Analysis Report (USAR) specified Class 1 requirement is not being met for the current seismic design. Further engineering analysis is in progress to address the weight issue for these racks and mounting requirements. The plant is shutdown and in Mode 5 with the reactor vessel head removed, so RCS is not intact and not required to be for current plant conditions. This report is being made in accordance with 10CFR72(b)(3)(ii)(A) for a degraded condition."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 25, 2021