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Event Notification Report for December 7, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/06/2017 - 12/07/2017

** EVENT NUMBERS **


53095 53105 53106

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53095
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: NICHOLAS CRISP
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/28/2017
Notification Time: 10:01 [ET]
Event Date: 11/27/2017
Event Time: 16:45 [CST]
Last Update Date: 12/06/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
NEIL OKEEFE (R4DO)
FFD GROUP (EMAI)

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

FITNESS FOR DUTY REPORT - FALSE POSITIVE ON BLIND SAMPLES

"[On] Monday, 11/20/17, [the licensee] received a call from the MRO [Medical Review Officer] staff that the Opiate blind submitted on 11/14/17 did not test as expected. The confirmatory test was positive for codeine and morphine but negative for 6-acetylmorphine. [The licensee] requested a retest by the MRO to the laboratory. The MRO staff contacted the provider of the blind specimens for documentation of the blind analysis. The lab was requested on 11/21/17 to perform the retest by the MRO. [On] 11/27/17, the results from the lab on the retest were virtually the same as the original test result. The lab's Certifying Scientist provided a letter documenting their findings. The MRO staff informed us [Wolf Creek] and we requested copies of all documentation from the provider of the blinds, the lab and any notes from the MRO staff. Informed Superintendent Access Screening of the test results. [The licensee] contacted two plants to verify reportability under 10 CFR 26.719. [The licensee] initiated CR 00117707 to document the occurrence. Superintendent contacted licensing and management."

The licensee will inform the NRC Resident Inspector and R4 NRC Security Inspector.

* * * RETRACTION ON 12/6/17 AT 1559 EST FROM LARRY HAUTH TO DONG PARK * * *

"This event was reported under 10 CFR 26.719(c)(3). Further review shows that this event should have been reported under 10 CFR 26.719(c)(1), which only required a Licensee Event Report, not an Event Notification. This notification is retracted."

The licensee will notify the NRC Resident Inspector.

Notified R4DO (Hipschman) and FFD Group via email.

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Power Reactor Event Number: 53105
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHRISTOPHER METZ
HQ OPS Officer: BETHANY CECERE
Notification Date: 12/06/2017
Notification Time: 01:55 [ET]
Event Date: 12/05/2017
Event Time: 20:00 [CST]
Last Update Date: 12/06/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
THOMAS HIPSCHMAN (R4DO)

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

UNPLANNED LOSS OF MULTIPLE RADIATION MONITORS DURING MAINTENANCE

"At 2000 (CST), Comanche Peak experienced a failure of SCADA B of the PC11 Radiation Monitor System. This failure caused a loss of Unit 1 Main Steam Line 1-01 and 1-03 Radiation Monitors (1-RE-2325 and 1-RE-2327) and Train A and Train B Station Service Water Radiation Monitors (1-RE-4269 and 1-RE-4270). With the Main Steam Line Radiation Monitors nonfunctional, all of the emergency action levels for a steam generator tube rupture in steam generators 1-01 and 1-03 could neither be evaluated nor monitored. With the Station Service Water Radiation Monitors non-functional, all of the emergency action levels for a radioactive release through station service water could neither be evaluated nor monitored. This unplanned condition is reportable as a loss of assessment capability per 10 CFR 50.72(b)(3)(xiii).

"Comanche Peak Nuclear Power Plant (CPNPP) has assurance of steam generator integrity, reactor coolant system integrity, and fuel cladding integrity and there is a negligible safety significance to condition from a public health and safety perspective. Additionally, compensatory measures are in place to assure adequate monitoring capability is available to implement the CPNPP emergency plan in the unlikely event of challenges to the steam generator, reactor coolant system, or the fuel cladding. Until these radiation monitors were restored, Operations implemented compensatory measures to monitor the Condenser Off Gas Radiation Monitor for early signs of a steam generator tube leak/rupture and Radiation Technicians were briefed on taking local readings with a Geiger-Mueller tube on the Main Steam Lines. Chemistry Technicians were performing hourly samples of Station Service Water and reporting results to the Control Room.

"Corrective actions were pursued to restore the non-functional radiation monitors back to service. Those actions are complete and all radiation monitors have been restored to service.

"The NRC Resident Inspector has been notified."

PC11 is a computer common to both Units. The failure happened during radiation monitor maintenance to a single monitor, which unexpectedly affected multiple monitors.

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Power Reactor Event Number: 53106
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: MICHAEL FITZWATER
HQ OPS Officer: STEVEN VITTO
Notification Date: 12/06/2017
Notification Time: 12:42 [ET]
Event Date: 12/06/2017
Event Time: 09:58 [EST]
Last Update Date: 12/06/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHRISTOPHER CAHILL (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

DIESEL FUEL OIL TANK SUPPLY NON-CONFORMING WITH LICENSING BASIS FOR TORNADO GENERATED MISSILES

"On December 6, 2017, during evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornado generated missiles, Three Mile Island Nuclear Station identified a non-conforming condition in the plant design such that specific TS equipment is considered to not be adequately protected from tornado generated missiles. A tornado could generate a missile that could strike the emergency diesel generator (EDG) fuel oil supply tank (DFT) vent stack. This could result in crimping of the stack, which could affect the ability of the DFT to perform its design function if such a tornado would occur.

"This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety, and per 10 CFR 50.72(b)(3)(v)(D) for 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 mitigate the consequences of an accident.

"This condition is being addressed in accordance with NRC enforcement guidance provided in EGM 15-002 and DSS-ISG-2016-01. Compensatory measures have been implemented in accordance with these documents.

"The NRC Resident Inspector has been informed of this notification."

Page Last Reviewed/Updated Thursday, December 07, 2017
Thursday, December 07, 2017