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Event Notification Report for June 17, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/16/2015 - 06/17/2015

** EVENT NUMBERS **


51138 51139 51140 51149 51151 51156 51158 51159 51161

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Agreement State Event Number: 51138
Rep Org: WA OFFICE OF RADIATION PROTECTION
Licensee: KING COUNTY MATERIALS LAB
Region: 4
City: RENTON State: WA
County:
License #: WN-LO22-1
Agreement: Y
Docket:
NRC Notified By: STEPHEN MATTHEWS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/08/2015
Notification Time: 13:03 [ET]
Event Date: 06/05/2015
Event Time: [PDT]
Last Update Date: 06/10/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG WERNER (R4DO)
NMSS_EVENTS_NOTIFICA ()

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE/DENSITY GAUGE

The following report was received via e-mail:

"A Troxler 3450 moisture density gauge was run over by a soft tire roller. The gauge housing was cracked open with no apparent damage to the source or shielding. The gauge was placed in its case and transported to the CTL lab in Tacoma."

The sources are: 10 mCi Cs-137 and 50 mCi Am-241

Washington Incident: WA-15-017

* * * UPDATE AT 1704 EDT ON 6/10/2015 FROM STEVE MATTHEWS TO MARK ABRAMOVITZ * * *

"A Troxler 3450 moisture density gauge was damaged by a soft tire roller at 2140 [PDT] Friday night, June 5th. The location was 15433 West Snoqualmie Valley Road, between Woodinville and Duvall near Carnation. The gauge housing was cracked open but there was no apparent damage to sources or shielding. The gauge was placed in its Type A package and transported to the licensee's facility in Puyallup. From there, the gauge was picked up by a gauge manufacture representative for repair and leak test. The incident occurred because the portable gauge operator turned away momentarily to speak with another construction worker and didn't see the roller getting close and making contact with the gauge. The licensee will be conducting additional training on constant control. There will be a citation for lack of constant surveillance and not notifying our office [Washington Office of Radiation Protection]. The actual notification we received was from the licensees customer, King County Materials Lab."

Notified the R4DO (Werner) and NMSS Events Notification (via e-mail).

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Non-Agreement State Event Number: 51139
Rep Org: ECS MID-ATLANTIC, LLC
Licensee: ECS MID-ATLANTIC, LLC
Region: 1
City: HANOVER State: MD
County:
License #: 19-31261-01
Agreement: Y
Docket:
NRC Notified By: MICHAEL DEAN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/08/2015
Notification Time: 15:51 [ET]
Event Date: 06/08/2015
Event Time: 14:30 [EDT]
Last Update Date: 06/08/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(a) - PROTECTIVE ACTION PREVENTED
Person (Organization):
JAMES DWYER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

MOISTURE/DENSITY GAUGE DAMAGED BY COMPACTOR ROLLER

At a work site on the U.S. Naval Academy grounds, a compactor roller backed over and damaged a Troxler Model 3430 moisture/density gauge. The gauge contains an 8 mCi Cs-137 source and a 40 mCi Am-241/Be source. Upon inspection of the gauge and surrounding area, the gauge case was found to be separated, but no damage was noted to the sources. The sources were in the shielded position at the time of the incident. The licensee will place the gauge back in its case, transport it to its normal storage location, and contact the manufacturer for repair/disposal.

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Agreement State Event Number: 51140
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: MISTRAS GROUP, INC
Region: 4
City: GEISMAR State: LA
County:
License #: LA-10968-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/08/2015
Notification Time: 16:35 [ET]
Event Date: 06/08/2015
Event Time: 07:00 [CDT]
Last Update Date: 06/08/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG WERNER (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - UNATTENDED RADIOGRAPHY CAMERA

The following report was received via fax:

"The incident happened on June 8, 2015, and was corrected and under the licensee's control by 0840 CDT. It was not reported to the Department [Louisiana Department of Environmental Quality] until 1150 CDT on June 8, 2015.

"A radiography exposure device was left in a company radiography rig parked at the Baton Rouge Metro Airport. A radiographer was flying out of the Baton Rouge Airport after working a job in the field. The radiographer went through security and boarded the plane departing at 0700 CDT. However, the person who was to retrieve the rig with the camera did not arrive at the airport until 0840 CDT. This means the camera alarm system was left unattended for 1 hour and 40 minutes.

"The IC alarm system for the radiography rig sounds/alarms to a 'key fob' while in the field. One potential responder was in the air with one alarming device and the other alarming device had not made it to the airport. The radiography rig was parked in a parking lot unattended. The rig and camera were retrieved at 0840 CDT the same morning.

"The camera was an AEA Delta 880, SN D8086 exposure device loaded with 34 Ci of Ir-192. The camera and the vehicle were locked and secured, but the alarming device was unmanned for approximately 2 hrs.

"The Radiation Safety Officer called in his report at approximately 1150 CDT on 06/08/2015. The situation did not result in a radiation incident. However, the potential for a radiation incident or security breach was the problem.

"At this time, LDEQ [Louisiana Department of Environmental Quality] considers this incident still open. The incident is still under investigation and review by the staff. Enforcement and corrective actions will be determined by the out-come of the investigation. The incident was considered under control by MISTRAS and reported after the exposure device was back at the MISTRAS'S Geismar, LA location."

Louisiana Report: id No.: LA150009

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Power Reactor Event Number: 51149
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ANGELO LEONE
HQ OPS Officer: STEVEN VITTO
Notification Date: 06/11/2015
Notification Time: 22:28 [ET]
Event Date: 06/11/2015
Event Time: 16:54 [EDT]
Last Update Date: 06/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JAMES DWYER (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

DEGRADED CONTAINMENT SPRAY FLOW CHECK VALVE

During containment spray pump inservice testing the minimum flow recirculation line recorded negative flow indicating reverse flow in the line. After the troubleshooting, it was determined that a degraded minimum flow check valve was allowing a path to the refueling water storage tank (RWST) for certain post loss of coolant accident (LOCA) conditions. The minimum flow isolation has been closed to eliminate the path. No actuation occurred during this time.

The NRC Resident Inspector, Connecticut Department of Energy and Environmental Protection (DEEP) Hartford, and Watertown Dispatch have been notified.


* * * UPDATE FROM TOM CLEARY TO STEVEN VITTO ON 06/16/15 AT 1349 EDT * * *

"The purpose of this call is to correct the record for the 10 CFR 50.72(b)(3)(v)(C) event report provided on June 11, 2015. Event report number 51149 states: 'During containment spray pump inservice testing ...' The condition of the degraded containment spray flow check valve was identified: 'During high pressure safety injection pump inservice testing...'."

Notified R1DO (Bickett)

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Power Reactor Event Number: 51151
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ROBERT WISE
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/12/2015
Notification Time: 14:05 [ET]
Event Date: 06/12/2015
Event Time: 09:24 [EDT]
Last Update Date: 06/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES DWYER (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

LOSS OF TONE ALERT RADIO SYSTEM

"At 1027 [EDT] on June 12, 2015, with the James A. FitzPatrick (JAF) Nuclear Power Plant operating at 100% reactor power, Oswego County Emergency Management Center notified JAF that the Tone Alert Radio System had been out of service since 0924 [EDT].

"This impacts the ability to readily notify a portion of the Emergency Planning Zone (EPZ) Population for the JAF Nuclear Power Plant. This failure meets NRC 8 hour reporting criterion 10 CFR 50.72(b)(3)(xiii).

"The county alert sirens which also function as part of the Public Prompt Notification System remain operable.

"The loss of the Tone Alert Radio System constitutes a significant loss of emergency off-site communications ability. Compensatory measures have been verified to be available should the Prompt Notification System be needed. This consists of utilizing the hyper reach system which is a reverse 911 feature available from the county 911 center. Local law enforcement personnel are also available for 'route alerting' of the affected areas of the EPZ.

"The event has been entered into the corrective action program and the [NRC] Resident Inspector has been briefed."

National Weather Service is investigating the failures.


* * * UPDATE FROM BENJAMIN EGNEW TO DONALD NORWOOD AT 1436 EDT ON 6/16/2015 * * *

"The Tone Alert System was restored to service on 6/16/15 at 1230 EDT."

The licensee notified the NRC Resident Inspector.

Notified the R1DO (Bickett).

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Power Reactor Event Number: 51156
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: LUKE HEDGES
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/15/2015
Notification Time: 20:15 [ET]
Event Date: 06/15/2015
Event Time: 19:20 [EDT]
Last Update Date: 06/16/2015
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):
BRICE BICKETT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 100 Power Operation 0 Hot Standby

Event Text

REACTOR TRIP DUE TO TURBINE TRIP

"On June 15, 2015 at 1920 EDT, Indian Point Unit 3 received a Turbine trip which directly led to a Reactor trip. Operators entered [plant procedure] E-0, Reactor Trip or Safety Injection. All control rods fully inserted. All safety systems responded as expected. The Auxiliary Feedwater (AFW) system actuated as expected. Offsite power and electrical lineups are normal. No primary or secondary code safety valves lifted. All MSIVs are open and the Main Condensers are being used as the heat sink. The Reactor is in Mode 3 and stable. Unit 2 was unaffected and remains at 100% power. Preliminary investigation determined that Breaker Number 1 in the Ring Bus was intentionally opened [by plant personnel on switching orders from the district operator] due to a problem on W93 [output feeder from Ring Bus]. Subsequently Breaker #3 went open and caused a Turbine/Reactor trip of the Unit."

The licensee notified the NRC Resident Inspector.


* * * UPDATE FROM BOB WALPOLE TO DANIEL MILLS ON 6/16/15 AT 1320 EDT * * *

The licensee previously identified "a problem on W93" which was a mistake and should have been stated as "a problem on W97". All other information was stated correctly.

The NRC Resident Inspector has been notified.

Notified R1DO (Bickett).

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Power Reactor Event Number: 51158
Facility: SUMMER
Region: 2 State: SC
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: JAMES SALTER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/16/2015
Notification Time: 10:39 [ET]
Event Date: 02/17/2015
Event Time: 08:00 [EDT]
Last Update Date: 06/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
Person (Organization):
ROBERT HAAG (R2DO)
PART 21/50.55 REACT (EMAI)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Under Construction 0 Under Construction
3 N N 0 Under Construction 0 Under Construction

Event Text

QUALITY ASSURANCE PROGRAMMATIC ISSUES

"10 CFR 50.55(e) initial notification for a failure to comply with requirements of 10 CFR 50 Appendix B associated with AP1000 nuclear power plant construction by Chicago Bridge & Iron Company (CB&I) at the V.C. Summer Units 2 & 3 construction site.

"This 50.55(e) initial notification addresses a failure to comply by CB&I, an agent of South Carolina Electric & Gas Company (SCE&G) for V.C. Summer Units 2 & 3, to meet the requirements of Appendix B, Criteria V and XV. It is concluded that Quality Assurance programmatic issues, as identified by CB&I Root Cause Analysis 2015-0539, could have produced a defect and this condition is reportable in accordance with 10 CFR 50.55(e)(3)(iii)(C). Root Cause Analysis 2015-0539 investigated the causes that lead to impingement of safety related reinforcing steel and the steel containment vessel during concrete core drilling operations within the Unit 2 containment structure. No defect has been identified.

"This condition is associated with NRC special inspection report number 05200027/2015-009.

"This notification closes the Interim Part 21 report submitted on April 16th, 2015, by CB&I.

"This 50.55(e) Initial Notification is being submitted pursuant to the requirements of 10 CFR 50.55(e)(3)(iii)(C)."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 51159
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: THOMAS MORSE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/16/2015
Notification Time: 11:34 [ET]
Event Date: 06/16/2015
Event Time: 04:52 [EDT]
Last Update Date: 06/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
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

EMERGENCY DIESEL GENERATOR FOUND INOPERABLE

"At 0452 EDT hours on June 16, 2015, during performance of a surveillance test for the Division 3 4160 Volt Bus Undervoltage/Degraded Voltage Channel Calibration and Logic System Functional Test, the K36 degraded voltage time delay relay was found outside of the Technical Specification 3.3.8.1 allowable value, resulting in an inoperable condition of the Division 3 Emergency Diesel Generator (EDG). The Division 3 EDG had previously been declared inoperable for performance of the surveillance testing.

"The K36 degraded voltage time delay relay initiates load shedding, isolates the Division 3 bus, and starts the Division 3 EDG. The Technical Specification allowable value is 180 to 270 seconds. The as-found time was 272.66 seconds. The K36 relay was calibrated in accordance with plant procedures and returned to service at 0730 hours on June 16, 2015.

"The Division 3 EDG is the on-site power source for the High Pressure Core Spray system which is a single train system. Therefore, this event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been informed."

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Power Reactor Event Number: 51161
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: WILLIAM McCOLLUM
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/17/2015
Notification Time: 04:15 [ET]
Event Date: 06/16/2015
Event Time: 23:43 [EDT]
Last Update Date: 06/17/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BRICE BICKETT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation

Event Text

SERVICE WATER EFFLUENT RADIATION MONITOR OUT OF SERVICE

The B train of the service water effluent radiation monitor failed at 2343 EDT and is being repaired.

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Wednesday, June 17, 2015
Wednesday, June 17, 2015