| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/05/2015 - 08/06/2015 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51273 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: DOMTAR PAPER COMPANY, LLC
Region: 1
City: PLYMOUTH State: NC
County:
License #: NC RAM #094-0
Agreement: Y
Docket:
NRC Notified By: DAVID CROWLEY
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 07/28/2015
Notification Time: 16:59 [ET]
Event Date: 07/22/2015
Event Time: [EDT]
Last Update Date: 07/28/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY MCKINLEY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED GAUGE WITH SHUTTER STUCK CLOSED
The following report was received from the State of North Carolina (NC) via email:
The licensee was performing routine maintenance and leak testing checks on a Berthold fixed nuclear density gauge when they discovered its shutter was stuck in the closed position. This maintenance record was dated for 7/22/2015 and listed that the device needed cleaning, showed signs of mild to moderate corrosion, the shutter failed to open, and replacement was necessary. The closed shutter was verified by a survey meter and its detector response. The [North Carolina] State was notified the following week, on 7/27/2015. The gauge manufacturer, Berthold, had already been contracted to dispose of the source and device. No exposures or radiation safety concerns have resulted from this failed shutter at this time and none are expected.
The Berthold Fixed Nuclear Gauge is serial #6625, model# LB7440 with a Berthold source serial #1329, model #D7547, 20 mCi Cs-137 source (as of 5/98). The last leak test performed March 28, 2013, that passed according to Thermofisher (3 year leak test requirement). Berthold will perform another leak test before transporting off site.
The cause of the stuck shutter is dirt and corrosion products that appear to be the leading cause of the shutter failing in the closed position. NC will follow up with the licensee to determine if dirt accumulation and corrosion occurred by operating in environmental conditions outside of the manufacturer's intentions.
NC State report: NC NMED #150022. |
| Non-Agreement State | Event Number: 51275 | Rep Org: CHEVRON USA, INC
Licensee: CHEVRON USA, INC
Region: 4
City: Covington State: LA
County:
License #: 17-29267-01
Agreement: Y
Docket:
NRC Notified By: JAMES GRIMSLEY
HQ OPS Officer: DANIEL MILLS | Notification Date: 07/29/2015
Notification Time: 20:14 [ET]
Event Date: 07/21/2015
Event Time: [CDT]
Last Update Date: 07/30/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text FIXED GAUGE SHUTTER STUCK IN THE OPEN POSITION
A fixed gauge shutter was determined to be stuck in the open position on 7/21/15. The device manufacturer was called and arrived on location on 7/24/15, and determined that the device "dip tube" is bent and the device will have to be removed for repair. The device is a Tracerco Profiler Series Fixed Density Profiler (Serial # 101020) with either 49 or 62 30mCi Am-241 sources (1470 mCi or 1860 mCi Am-241 aggregate). The device is located inside a process vessel on an offshore platform. Radiation measurements taken outside the process vessel indicate no detectable radiation. The have been no radiation exposures. The manufacturer will remove the device and repair it.
* * * UPDATE FROM RUSTY GRIMSLEY TO DANIEL MILLS AT 1852 EDT ON 7/30/15 * * *
The following was received from the licensee via email:
"In accordance with 10 CFR 30.50(b)(2), Chevron submitted a verbal notification to the NRC Operations Center at 2014 hrs. EDT on July 29, 2015. We [Chevron USA, Inc.] are submitting this written report to verify the information conveyed in the verbal report.
"Test separator MBD1010 on Chevron's Jack/St. Malo oil and gas production platform is equipped with a Tracerco Profiler Series Model T-240 fixed density profiler, serial number T240-FM-1-324. On July 21, 2015, it was discovered that this profiler's shutter was in the open position and would not close. Tracerco, the manufacturer of the device, was immediately notified. Tracerco inspected the profiler on July 24, 2015 and confirmed that the shutter would not close. Tracerco's initial investigation indicated that the density profiler source and detector tubes were bent, prohibiting the movement of the shutter.
"The Jack/St. Malo platform is located in Walker Ridge Block 718, OCS-G 32703, approximately 190 miles offshore Louisiana in the Outer Continental Shelf. The test separator is located on the Production Module lower deck. The shielded source housing and shutter mechanism are located on the Production Module mezzanine deck, which sits immediately above the separator.
"The profiler source tube contains 62 Americium 241 sources, 30 milliCuries per source, for a total of 1,860 milliCuries.
"Tracerco, the manufacturer of the profiler, is onsite and is developing a plan for disassembly and removal of the device from the separator using appropriate shielding and other protective measures to minimize potential exposures. If entry into the separator with the sources still in place is deemed necessary, Tracerco will implement appropriate radiation safety measures to minimize exposures. The device and sources will be stored in appropriate containers during shipment to Tracerco; turnover of the sources to Tracerco will be documented. As any repairs to the device or vessel entry would not constitute routine maintenance, Chevron personnel will not be involved in repairing or removing the profiler.
"There has been no exposure of platform personnel. Although the shutter remains in the open position, no one has entered the separator, and no radiation is detectable at the exterior of the separator. The separator is coated in insulation, covering the manways that provide access to the interior of the separator.
"Tracerco has been working on the Production Module mezzanine deck and has partially removed the profiler from the separator to assess its condition. Tracerco has established a barricade around the work area to prevent unauthorized access. Their monitoring indicates no exposures beyond five feet from the sources. Tracerco reports that the radiation detected appears to be lower than expected for fully unshielded sources. Tracerco has conducted wipe tests and has found no leakage from the sources."
Notified R4DO (Warnick) and NMSS Events Notification via email. |
| Power Reactor | Event Number: 51289 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: JONATHAN PRYOR
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/05/2015
Notification Time: 16:22 [ET]
Event Date: 08/05/2015
Event Time: 12:52 [EDT]
Last Update Date: 08/05/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
ART BURRITT (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 MOMENTARY LOSS OF SECONDARY CONTAINMENT
"Nine Mile Point Unit 1 (NMP1) experienced a momentary loss of Secondary Containment due to both Reactor Building (RB) airlock doors being opened at the same time.
"At 1252 [EDT] on 08/05/15, both RB airlock doors were opened simultaneously for less than 5 seconds. This resulted in Secondary Containment being declared inoperable (TS 3.4.3). Secondary Containment was restored to operable when the doors were closed.
"The event is reportable in accordance with 10 CFR 50.72(b)(3)(v)(c), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.'
"The condition has been entered into the station's corrective action program and the NRC Resident Inspector has been notified."
The licensee also notified the State of New York Public Service Commission. |
| Power Reactor | Event Number: 51290 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MCHUGH
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/05/2015
Notification Time: 18:51 [ET]
Event Date: 08/05/2015
Event Time: 15:38 [EDT]
Last Update Date: 08/05/2015 | 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):
ART BURRITT (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP ON LOW REACTOR COOLANT FLOW
"This 4-hour and 8-hour notification is being made to report that Salem Unit 2 had an unplanned automatic reactor trip. The trip occurred because the 2H 4kV infeed breaker tripped on over current protection which deenergized the 2H 4kV group bus resulting in a reactor trip on reactor coolant flow due to the loss of the 21 reactor coolant pump [RCP]. The 21 RCP remains unavailable. The cause of the over current protection trip on the 2H 4kV infeed breaker is unknown at this time.
"All control rods inserted on the reactor trip. All ECCS [emergency core cooling systems] and ESF [engineered safety feature] systems functioned as expected. The auxiliary feed pumps started as expected.
"Salem Unit 2 is currently in Mode 3. Reactor coolant system pressure is at 2235 psig and temperature is 547 degrees Fahrenheit with decay heat removal via the main steam dumps and auxiliary feedwater systems. Unit 2 has no active technical specification action statements in effect requiring a lower mode of operation due to the transient.
"The 22 auxiliary building supply fan was tagged for maintenance prior to this event and has no adverse impact of the post trip plant response or stabilization. There was no major secondary equipment tagged for maintenance prior to the event. There were no personnel injuries as a result of this event.
"There is no physical evidence of damage to the 2H 4kV bus based on visual observations and thermography."
Normal offsite power is available to the site. There is no effect on Unit 1.
The licensee has notified the NRC Resident Inspector and will notify the Lower Alloways Creek Township Police Department. |
| Part 21 | Event Number: 51291 | Rep Org: ALPHA-OMEGA SERVICES, INC
Licensee: ALPHA-OMEGA SERVICES, INC
Region: 4
City: BELLFLOWER State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TROY HEDGER
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/05/2015
Notification Time: 19:02 [ET]
Event Date: 08/04/2015
Event Time: [PDT]
Last Update Date: 08/05/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
RAY AZUA (R4DO)
PART 21 MATERIALS (EMAI)
| Event Text PART 21 - POTENTIAL RADIOACTIVE MATERIAL TRANSPORT PACKAGING SHIELDING FAILING TO COMPLY WITH 10CFR71.47 AND/OR 10CFR71.51
The following information is a summary that was excerpted from a facsimile received from Alpha-Omega Services, Inc.:
"Pursuant to 10CFR 21.21 (d)(3)(ii) Alpha-Omega Services, Inc. [AOS] is providing the USNRC with written notification of the identification of a potential failure to comply. The following information is required per 10CFR 21.21 (d)(4):
"Name and Address of the individual or individuals informing the Commission. Troy Hedger, President, Alpha-Omega Services, Inc., 9156 Rose Street, Bellflower, CA 90706
"Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect. AOS Document Number FM9054, Rev. H, Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages (Revision H, December 30, 2012; Docket No. 71-9136) Model AOS-100A Package, USA/9316/B(U)-96 (Certificate of Compliance #9316)
"Nature of the defect of failure to comply and the safety hazard which is created or could be created by such defect of failure to comply. There is a potential issue that shielding fails to comply with 10CFR 71.47 and/or 10CFR 71.51 (a)(2). This is not a 'defect' of the package, but rather an un-analyzed condition that could lead, if credible, to a safety hazard. DAHER-TLI Engineering Services notified AOS via telephone conversation on July 28, 2015 that there is a possible discrepancy in the original SAR shielding calculations originally performed. The potential discrepancy was discovered in conjunction with the independent preparation of a DAHER-TLI symposium paper that they are working on for presentation for future use of the AOS Cask family products. Specifically, DAHER-TLI observed that the AOS SAR does not analyze the radiation levels on the exterior of the package when a point source is located in a corner of the cask cavity.
"In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part. Currently, four (4) AOS-100A packages have been fabricated and three (3) were certified for use prior to August 4, 2015; one (1) is currently not in service. There are two (2) AOS-050 packages which are on hold for completion of fabrication activities. The following are the locations of the active units: AOS - Bellflower, CA, Serial no. AOS-100A-0001 (not currently in service); Elekta - Nordion Ottawa, Canada, Serial no: AOS-100A-0002; AOS - GE Vallecitos Sunol, CA, Serial no: AOS-100A-0003; Elekta - Nordion Ottawa, Canada, Serial no: AOS-100A-0004" | |