| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/08/2016 - 07/11/2016 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 51988 | Rep Org: CURTISS WRIGHT
Licensee: STRUTHERS-DUNN
Region: 3
City: CINCINNATI State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TIMOTHY FRANCHUK
HQ OPS Officer: JEFF HERRERA | Notification Date: 06/08/2016
Notification Time: 09:27 [ET]
Event Date: 06/08/2016
Event Time: [EDT]
Last Update Date: 07/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
BILLY DICKSON (R3DO)
FRANK ARNER (R1DO)
ANTHONY MASTERS (R2DO)
JOHN KRAMER (R4DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART-21 REPORT - NONCONFORMANCE ON STRUTHERS-DUNN RELAY FOR PSEG NUCLEAR LLC
"This letter serves as an interim report in accordance with 10 CFR 21.21 pertaining to a potential deviation associated with Struthers-Dunn relays P/N B255XCXPFHSC125V supplied to PSEG Nuclear LLC. Based upon information obtained from PSEG, a defect may exist with the reset coil of the Struthers-Dunn relay listed above. Preliminary observations indicate the reset coil had shorted (opened) during operation, and that no other sub-components of the relay are believed to be associated with this failure. PSEG is aware of Curtiss-Wright's investigation into this failure.
"Evaluation of reportability in accordance with 10 CFR Part 21 is not able to be completed within the 60-day evaluation period due to the need for additional time to collect and evaluate the necessary information. It is currently expected that the evaluation of this defect will be completed by July 22, 2016."
POC: Timothy Franchuk
Director, Quality Assurance
4600 East Tech Drive
Cincinnati, Ohio 45245
(513) 528-7900
The licensee indicated that the current list of affected plants are being evaluated.
* * * UPDATE ON 07/08/16 AT 1511 EDT FROM MARGIE HOVER TO BETHANY CECERE * * *
The following is excerpted from the submitted report:
"Struthers-Dunn Relay P/N: B255XCXP125V. Note that the original interim report identified the part number as B255XCXPFHSC125V, which contains designators 'FHSC', which are an internal Curtiss-Wright numbering scheme."
"The following facilities were supplied the components:
Salem Nuclear Generating Station/Hope Creek Generating Station
Total Quantity: 104
Wolf Creek Generating Station
Total Quantity: 10
"Evaluation: Findings as a result of the Curtiss-Wright Failure Analysis indicated that the reset coil failure was linked to the magnet wire insulation, the coil winding process, and the attachment of the coil leads to the magnet wire
"Corrective Action: Struthers-Dunn has revised their reset coil assembly procedure such that the reset coil receives two wraps of insulation tape prior to laying the magnet wire terminations which are then soldered to the relay leads which connect to the pins at the base of the relay. Based on testing by Struthers-Dunn this two wrap process greatly increases dielectric strength which should eliminate the failure modes identified. Affected relays were returned to Struthers-Dunn to have the reset coil replaced using the revised reset coil assembly method. After the coils have been replaced they are sent to Curtiss-Wright Nuclear Division to be re-dedicated prior to being returned to the end user."
Notified the R1DO (Bower), R4DO (Drake), and Part 21 Group (via email). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 52004 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: ANDREW D. MITCHELL
HQ OPS Officer: DANIEL MILLS | Notification Date: 06/13/2016
Notification Time: 22:13 [ET]
Event Date: 06/13/2016
Event Time: 17:33 [CDT]
Last Update Date: 07/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ANTHONY MASTERS (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text ALERT SIRENS FAILED TO ROTATE
"At 1845 CDT on June 13, 2016, TVA Corporate Emergency Preparedness notified the Shift Manager at Browns Ferry Nuclear Plant that eight of the BFN [Browns Ferry Nuclear] Alert & Notification Sirens (19, 39, 55, 59, 60, 61, 69, 95) failed to rotate. The sirens were activated at 0915 CDT. Post sounding siren feedback indicated thirteen sirens that failed to rotate. BFN EP [Emergency Preparedness] Senior Instrument Mechanics were dispatched to inspect the thirteen sirens and determined, through field inspections that only eight sirens would not rotate. The field inspection was completed and communicated to Corporate Emergency Preparedness at 1733 CDT.
"Per NPG-SPP-03.5.1, the affected sirens which were lost affect 25.1 percent of the Emergency Planning Zone (EPZ) population and the sirens are not expected to be returned to service within 24 hours. Per NPG-SPP-03.5.1, a Loss of Alert and Notification System Capability exists when there is an unplanned or planned loss of primary Alert and Notification System (ANS) equipment for greater than one hour resulting in a loss of capability to alert 25 percent or more of the total Emergency Planning Zone (EPZ) population and either the Federal Emergency Management Agency (FEMA) approved backup alerting method cannot be implemented for the area affected by the lost primary ANS equipment OR the primary ANS equipment is not expected to be returned to service within 24 hours.
"TVA Corporate Emergency Preparedness is redirecting a team from Watts Bar Nuclear Plant to commence repairs on Wednesday 6/15/2016.
"This 8 hour notification is being made per the reporting requirements specified by 10 CFR 50.72(b)(3)xiii.
"The NRC Resident Inspector has been notified.
"This event has been entered in the Corrective Action Program."
* * * EVENT RETRACTION FROM MARK MOEBES TO RICHARD SMITH AT 0538 EDT ON 7/08/2016 * * *
"The licensee is retracting this event notification.
"Upon further evaluation using siren modeling software, back-up route alerting was deemed unnecessary since the overlap from neighboring sirens provided the required minimum siren coverage over all populated areas within the EPZ. The TVA siren system provides significant acoustic overlap that is not completely accounted for in the population factors used to initially determine the impacted population for the purposes of reportability. During the event, BFN remained capable of providing adequate siren coverage, and the loss of ANS equipment impacted less than 25 percent of the population within the EPZ. Therefore, this was not a reportable event.
"The NRC Resident Inspector has been notified."
Notified the RII RDO (Seymour). |
| Agreement State | Event Number: 52015 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: FLINT HILLS RESOURCES LONGVIEW
Region: 4
City: LONGVIEW State: TX
County:
License #: 06708
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/17/2016
Notification Time: 14:24 [ET]
Event Date: 06/16/2016
Event Time: [CDT]
Last Update Date: 07/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK OPEN SHUTTER ON NUCLEAR GAUGE
The following information was received from the State of Texas via email:
"On June 17, 2016, the Agency was notified by the licensee that it had discovered the shutter on a Ohmart model SH-F1 nuclear gauge containing a 50 millicurie (original activity) Cs-137 source would not close. Open is the normal position for the gauge. The licensee stated the gauge does not create an exposure risk to it's employees or members of the general public. The licensee stated a service company will be on site the week of June 27, 2016 to repair the gauge. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9413
* * * UPDATE FROM ARTHUR TUCKER TO RICHARD SMITH AT 0814 ON 07/08/16 * * *
The following update was received via email from the state of Texas:
"Update to correct licensee's name.
"Should have been recorded as Flint Hills Resources Longview. Additional information will be provided as it is received in accordance with SA-300."
The R4DO (Drake) was notified and NMSS Event Notification via email. |
| Agreement State | Event Number: 52058 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: JOHN R. BYERLY, INC.
Region: 4
City: BLOOMINGTON State: CA
County:
License #: 3516-36
Agreement: Y
Docket:
NRC Notified By: KATHLEEN HARKNESS
HQ OPS Officer: JEFF HERRERA | Notification Date: 07/01/2016
Notification Time: 16:07 [ET]
Event Date: 06/30/2016
Event Time: 15:00 [PDT]
Last Update Date: 07/01/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS HIPSCHMAN (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - TROXLER CRUSHED BY CONSTRUCTION VEHICLE
The following report was received from the California Department of Public Health via email:
"On June 30, 2016, around 2 pm [PDT], a Troxler model 3440 # 20303 (reference date 12/1979) containing 40 mCi of Cs-137 and 8 mCi of Am-241:Be was involved in an accident and was crushed by a construction vehicle. The gauge operator cordoned off the area and notified the San Bernardino County Fire/HazMat office and the CA Warning Center - Event # 16-3978. The gauge's housing was crushed and the Cs-137 source handle was bent and loose. A photograph of the damaged gauge was sent to Radiologic Health Branch (RHB) [California Department of Public Health] for evaluation. An RHB inspector responded to the construction site to assist with shielding the source rod and ensuring all radioactive material is placed into the Type A transportation box to travel to the licensee's storage area. Upon arrival, the inspector noted that the bottom plate had broken off of the shield assembly and the sliding block had fallen out of the assembly, exposing the source. The sliding block was placed back in the assembly and the bottom plate taped back onto the bottom of the shield assembly. The top and bottom halves of the gauge body were taped back together, allowing the gauge to be placed back into the transport case for transport back to storage. A survey of the area of the incident after the gauge was placed in the transport vehicle was at background, indicating the no radioactive material remained at the site. The licensee was notified to contact their service provider to arrange for the gauge to be evaluated and possibly disposed.
"Radiation level on the damaged gauge was 4 mR/hr on contact. Radiation level on the loaded Type A case was 0.6 mR/hr on contact."
California 5010 Number: 063016 |
| Agreement State | Event Number: 52059 | Rep Org: WA OFFICE OF RADIATION PROTECTION
Licensee: NELSON GEOTECHNICAL ASSOCIATES INC
Region: 4
City: WOODINVILLE State: WA
County:
License #: WN-I0421-1
Agreement: Y
Docket:
NRC Notified By: JAMES E. KILLINGBECK
HQ OPS Officer: JEFF HERRERA | Notification Date: 07/01/2016
Notification Time: 16:44 [ET]
Event Date: 06/30/2016
Event Time: [PDT]
Last Update Date: 07/01/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS HIPSCHMAN (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - TROXLER GAUGE RUN OVER BY A DRUM ROLLER
The following report was received from the Washington State Department of Health, Office of Radiation Protection via email:
"On June 30, the operator of a Troxler 3411-B portable moisture-density gauge temporarily left the gauge unattended at a construction site in Chelan, Washington, and the gauge was run over by a drum roller. The top of the gauge housing was damaged, but there was no apparent damage to the sealed sources. At the time of the impact, the source rod was retracted inside the gauge and the handle was locked. After the licensee's radiation safety officer and the Washington State Department of Health were notified about this incident, the gauge was placed back into its transport case and transported to the licensee's licensed storage location in East Wenatchee, Washington. Then a leak test wipe was conducted on each of the sources, and the leak test wipes were mailed to a laboratory for analysis. The gauge is being stored at the licensee's storage location until the leak test results have been received, and then the gauge will be either repaired or sent for disposal.
"Device type: Troxler portable gauge
Model Number: 3411-B
Serial Number 14853
Activity: Cesium-137, 8 milliCuries; Americium-241/beryllium, 40 milliCuries"
Washington Item Number: WA160003 |
| Power Reactor | Event Number: 52073 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID ARCELUS
HQ OPS Officer: DAN LIVERMORE | Notification Date: 07/08/2016
Notification Time: 08:48 [ET]
Event Date: 07/08/2016
Event Time: 06:45 [EDT]
Last Update Date: 07/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
FRED BOWER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 83 | Power Operation | 64 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO OIL SPILL
"Oil reported in the vicinity of the station's circulating water system effluent after the start of 3rd circulating water pump. The source of the oil is believed to be from oil entrained in the discharge canal from oil leak previously reported in EN#52045. One circulating water pump was removed from service to mitigate the source. The United States Coast Guard Response Center, and the New York State Department of Environmental Conservation have been notified. James A. Fitzpatrick Control Room was notified of the issue at 0645, off site agencies were first notified at 0743."
The licensee notified the NRC Resident Inspector.
Notified DOE, EPA, USDA, HHS, and FEMA. |
| Part 21 | Event Number: 52074 | Rep Org: TEAM CORPORATE
Licensee: FURMANITE
Region: 4
City: ALVIN State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: EDWARD RICH
HQ OPS Officer: BETHANY CECERE | Notification Date: 07/08/2016
Notification Time: 16:25 [ET]
Event Date: 05/01/2016
Event Time: [CDT]
Last Update Date: 07/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
DEBORAH SEYMOUR (R2DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART 21 REPORT - MATERIALS NOT PROPERLY DEDICATED
The following information was excerpted from the email received from Team Corporate:
"It was discovered during an internal audit that a Line Stop Fitting manufactured at the Furmanite Dixie Drive location and ordered from the Furmanite Charlotte location for nuclear work at Browns Ferry did not have material properly dedicated.
"Completion of the [engineering] evaluation [to determine if safety is compromised] to be complete by August 31, 2016.
A review of all safety related nuclear orders was performed and only the ones listed below are affected:
Browns Ferry - Part number SF-0615-STD for TVA Job 256-MH-131067 (Tee fitting, blank flange, gasket, studs and nuts)
Turkey Point - Part number CUS1301044-DWG-01, CUS1304019-DWG-01and CUS1304073-DWG-01(Leak Sealing cup, restraints, and enclosures) for FL&P job numbers 101-LS-104669, 101-LS-401085, and 101-LS-401142 respectively
Catawba - Part number CUS1505165-DWG-01for Duke Energy Job 101-LS-403182 (Gamma plug enclosure, studs and nuts)
POC: Edward Rich - Director of Quality
Team Corporate
200 Herman Drive
Alvin, TX 77511
(281) 388-5567 |
| Power Reactor | Event Number: 52076 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: BETHANY CECERE | Notification Date: 07/08/2016
Notification Time: 23:14 [ET]
Event Date: 07/08/2016
Event Time: 20:05 [EDT]
Last Update Date: 07/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
PATTY PELKE (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 SECONDARY CONTAINMENT TECHNICAL SPECIFICATION NOT MET
"On July 8 2016, at 19:09 [EDT] a severe thunderstorm warning was issued for Monroe County. This severe thunderstorm warning included the Fermi 2 site. Due to the high winds encountered during the thunderstorm, the Technical Specification (TS) for the secondary containment pressure boundary was not met two times during the storm for a duration time of 2 seconds total (one second for each event).
"At 20:05:21 Secondary Containment pressure went positive (0.22 inches of water gauge) and at 20:05:22 returned back below plant TS limits (-0.35 inches of water gauge).
"At 20:06:33 Secondary Containment pressure went greater than TS limits (-0.10 inches of water gauge) and at 20:06:34 returned below TS limits (-0.28 inches of water gauge).
"All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned the secondary containment pressure below the TS limits. There were no radiological releases associated with this event. The severe thunderstorm warning for the area was cancelled at 20:30.
"The TS requirement is to maintain secondary containment greater than or equal to 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) for secondary containment operability. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 52079 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: ANDREW MILLER
HQ OPS Officer: JEFF ROTTON | Notification Date: 07/10/2016
Notification Time: 10:29 [ET]
Event Date: 07/01/2016
Event Time: 05:42 [EDT]
Last Update Date: 07/10/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
PATTY PELKE (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 | Event Text FAILURE TO PERFORM TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
"At 2342 [EDT], June 30, 2016, the Control Room received panel alarms associated with Safety Features Actuation System (SFAS) Channel 2. Subsequent investigation revealed the alarms were due to a loss of supplied power caused, in part, by a level permissive in the Borated Water Storage Tank (BWST) to be inoperable. With SFAS Channel 1 BWST level transmitter previously declared inoperable for maintenance, the on-shift operating crew did not correctly identify that technical specification (TS) 3.3.5, Condition B applied which is a 6-hour shutdown required action. At 0245, following a duty team call when the condition was re-assessed, the crew entered the proper additional Condition B and correctly identified they were approximately 3 hours into a 6-hour shutdown specification. At 0330 the condition was inappropriately exited on the premise that an operable but degraded situation could be justified. The plant did not initiate a shutdown required by technical specification but, in retrospect, should have initiated and completed a shutdown within 6 hours of 2342.
" On July 1 at 1351, the BWST level transmitter for SFAS Channel 1 was repaired and declared operable [and exited TS 3.3.5 Condition B], however, the total time exceeded the 6-hour shutdown action. The plant remained stable throughout this event. On July 9, 2016, while internally discussing the event among FENOC senior leadership, it was determined that a 4-hour report would have been made if the shutdown was initiated. Hence, this report is retrospective in that a 10 CFR 50.72(h)(2)(i) required report should have been made upon the initiation of any nuclear plant shutdown required by plant's technical specification.
"A Licensee Event Report will be provided pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition that was prohibited by the plant's technical specification. The NRC Resident Inspector has been notified."
[At 1325 EDT on July 1, it was determined that the justification for SFAS channel 2 BWST level permissive to be operable but degraded could not be supported and reentered TS 3.3.5 Condition B.] | |