| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/05/2014 - 09/08/2014 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 49904 | Rep Org: VALCOR ENGINEERING CORPORATION
Licensee: VALCOR ENGINEERING CORPORATION
Region: 1
City: SPRINGFIELD State: NJ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JIMMY SHIEH
HQ OPS Officer: CHARLES TEAL | Notification Date: 03/12/2014
Notification Time: 18:24 [ET]
Event Date: 01/11/2014
Event Time: [EDT]
Last Update Date: 09/05/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
PART 21 GROUP (EMAI)
| Event Text PART 21 - AP-1000 SOLENOID OPERATED VALVES LEAKAGE
The following was excerpted from a fax received from Valcor Engineering Corporation:
"Background:
"Valcor was chosen by WEC [Westinghouse Electric Corporation] as a supplier to the AP-1000 for the ASME Section Ill Class 1, 2 and 3 Solenoid Operated Valves. As part of the specification requirements Valcor is required to perform qualification testing in accordance with the requirements of IEEE-323-1974, IEEE-344-1987 and IEEE-382-1996.
"Discovery:
"On Saturday January 11th, 2014, Valcor's lab technician discovered that the hard faced seat of an AP-1000 Solenoid Operated qualification valve had a crack through the thickness of the valve seat to the outlet port that caused the valve to leak in the closed position beyond its Technical Specification requirement (WEC Specification APP-PV13-ZOD-101). The subject valve had undergone heat rise testing to determine actuator temperatures during its specified design basis conditions. As part of the qualification process (IEEE-323) and in accordance with the test procedure the subject valve is given a factory acceptance test (FAT) at each stage of the qualification program.
"The valve design is unique to the model (V526-5631-36/40) in that the dimensional constrain resulted in a web thickness of the hard faced seat that is thinner than our standard historical valve designs. A total of eight (8) valves of this configuration (four (4) for Valve Model Number V525-5631-36 and four (4) for Model number V526-5631-40) have been delivered to Westinghouse for installation in the Sanmen and Haiyang nuclear power plants located in the People's Republic of China. Neither of these plants have loaded fuel or are operational.
"The investigation, failure analyses, and stress analyses completed to-date have not provided a firm conclusion of the root cause of the crack. Westinghouse, the purchaser who imposed 10CFR21 on the procurement document of the valve models identified in question, has been informed of the condition and current status of investigation."
Submitted by Jimmy Shieh Quality Assurance Director.
* * * UPDATE PROVIDED BY JIMMY SHEIH TO JEFF ROTTON VIA FAX AT 0944 EDT ON 08/15/2014 * * *
"Subject: An update to Interim Report initially filed on 3/12/14, revised 3/13/14
"Reference: SKA23651 previously submitted
"Investigation activities since the Interim Report:
"Computer Flow and Thermal Analysis conducted from March to April 2014.
"Finite Element Stress Analysis rerun using Computer Flow and Thermal Analysis in April 2014.
"Both analysis above suggest that the design is adequate and that stress induced by rapid temperature rise would not cause the seat to crack.
"With Westinghouse assistance and permission [two] 2 production valves were disassembled and NDE (Visual, LP, radiographic, and Eddy current) of body seat area performed during May. The examinations did not identify any defect in the valve seat area.
"Contrary to all stress/thermal analysis, cracking of valve seat was reproduced early June when one of the above mentioned bodies was subjected to the same thermal shock condition that caused the initial observed cracking. The second valve was tested at the same pressure and end temperature without the thermal shock. The valve seat remained intact without cracking.
"Westinghouse has been supporting the Part 21 investigation that Valcor is leading. Westinghouse has reviewed all metallurgy, CFD, FEA, NDE, heat rise laboratory and other data Valcor collected during our thorough investigation. All of this information is currently being evaluated by Westinghouse. At this time, the only outstanding issue is for Westinghouse to review all AP1000 transient conditions that are applicable to PV13 solenoid valves. Westinghouse anticipates having the preliminary transient research completed imminently and estimates to take until Nov. 30, 2014 to have all calculations and transient research validated.
"As stated in the original notification, the condition does not affect any operating plant. Affected valves are limited to overseas construction, none have been installed to date."
Notified R2DO (Hopper) and NRR Part 21 Group via email.
* * * UPDATE PROVIDED BY JIMMY SHEIH TO JEFF ROTTON VIA FAX AT 1620 EDT ON 09/05/2014 * * *
"Westinghouse has informed Valcor that none of the affected valves have been installed and they are quarantined from accidental installation. Valcor therefore is not required to pursue 10CFR21 reporting further and we [Valcor] consider the report closed."
Notified R2DO (Seymour) and NRR Part 21 Group via email. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 50262 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MARY SIPIORSKI
HQ OPS Officer: STEVE SANDIN | Notification Date: 07/08/2014
Notification Time: 07:28 [ET]
Event Date: 07/08/2014
Event Time: 00:24 [CDT]
Last Update Date: 09/05/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID HILLS (R3DO)
|
| 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 UNIT 2 SPRAY ADDITION DECLARED INOPERABLE DUE TO TANK INDICATION GREATER THAN 67%
"At 0024 CDT on 7/8/2014, Unit 2 Spray Addition was declared inoperable and LCO 3.6.7 (Spray Additive System) not being met, which resulted in a condition reportable pursuant to 10CFR50.72(b)(3)(v)(D). The inoperability was caused by Unit 2 Sodium Hydroxide Tank level indication greater than 67%, at 67.5%. This exceeds a current Prompt Operability Determination compensatory action requirement stating 'level shall be maintained no higher than 67%.'
"At 0104 CDT on 7/8/2014, Unit 2 Sodium Hydroxide Tank level was restored to an acceptable level, less than 67%. TSAC 3.6.7B was exited and LCO 3.6.7 met."
The licensee informed the NRC Resident Inspector.
* * * RETRACTION PROVIDED BY BRADLEY DERINGTON TO JEFF ROTTON AT 1710 EDT ON 09/05/2014 * * *
"Point Beach is retracting EN# 50262 made on July 8, 2014 at 0628 CDT. The Operability Determination for this condition has been revised based upon engineering analysis. The event notification is being retracted based upon the subsequent Operability Determination revision that shows the NaOH Injection System was capable of performing its safety function at an observed Spray Additive Tank level of no higher than 77.2 percent."
The licensee has notified the NRC Resident Inspector.
Notified R3DO (Lipa). |
| Agreement State | Event Number: 50412 | Rep Org: GEORGIA RADIOACTIVE MATERIAL PGM
Licensee: GEORGIA DEPARTMENT OF TRANSPORTATION
Region: 1
City: ATLANTA State: GA
County:
License #: GA50-1
Agreement: Y
Docket:
NRC Notified By: BARTY SIMONTON
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/28/2014
Notification Time: 15:30 [ET]
Event Date: 08/28/2014
Event Time: 12:00 [EDT]
Last Update Date: 08/28/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
KEVIN MANGAN (R1DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - TROXLER MOISTURE DENSITY GAUGE STOLEN FROM PICKUP TRUCK
A Georgia Department of Transportation crew stopped for lunch at 1200 EDT on 08/28/14 at a Sam's Club in McDonough, GA. A Troxler Model 3430, S/N 31643, containing two sources: 10 mCi of Cs-137 and 40 mCi of Am241/Be, was stolen from the unattended vehicle. The Troxler was not properly secured as required. The State of Georgia is conducting an investigation into the incident.
The Henry County Police Department is investigating.
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 |
| Agreement State | Event Number: 50414 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: INOVA FAIRFAX HOSPITAL
Region: 1
City: FALLS CHURCH State: VA
County:
License #: 610-116-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/29/2014
Notification Time: 14:51 [ET]
Event Date: 08/29/2014
Event Time: [EDT]
Last Update Date: 08/29/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
KEVIN MANGAN (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MEDICAL EVENT
The following information was received via facsimile:
"On August 29, 2014, the licensee made a telephone notification of a medical event which occurred during a skin treatment using a Nucletron microSelecton 106.990 HDR. The Radiation Safety Officer indicated that a decay corrected value for the source activity was used during data entry for the treatment plan. The licensee discovered, after the administration of the treatment fraction, that the software also corrected for decay in determining the exposure time for the fraction. The extra decay correction resulted in a dose approximately twice the prescribed fraction dose of 600 cGy. The licensee has informed the referring physician and held a staff meeting to discuss the circumstances. Any future treatment fractions for the patient will be reviewed and the licensee will review its nine previous skin treatment procedures to determine if additional medical events may have occurred. Additional information, including the administered dose, will be provided by the licensee in its written report."
Event Report ID No.:VA-2014-005
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. |
| Agreement State | Event Number: 50419 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: FOREE AND VANN, INC.
Region: 4
City: PHOENIX State: AZ
County:
License #: AZ 7-263
Agreement: Y
Docket:
NRC Notified By: BRIAN GORETZKI
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/29/2014
Notification Time: 11:33 [ET]
Event Date: 08/28/2014
Event Time: 09:30 [MST]
Last Update Date: 08/29/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED MOISTURE/DENSITY GAUGE
The following information was received via facsimile:
"At approximately 0950 MST on August 28, 2014, the Agency [Arizona Radiation Regulatory Agency] was informed that the licensee had a Troxler Model 3430, portable moisture/density gauge damaged at a construction site. The damage occurred at approximately 0930 MST on August 28, 2014. The gauge was in use and was run over by construction equipment. The sealed sources were not damaged and were intact. The damaged gauge was leak tested and will be returned to Troxler for repairs. The Troxler gauge, serial number 35809, contains 8 mCi of Cesium-137 and 40 mCi of Am:Be-241.
"The Agency continues to investigate the event. The Governor's Office and US NRC are being notified of this event."
Arizona First Notice #: 14-021 |
| Power Reactor | Event Number: 50427 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MARK BRIDGES
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/05/2014
Notification Time: 00:27 [ET]
Event Date: 09/04/2014
Event Time: 19:05 [CDT]
Last Update Date: 09/05/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
CHRISTINE LIPA (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 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INOPERABLE
"On September 04, 2014, at 1905 hours [CDT], the Control Room Emergency Ventilation (CREV) system was declared inoperable due to the Air Handling Unit (AHU) tripping upon restoration of Control Room Ventilation following testing of Reactor Building Ventilation instrumentation. Troubleshooting is in progress at this time.
"Technical Specification 3.7.4, Condition A, was entered which requires the CREV system to be restored to an operable status in seven (7) days. Additionally, Technical Specification 3.7.5, Condition A, was entered which requires CREV AC to be restored to an operable status in 30 days.
"This notification is being made in accordance with 10CFR50.72(b)(3)(v)(D), '[any] event or condition that could have prevented fulfillment of a safety function,' because the CREV system is a single train system required to mitigate the consequences of an accident."
The licensee has notified the NRC Resident Inspector. |
| Part 21 | Event Number: 50428 | Rep Org: SCHULZ ELECTRIC
Licensee: SCHULZ ELECTRIC
Region: 1
City: NEW HAVEN State: CT
County:
License #:
Agreement: N
Docket:
NRC Notified By: BILL ELDREDGE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/05/2014
Notification Time: 11:08 [ET]
Event Date: 09/04/2014
Event Time: [EDT]
Last Update Date: 09/05/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
MARC FERDAS (R1DO)
DEBORAH SEYMOUR (R2DO)
CHRISTINE LIPA (R3DO)
WAYNE WALKER (R4DO)
PART 21 REACTORS GRO (EMAI)
| Event Text POTENTIAL PART 21 ISSUE ON MOTOR DEDICATIONS PERFORMED PRIOR TO JUNE 2002
The following information was obtained via fax:
"Pursuant to the 10 CFR Part 21 requirements, this letter is to notify the NRC of a potential Part 21 condition.
"While performing research on questions regarding acceleration presented by First Energy/Davis Besse, Schulz Electric identified that the acceleration calculation used to determine acceleration times for new motors which it dedicated before June 7, 2002 (at which time Schulz developed a shop instruction for calculating acceleration using the proper calculation) was incorrect. The use of this incorrect calculation could potentially cause misleading acceleration times, and therefore motors which may not perform as required by First Energy/Davis Besse and/or other customers.
"Schulz Electric will perform an evaluation to identify:
1. All projects that had acceleration calculations performed as part of a motor dedication prior to June 7, 2002.
2. The methodology used to perform the calculations.
3. Whether the actual acceleration times meet the acceleration/performance requirements of the applicable customers.
"Schulz Electric has the capability and chooses to perform the evaluation to determine if a defect exists. It is the responsibility of Schulz Electric to inform the purchaser(s), and any affected licensees.
"Schulz Electric will complete the specified evaluation of the circumstances within sixty (60) days of discovery of the potential defect. The NRC will be provided a copy of Schulz Electric's evaluation report.
"If you have any questions, please feel free to contact me [Charles 'Bill' Eldredge] by phone 203.562.5811, by fax 203.562.1082, or email me at Eldredge@schulzelectric.com." |
| Power Reactor | Event Number: 50430 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PATRICK A. HARTIG
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/06/2014
Notification Time: 11:18 [ET]
Event Date: 09/06/2014
Event Time: 09:51 [EDT]
Last Update Date: 09/07/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MARC FERDAS (R1DO)
|
| 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 OFFSITE NOTIFICATION DUE TO ONSITE OIL SPILL
"At 0951 EDT on September 6, 2014, it was determined that Beaver Valley Unit 2 had experienced an oil spill to the catch basin system that progressed to the Ohio River, requiring notification of:
National Response Center (incident report #1094523),
Pennsylvania (PA) Department of Environmental Protection,
Beaver County Emergency Management Agency,
PA Emergency Management Agency and,
Downstream water authorities (Midland Water Authority, Allegheny Ludlum, East Liverpool Water Co.)
"This notification is a required 4-hour report per 10CFR50.72(b)(2)(xi).
"Oil was inadvertently pumped from a transformer spill catch area during routine seasonal water removal efforts. Oil was not expected in the catch area and the spill catch area had tested negative for oil during pre-removal testing. An oil sheen has been detected on the Ohio River immediately surrounding the outfall. The source of the spill has been terminated, however some residual oil is washing out of the catch basin system into the river. It is estimated that less than 5 gallons entered the river.
"Clean up efforts for the catch basins are currently underway and containment efforts for the oil in the river are being evaluated. A press release is currently being planned.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM BLASE BARTKO TO HOWIE CROUCH AT 1025 EDT ON 9/7/14 * * *
The licensee has decided not to issue a press release concerning this event.
The licensee will notify the NRC Resident Inspector.
Notified R1DO (Ferdas). |
| Power Reactor | Event Number: 50431 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: EDWIN SWANSON
HQ OPS Officer: DANIEL MILLS | Notification Date: 09/06/2014
Notification Time: 13:17 [ET]
Event Date: 09/06/2014
Event Time: 06:13 [CDT]
Last Update Date: 09/06/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
CHRISTINE LIPA (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 TECHNICAL SUPPORT CENTER AIR CONDITIONING CONDENSING UNITS OUT OF SERVICE
"At 0613 [CDT] on 9/6/2014, Technical Support Center roof mounted condensing units were found tripped by operations personnel. An attempt was made to restart both condensing units, neither condensing unit would restart. This caused a loss of Technical Support Center cooling capability. Technical Support Center Air Handling system is in service and required filtration remains available. Wet bulb temperature of the TSC, taken at 0950 [CDT] is 78.0 degrees F. Corrective action process has been initiated.
"This event is reportable under 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 3, since this condition affects an emergency response facility."
The NRC Resident Inspector has been notified. | |