Event Notification Report for February 01, 2018

PART 21 - REFURBISHED PRESSURE REGULATOR MAY RESULT IN EMERGENCY DIESEL GENERATOR FAILURE TO START

The following report is an excerpt from a fax from Engine Systems, Inc.:

"ESI [Engine Systems, Inc.] supplied a refurbished pressure regulator assembly, P/N 1776 506, S/N 20776487, to Brunswick Nuclear Plant in August 2017. ESI later determined that two components of the assembly, an upper and lower diaphragm plate, were omitted during reassembly of the refurbished regulator. Reference item 8 on Figure 1 for location of the diaphragm plates within the pilot valve portion of the regulator
assembly. These metal diaphragm plates distribute load and retain the associated rubber diaphragm. Omission of the metal plate may not initially affect operation of the pilot valve and therefore may not be detected during functional testing; however over repeated cycles there is a strong possibility that
the rubber diaphragm would tear or rupture without the benefit of load distribution and support
provided by the metal diaphragm plate.

"The regulator assembly is used in the safety-related air start system of the emergency diesel generators (EDGs) at Brunswick Nuclear Plant. Failure of the regulator to function properly due to the omission of a component within the pilot valve portion of the assembly could adversely affect the starting capability of the EDG. Since the EDG is a safety system used to ensure the safe shutdown of the nuclear reactor, this issue is considered to be a reportable defect as defined by 10CFR21."

UNUSUAL EVENT - FIRE IN THE TURBINE BUILDING LASTING GREATER THAN 15 MINUTES

"Nine Mile Point unit 2 experienced an unusual event due to a small fire in the turbine building that was immediately extinguished and then reflashed. The fire was declared out at 1119 [EST], 2/1/18. The fire was caused when steam leak repair injection equipment failed and leaked onto hot piping. There was no equipment damage or impact to plant operation. The fire was extinguished by the fire brigade. Offsite assistance was not required."

The fire resulted from Furmanite repair of a Moisture Separator Reheater inlet flow control valve. The unusual event will be terminated when sufficient lagging is removed to verify the extent of leaked fluid.

The licensee notified the NRC Resident Inspector.

Notified DHS SWO, FEMA, DHS NICC, and NNSA (via e-mail).

* * * UPDATE AT 1240 EST ON 2/1/2018 FROM ANTHONY PETRELLI TO MARK ABRAMOVITZ * * *

The unusual event was terminated at 1211 EST.

The licensee notified the NRC Resident Inspector.

Notified the R1DO (Janda), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA, DHS NICC, and NNSA (via e-mail).

FITNESS FOR DUTY - CONFIRMED POSITIVE TEST

"A non-licensed [employee] supervisor had a confirmed positive test for alcohol during a random fitness-for-duty [FFD] test. The individual's unescorted access to the plant has been [terminated].

"The NRC Resident Inspector has been notified."

MANUAL REACTOR SCRAM

"At 1057 CST on February 1, 2018 with the unit in Mode 1 at approximately 27% power, a manual actuation of the Reactor Protection System (RPS) was initiated due to an unexpected trip of the B Recirc Pump with A Recirc Pump in fast speed. B Recirc Pump tripped during transfer from slow to fast speed resulting in single loop operation. Operators were unable to reconcile differing indications of core flow. This resulted in a conservative decision to initiate a manual scram. The cause of the B Recirc Pump trip and the apparent issues with core flow indication are under investigation. The plant is currently stable in Mode 3.

"The plant response to the scram was as expected. All control rods [fully] inserted as expected; the feedwater system is maintaining reactor vessel water level in the normal control band and reactor pressure is being maintained with steam line drains and main turbine bypass valves.

"The NRC Senior Resident [Inspector] has been notified."

* * * RETRACTION AT 1015 EDT ON 03/22/2018 FROM DAVID DABADIE TO OSSY FONT * * *

"This event was initially reported under 10 CFR 72(b)(2)(iv)(B) as a manual actuation of the RPS due to an unexpected trip of the B Reactor Recirculation Pump with the A Reactor Recirculation Pump running in fast speed (Single Loop Operations). Operations was unable to reconcile differing indications of core flow and made the conservative decision to perform a planned shutdown in accordance with normal operating procedures. Therefore, this event 'resulted from and was part of a pre-planned sequence during testing or reactor operation' as specified in 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50.73(a)(2)(iv)(A) and NUREG-1022 Section 3.2.6. Consequently, this event is not reportable as an actuation of RPS.

"The NRC Resident Inspector has been notified."

R4DO (Groom) has been notified.

AGREEMENT STATE REPORT - DAMAGED RADIOGRAPH CAMERA

The following report was received via email:

"The radiographers placed the camera on a pipe, several feet from the ground, to take a shot. They did not secure the camera to the pipe. During the crank out process the camera fell off the pipe, face first, crimping the guide tube and causing the source to become stuck. The company called their radiographer crew located in Jacksonville, FL, to assist them in the retrieval of the source. The RSO and the helper from that office are trained in source retrieval. In the meantime, the area was cordoned off and secured until assistance could arrive. The incident occurred at approximately 1216 EST and completed the source retrieval at approximately 1900 EST. The source was not damaged. The exposure device and drive cable were put out of service and sent to the manufacturer for inspection/repair. The guide tube was damaged due to the fall and was disposed.

"The licensee will be submitting a report within a few days with detailed information. The licensee will be in the State for the remainder of the month providing us an opportunity to do an on-site inspection."

Camera: QSA Model 880 Delta
Source: Ir-192, 91 Ci
RSO dose: 310 mrem,
Helper dose: 118 mrem