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Event Notification Report for September 30, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/29/2016 - 09/30/2016

** EVENT NUMBERS **


52256 52257 52270 52271

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Agreement State Event Number: 52256
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: CIVIL & ENVIRONMENTAL CONSULTANTS INC.
Region: 1
City: PITTSBURGH State: PA
County:
License #: PA-1147
Agreement: Y
Docket:
NRC Notified By: JOE MELNIC
HQ OPS Officer: STEVEN VITTO
Notification Date: 09/22/2016
Notification Time: 11:21 [ET]
Event Date: 09/21/2016
Event Time: [EDT]
Last Update Date: 09/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PAUL KROHN (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE

The following was received from the Commonwealth of Pennsylvania via fax:

"A Troxler nuclear gauge was hit by an asphalt road compactor while on a temporary job site. Impact rendered the gauge unusable. The area was secured and the licensee Radiation Safety Officer determined that the gauge was not leaking. The gauge was then secured for shipment back to Troxler for possible repair or replacement. There was no exposure to workers or the public.

"The gauge has been secured for transport to Troxler. The Department [PA Department Bureau of Radiation Protection] was also onsite to verify radiation measurements and perform a reactive inspection. More information will be provided when available.

"Radionuclides: Cs-137 / Am-241:Be
Manufacturer: Troxler
Model: 3430
Serial Number: 21864
Activity: 9 mCi (Cs-137) / 44 mCi (Am-241)

"Event Report ID No: PA 160026"

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Agreement State Event Number: 52257
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: CHEMOURS
Region: 1
City: FAYETTEVILLE State: NC
County:
License #: 026-0109-7
Agreement: Y
Docket:
NRC Notified By: TRAVIS CARTOSKI
HQ OPS Officer: JEFF HERRERA
Notification Date: 09/22/2016
Notification Time: 17:56 [ET]
Event Date: 04/20/2016
Event Time: [EDT]
Last Update Date: 09/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PAUL KROHN (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - NUCLEAR GAUGE STUCK SHUTTER

The following report was received from the North Carolina Department of Health and Human Services via email:

"The Agency [North Carolina Department of Health and Human Services] was notified of service contract reciprocity 0003-R Ronan to arrive at NC [North Carolina] Licensee Chemours in Fayetteville on 9/21/16. Ronan to work on a Ronan SA-1, Gauge SN:M1713, Cs-137, 20 mCi (decayed to approx 10 mCi) with a stuck shutter.

"[The North Carolina Radioactive Materials Branch Health Physicist] went to Chemours 0109-7 to conduct a reciprocity inspection, and conducted an investigation regarding [Chemours] failing to notify the Agency [North Carolina Department of Health and Human Services] of a stuck shutter on a radioactive gauge. The stuck shutter was identified during scheduled leak test and shutter testing by Chemours workers in June, 2016. This was confirmed with the RSO [Radiation Safety Officer].

"Shutter was in the open position. No members of the public or workers were at risk of exposure (due to facility design).

"Source: Cs-137
Activity: 0.020 Ci
Manufacturer: Ronan Engineering
Model Number: sa-1
Serial Number: m1713

"NC Item Number: NC160030"

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Power Reactor Event Number: 52270
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRIAN DEVINE
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/30/2016
Notification Time: 02:11 [ET]
Event Date: 09/29/2016
Event Time: 17:00 [EDT]
Last Update Date: 09/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WILLIAM COOK (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

TSC VENTILATION INDICATION ISSUE IDENTIFIED FOLLOWING SURVEILLANCE TESTING

"On 9/29/2016 at 1700 [EDT] the MCR [Main Control Room] was notified of a potential Technical Support Center [TSC] emergency ventilation indication issue following surveillance testing. At 2350 troubleshooting revealed a blown control power fuse which affected functionality of TSC HVAC emergency mode. The system was restored to operable as of 0043 on 9/30/16.

"If an emergency had been declared and TSC activation was required, the TSC would have been staffed and activated unless the TSC became uninhabitable due to ambient temperatures, radiological or other conditions. The Station Emergency Director would assess habitability in accordance with station procedures. If TSC relocation becomes necessary, then personnel would be directed as required until such time that the TSC emergency ventilation system was returned to service."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 52271
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: MARK GOHMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/30/2016
Notification Time: 04:01 [ET]
Event Date: 09/29/2016
Event Time: 21:00 [CDT]
Last Update Date: 09/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
WILLIAM COOK (R1DO)
CHRIS MILLER (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

UNISOLABLE LEAK ON DECAY HEAT REMOVAL PIPING DUE TO WELD FAILURE ON A 1" COMMON PIPE

"At 2100 CDT on 09/29/16, while in Mode 6, both trains of Decay Heat (Residual Heat Removal) were declared inoperable due to a cracked weld on a 1" common pipe. The leak developed in a USAS B31.7, Class1 pipe at a weld upstream of pressure indication isolation valve DH-1037. The leak is not isolable from the common 8-inch Decay Heat piping and encompasses approximately 1/3 [one third] of the pipe circumference.

"At the time of discovery, the unit was in Lowered Inventory with both Loops of Decay Heat in service. Subsequently, one train of Decay Heat has been secured to reduce the likelihood of crack propagation. One Train of Decay Heat remains in service providing the function of removing Decay Heat and the other train is readily available. The leakage impacts redundant equipment required to fulfill a safety function. In the current condition, both trains are required to be operable to meet Technical Specification LCO 3.9.5, Decay Heat Removal (DHR) and Coolant Circulation-Low water Level.

"This condition is reportable per 10 CFR 50.72(b)(3)(v)(B) for any event or condition that results in a loss of Safety Function associated with the Decay Heat System (Residual Heat Removal System).

"The licensee has notified the NRC Resident Inspector."

The leak is approximately 0.25 gallons per minute and pipe pressure is 140 psi. Compensatory measures are in place and include an individual posted to watch the pipe in case plugging is necessary. Repairs to the pipe will be completed once pipe is able to be drained.

Page Last Reviewed/Updated Friday, September 30, 2016
Friday, September 30, 2016