| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/02/2016 - 09/06/2016 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52200 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: LANCASTER GENERAL HOSPITAL
Region: 1
City: LANCASTER State: PA
County:
License #: PA-0233
Agreement: Y
Docket:
NRC Notified By: JOHN CHIPPO
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/25/2016
Notification Time: 14:29 [ET]
Event Date: 08/25/2016
Event Time: 08:30 [EDT]
Last Update Date: 08/25/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
ANGELA MCINTOSH (NMSS)
| Event Text AGREEMENT STATE REPORT - TRANSPORTED PACKAGE EXCEEDED CONTAMINATION LIMITS
The following was received from the Commonwealth of Pennsylvania:
"On August 25, 2016, the Department [Commonwealth of Pennsylvania] was notified by Lancaster General Hospital that a package was received in which 5 of the 6 sides exceeded the contamination limits in 10 CFR 71.47. This is reportable per 10 CFR 20.1906(d)(1).
"A package containing a vial of 5 milliCuries of iodine-123 in liquid form was received from GE Healthcare at approximately 0830 [EDT] this morning. The package was undamaged. The receipt survey was performed and noted removable contamination as follows: Front and handle 10,108 dpm; Right side 2,131 dpm; Front handle 4,977 dpm; Front 4,426 dpm; Top background; Top strap 4,577 dpm; Back/bottom 1,997 dpm.
"After completing wipe testing, the technologist performed an area survey. The area background was found to be 0.04 mR/hr. At 1 meter, the package was found to be 0.05 mR/hr. At the package surface the reading was found to be 0.4 mR/hr. The contamination identified as technetium-99m. Given this finding, package [was] opened to verify it was I-123. The contamination is believed to have been transferred from somewhere else. Upon return to the originator (GE) pharmacy, a survey of the delivery driver's hands, vehicle, and all packages in the vehicle was performed. None showed contamination. All hospital personnel involved and surrounding areas were surveyed and found to be contamination free. No one received a dose above regulatory limits."
Cause of the event is unknown at this time. The Department has an inspector onsite. More information will be provided when available.
Event Report ID No: PA160023 |
| Agreement State | Event Number: 52203 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: IPSCO KOPPEL TUBULARS CORPORATION
Region: 1
City: KOPPEL State: PA
County:
License #: PA-1049
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: VINCE KLCO | Notification Date: 08/26/2016
Notification Time: 10:34 [ET]
Event Date: 08/24/2016
Event Time: [EDT]
Last Update Date: 08/26/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED SOURCE ROD
The following information was received from the Commonwealth of Pennsylvania via facsimile:
"Notifications: On August 25, 2016, the Department [Pennsylvania Bureau of Radiation Protection] was notified that a licensee had a cobalt-60 (Co-60) source rod that became bent and unusable during installation into a gauge at a work location. This is reportable per 10 CFR 30.50(b)(2).
"Event Description: During the process of installing a Co-60 source rod and moving it from a transfer shield to a gauge and industrial process mold, the licensee observed difficulty in getting the source rod to insert into the mold. Using a remote handling device, the Co-60 source was partially removed from the transfer shield and briefly (about 30 seconds) inspected. It was noted that the rod was partially bent. The rod was immediately retracted into the fully shielded position in the transfer shield. The transfer shield containing the Co-60 rod was then taken to a designated storage area where it is secured from unauthorized access. The calculated dose to the workers was estimated to be 0.44 millirem. No exposures over regulatory limits occurred.
"Radionuclide: Co-60; Manufacturer: Berthold Technologies; Source Model: P 2608-100; Gauge Model: LB 300 ML; Source Serial Number: 1766-10-13; Activity: 3.8 milliCuries
"ACTIONS: The rod has been securely stored and placed out of service until repairs or return can be accomplished by a licensed service provider. The Department has scheduled a reactive inspection. More information will be provided when available."
Pennsylvania Event: PA160024 |
| Agreement State | Event Number: 52206 | Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: TRC ENVIRONMENTAL CORPORATION
Region: 1
City: NOT PROVIDED State: NY
County:
License #: NOT PROVIDED
Agreement: Y
Docket:
NRC Notified By: KAREN FLANIGAN
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/27/2016
Notification Time: 21:06 [ET]
Event Date: 08/25/2016
Event Time: 18:45 [EDT]
Last Update Date: 08/27/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST X-RAY FLUORESCENCE ANALYZER
The following was received from the State of New Jersey via email:
"NJDEP [New Jersey Department of Environmental Protection] received notification from New Jersey Transit Police at 1426 EDT on Saturday, 8/27/16, that a Niton xlp 300 series XRF with serial number 7710 belonging to New York licensee TRC Environmental Corporation was left on a New Jersey Transit bus on Thursday, 8/25/16 at approximately 1845 EDT. The licensee reported the loss of the device to New York State Department of Health on Friday, 8/26/16. The Cadmium-109 source in the device has a maximum activity of 50 mCi (per sealed source registry). This is being reported under 10 CFR 20.2201(a)(1)(i) because it exceeds 1000 times the value for Cd-109 in Appendix C. The licensee employee who left the device on the bus was taking it home to have it for a job in New York the next day. They did not plan to use the device in New Jersey.
"NY DOH [New York Department of Health] officials indicated that they will provide NJDEP with more information on Monday, 8/28/16."
State Report #: NJ-16-02
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: 52207 | Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: TRC ENVIRONMENTAL CORPORATION
Region: 1
City: WAYNE State: NJ
County:
License #: C3264
Agreement: Y
Docket:
NRC Notified By: DANIEL SAMSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/29/2016
Notification Time: 16:29 [ET]
Event Date: 08/25/2016
Event Time: 19:15 [EDT]
Last Update Date: 08/29/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST X-RAY FLUORESCENCE ANALYZER
The following report was received from the New York Department of Health:
"An employee of TRC [TRC ENVIRONMENTAL CORPORATION] put a Niton XLP-300, XRF [X-Ray fluorescence analyzer] containing 40 milliCuries of Cadmium 109 on the overhead shelf of New Jersey Transit bus #8306 and then forgot to collect the case when he got off the bus and went home. The employee contacted the NJT [New Jersey Transit] offices at approximately 0845 [EDT] on Friday, 8/26/2016, to inquire about the lost case. He provided a description of the case and a photo of a similar case. Claim number L487457 was assigned to the matter by NJT. As of 1730 on 8/26/2016, NJT staff had not located the case. A TRC Project Manager visited the PABT [Port Authority Bus Terminal] in New York City at approximately 1430 on Friday 8/26/2016. When the bus arrived, the TRC Project Manager inquired with the driver if the case had been found and double checked the bus, but did not locate the case. The TRC Project Manager also went to Customer Service/Lost and Found at PABT for NJT and made an additional claim, number L487502, with his mobile contact number should device be returned to PABT. The TRC employee will check in with the NJT lost and found department later in the evening on 8/26/2016 to ask if the case has been located."
See also EN-52206.
New York Event # NY-16-05
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 |
| Part 21 | Event Number: 52216 | Rep Org: ENERSYS
Licensee: ENERSYS
Region: 1
City: READING State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: WILLIAM ROSS
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/01/2016
Notification Time: 14:51 [ET]
Event Date: 09/01/2016
Event Time: [EDT]
Last Update Date: 09/02/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
RAY POWELL (R1DO)
JONATHAN BARTLEY (R2DO)
BILLY DICKSON (R3DO)
GREG WARNICK (R4DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART 21 - POTENTIAL FAILURE OF BATTERY SYSTEM CONNECTIONS
"This letter will serve as notification from EnerSys to the United States Nuclear Regulatory Commission of an identified deviation in published literature information. The literature defines requirements for resistance in both cell to cell and cell to terminal connections in supplied battery systems. High connection resistance causes increased cell voltage drop and a potential failure to meet run time requirements.
"Internal investigation by EnerSys confirms that no defects exist in systems tested before shipment to customer utilities as internal documented procedures define correct parameters. However, the potential of less than desired performance exists if the values noted in the literature are used during installation and test at utility sites.
"EnerSys does not have the ability to evaluate if a defect exists at customer utilities so per the provisions of Part 21, notification is being made to both the Commission and affected EnerSys customers."
POC: 800-538-3627 ext. 1974
* * * UPDATE FROM WILLIAM ROSS TO STEVEN VITTO AT 1339 EDT on 09/02/2016 * * *
"The literature in question is the EnerSys Safety, Storage, Installation, Operation and Maintenance Manual for Flooded Lead-Acid Batteries C, D, E, F and G, number US-FL-IOM-002 dated January 2007. The errors are located in Section 7.4.3.8c line 2. The current wording of '... connection is more than 30 percent or 5 Mohms above the average...' should read 'connection is more than 10 percent or 5 micro-ohms, whichever is greater, above the average'."
Licensees affected are Dominion North Anna, Dominion Surry Nuclear Power Plant, Energy Northwest Columbia Generating Station, Entergy Nuclear Operations IP2, First Energy Beaver Valley NPP, NextEra Energy Point Beach Nuclear Plant, Perry Nuclear Power Plant, and San Onofre Nuclear Generating Station.
Notified R1DO(Powell), R2DO (Bartley), R3DO (Dickson), R4DO (Warnick), and Part 21Group via email. |
| Power Reactor | Event Number: 52218 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: LARRY HAUTH
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/02/2016
Notification Time: 11:29 [ET]
Event Date: 09/02/2016
Event Time: 08:08 [CDT]
Last Update Date: 09/02/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
GREG WARNICK (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 0 | Hot Standby | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
"While operating in MODE 1 at 100 percent rated thermal power and placing Excess Letdown in service for Reactor Coolant System (RCS) leak detection, RCS operational leakage exceeded 1 gpm [gallon per minute] unidentified leakage as identified by performing RCS Water Inventory Balance using the Nuclear Plant Information System Computer. This required the entry into Technical Specification (TS) Limiting Condition of Operation (LCO) 3.4.13 Condition B at 0808 [CDT] on 9/2/16. The associated action is to place the unit into Mode 3 in 6 hours. Trending of containment sump level indicates the leakage is inside containment with the exact location within containment unknown. Containment inspection is being performed to try and identify the source of Reactor Coolant System leakage. NRC Resident Inspector has been notified. Re-alignment of the Letdown System back to its normal arrangement has subsequently reduced RCS leak rate to 0.521 gpm at 0652 CDT on 9/2/16.
"Unusual or Not Understood - Leak Location is not known at this time."
Maximum leak rate recorded was 1.358 gpm. The leak was first discovered at 08/31/16 at 1519 CDT.
Safety Related Equipment not operational - Reactor Vessel Level Indicating System (TS 3.3.3). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 52219 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DANIEL BARKER
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/02/2016
Notification Time: 23:33 [ET]
Event Date: 09/02/2016
Event Time: 19:22 [EDT]
Last Update Date: 09/04/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JONATHAN BARTLEY (R2DO)
|
| 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 SPENT FUEL POOL AREA RADIATION MONITOR LOST SIGNAL
"Unit 1 Spent Fuel Pool Area Radiation Monitor (1EMF17) lost signal resulting in off scale high indications. Subject EMF provides alarm functions and indication which are used for assessment of EAL classifications. Failure response conducted per applicable Alarm Response Procedures and subsequent actions performed per applicable license commitment required actions. Temporary dose rate monitor has been set up for area monitoring with alarm setpoint commensurate with subject EMF. Issue entered into corrective action program and prioritized to restore subject EMF to functional status within required 30 days."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM PHILIP BALES TO STEVEN VITTO AT 2323 EDT ON 9/4/2016 * * *
"This notification is being made to retract event EN 52219, which was reported on September 2, 2016. Upon further investigation, the loss of radiation monitor 1EMF17 did not prevent the evaluation of all EALs [Emergency Action Level] for the associated emergency initiating conditions. Additionally, it has been determined 1EMF17 is not utilized for performing radiological assessments.
"Therefore, no actual or potential major loss of emergency assessment capability existed per 10 CFR 50.72(b)(3)(xiii). This is consistent with NUREG 1022, Rev. 3, Supplement 1 and NEI 13-01, Rev. 0. The NRC Resident Inspector will be notified of the retraction."
Notified R2DO (Bartley). |
| Power Reactor | Event Number: 52221 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ZACH HYDE
HQ OPS Officer: DANIEL MILLS | Notification Date: 09/03/2016
Notification Time: 08:44 [ET]
Event Date: 09/03/2016
Event Time: 07:10 [CDT]
Last Update Date: 09/03/2016 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
GREG WARNICK (R4DO)
CHRIS MILLER (NRR)
BRIAN McDERMOTT (NRR)
KRISS KENNEDY (R4RA)
BERNARD STAPLETON (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 93 | Power Operation | 93 | Power Operation | Event Text UNUSUAL EVENT DECLARED DUE TO SEISMIC EVENT ALARM
At 0710 CDT, Cooper Nuclear Station declared a Notification of Unusual Event under EAL HU1.1 due to the station seismic event alarm registering a response to an earthquake (epicenter near Pawnee, OK). The reactor was not affected by the earthquake and remains at 93 percent power. The licensee is performing walkdowns of structures and equipment to verify that the site is unaffected.
Notified the DHS SWO, FEMA Ops Center, DHS NICC, FEMA National Watch Center (E-mail) and Nuclear SSA (E-mail).
* * * UPDATE FROM ZACH HYDE TO STEVEN VITTO AT 1704 EDT ON 9/3/2016 * * *
At 1547 CDT, Cooper Nuclear Station terminated the Notice of Unusual Event. All inspections and walkdowns of the plant have been completed. No damage or injuries were reported. The seismic event caused no impact to the plant.
The Licensee has notified the NRC Resident Inspector.
Notified R1DO (Warnick), NRR EO (Miller), IRDMOC (Stapleton), DHS SWO, FEMA Ops Center, DHS NICC, FEMA National Watch Center (E-mail) and Nuclear SSA (E-mail). |
| Power Reactor | Event Number: 52222 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE BRUMMITT
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/03/2016
Notification Time: 12:47 [ET]
Event Date: 09/03/2016
Event Time: 09:02 [EDT]
Last Update Date: 09/03/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
RAY POWELL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 60 | Power Operation | 60 | Power Operation | Event Text UNIDENTIFIED LEAKAGE GREATER THAN TECHNICAL SPECIFICATIONS
"At 0902 EDT, on September 3, 2016, a leak developed from 13 Charging Pump seals that resulted in an unidentified leak rate of 1.3 gpm. Salem Unit 1 entered Technical Specification 3.4.6.2.b for unidentified leakage greater than 1 gpm. The Technical Specification requires the leak rate to be restored to below 1 gpm in a 4 hour period or place the Unit in Hot Standby in the next 6 hours and Cold Shutdown within the following 30 hours. In addition there is an allowable total ECCS leakage outside of Containment value of 0.45 gpm associated with Control Room habitability to comply with GDC-19 [General Design Criteria] limits. 12 Charging Pump was placed in service and 13 Charging Pump was removed from service and isolated. The unidentified leak rate lowered to below the 0.45gpm requirement for the total ECCS leakage outside of containment and the Technical Specification value of 1 gpm.
"This event is being reported under the requirements of 10CFR50.72(b)(3)(ii)(B) as 'the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety' for exceeding the 0.45gpm total ECCS leakage allowable in accordance with GDC-19 limitations.
"The Licensee has notified the NRC Resident and the Lower Alloways Creek Township." | |