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Event Notification Report for September 06, 2017

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
09/05/2017 - 09/06/2017

EVENT NUMBERS
529505295152948

Power Reactor
Event Number: 52950
Facility: NINE MILE POINT
Region: 1     State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: JASON QUICK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/06/2017
Notification Time: 15:41 [ET]
Event Date: 09/06/2017
Event Time: 11:57 [EDT]
Last Update Date: 09/06/2017
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):
GLENN DENTEL (R1DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown
Event Text
AUTOMATIC REACTOR SCRAM ON LOW REACTOR VESSEL WATER LEVEL

"On September 6, 2017 at 1157 [EDT], Nine Mile Point Unit 1 experienced an automatic reactor scram with a Main Steam Isolation Valve (MSIV) and Containment isolation. The scram was due to reactor vessel low water level. The cause of the reactor vessel low water level is under investigation. All control rods fully inserted. Following the scram, pressure was momentarily controlled through the use of the Emergency Condenser (EC) system. At 1205, pressure control was established through the main steam lines to the condenser through the turbine bypass valves. All plant systems responded per design following the scram. The reactor scram is a 4-hour report per 10 CFR 50.72(b)(2)(iv)(B).

"The following systems automatically actuated after the scram as expected. These system actuations are an 8-hour report per 10 CFR 50.72(b)(3)(iv)(A):

1. The High Pressure Coolant Injection (HPCI) system. HPCI initiated at 1157 and was reset at 1158 when RPV level was restored above the HPCI system low level actuation set point. HPCI is a flow control mode of the normal feedwater systems, and is not an Emergency Core Cooling System.
2. The Core Spray system actuated, but did not discharge to the Reactor Coolant system. The Core Spray system was secured at 1216.
3. Containment and MSIV isolation on reactor vessel low-low water level signal.

"Nine Mile Point Unit 1 is currently in Hot Shutdown, with reactor vessel water level and pressure maintained within normal bands. Decay heat is being removed via steam to the main condenser using the turbine bypass valves. The offsite grid is stable with no grid restrictions or warnings in effect.

"The licensee has notified the NRC Resident Inspector."

No safety relief valves lifted during the transient. The main steam isolation valves were opened after the isolation signal cleared to facilitate decay heat removal. Offsite power is supplying all plant loads. There was no effect on Unit 2.

The licensee notified New York State Department of Environmental Protection and will be issuing a press release.


Agreement State
Event Number: 52951
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: INGREDION
Region: 3
City: BEDFORD PARK   State: IL
County:
License #: IL-01065-02
Agreement: Y
Docket:
NRC Notified By: GARY FORSEE
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/07/2017
Notification Time: 13:32 [ET]
Event Date: 09/06/2017
Event Time: 00:00 [CDT]
Last Update Date: 09/07/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
ANN MARIE STONE (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
Event Text
AGREEMENT STATE REPORT - LEVEL GAUGE STUCK SHUTTER

The following was received from the State of Illinois via email:

"At approximately 1052 [CDT] on 9/7/17, the RSO for lngredion (IL-01065-02) reported a shutter stuck in the 'on' position for a level gauge at their licensed facility in Bedford Park. The inoperable condition of the shutter and the resulting removal of the gauge from service occurred on 9/6/17. Reportedly, due to the mounting location of the device, no potential for exposure to personnel existed. The gauge has been removed and locked out by SAHCI [Stan A Huber Consultants, Inc.]. No surfaces of the gauge exceed 2 mR/hour and appropriate action for disposal is pending.

"The licensee reports an electronic switching device operates the shutter. This automatic device was bent and deformed as part of the operating process and the rod portion of the shutter was cracked most of the way through. As part of the remediation process, the shutter push rod broke off completely. Several unsuccessful attempts were made using WD40 and a pin to close the shutter. The gauge was removed from operation by SAHCI, keeping the primary beam away from all personnel. A 2x4x4 inch lead brick was secured to the face of the gauge. The exposure rate at the face of the gauge was less than 2mR/hr at all accessible surfaces. The gauge was secured in the locked radioactive material storage cabinet. The storage cabinet has five nuclear gauges stored within. The outside of the storage cabinet is less than 2mR/hr at the surface.

"The current plan is to properly dispose of the stuck shutter gauge. [SAHCI] request a disposal quote.

"The SSDR indicates maximum exposure rates for this device (max 500 mCi Cs-137) when the shutter is in the 'ON' position are less than 50 mR/hr at 5 cm and less than 5 mR/hr at 30 cm."


Power Reactor
Event Number: 52948
Facility: MILLSTONE
Region: 1     State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JAY CAWLEY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/06/2017
Notification Time: 14:11 [ET]
Event Date: 09/06/2017
Event Time: 11:15 [EDT]
Last Update Date: 09/06/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GLENN DENTEL (R1DO)
Power Reactor Unit Info
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
OFFSITE NOTIFICATION DUE TO POTENTIAL RELEASE OF TRITIUM BEARING WATER AND SECONDARY CHEMICALS INTO THE PROTECTED AREA

"Inspection of an underground pipe used to discharge the contents of the Unit 3 Condensate Polishing Facility in accordance with the National Pollutant Discharge Elimination System (NPDES) Discharge Permit identified the potential for small amounts of water containing tritium and Secondary chemicals to be released to the ground within the plant Protected Area. The water met all permit limits for discharge to the normal discharge point. Groundwater tritium levels were well below reportable limits. The line has been removed from service. The Connecticut Department of Energy and Environmental Protection was notified at 1115 [EDT] on September 6, 2017.

"This event is being reported in accordance with 10CFR50.72(b)(2)(xi) for 'Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made."