Event Notification Report for October 26, 2021

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
10/25/2021 - 10/26/2021

EVENT NUMBERS
55436 55530 55532
Power Reactor
Event Number: 55436
Facility: Waterford
Region: 4     State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: John Lewis
HQ OPS Officer: Bethany Cecere
Notification Date: 08/30/2021
Notification Time: 01:50 [ET]
Event Date: 08/29/2021
Event Time: 18:04 [CDT]
Last Update Date: 10/25/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
KOZAL, JASON (R4)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Hot Shutdown 0 Cold Shutdown
Event Text
EN Revision Imported Date: 10/26/2021

EN Revision Text: SAFETY SYSTEM ACTUATION

"At 1804 CDT on 8/29/2021, Waterford 3 Steam Electric Station (WF3) experienced a Loss of Off Site Power event due to Hurricane Ida (See EN #55435). This event caused an automatic actuation of Emergency Diesel Generators Trains A and B. Both Emergency Diesel Generators started as designed and both are currently operating normally supplying power to their respective Class 1E Safety Busses. This automatic actuation is reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A). Prior to the loss of offsite power, WF3 was in progress of performing a plant cooldown in accordance with procedural guidance. As part of this cooldown and after entering Mode 4, all Safety Injection Tanks were isolated. As a result of losing offsite power, Reactor Coolant System Temperature increased above 350F which is above the temperature requirements for Mode 4. Safety Injection Tanks are required to be unisolated and OPERABLE in Mode 3. Therefore, with no Safety Injection Tanks OPERABLE, this constituted an event or condition that could have prevented the fulfillment of a safety function and the unit entered Technical Specification 3.0.3. The unit was in Technical Specification 3.0.3 for approximately 43 minutes from 1805 CDT until 1848 CDT when Mode 4 conditions were re-established. This event or condition that could have prevented the fulfillment of a Safety Function is reportable in accordance with 10 CFR 50.72(b)(3)(v)(D).

"While continuing to perform the Reactor Coolant System Cooldown and prior to placing Shutdown Cooling Train in service, it became necessary to start one train of Emergency Feedwater. Emergency Feedwater Train A was manually started at 1847 CDT to feed the Steam Generators and was secured at 1947 CDT. Emergency Feedwater Train A started and operated normally during this period. This manual actuation is reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A)."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 1549 EDT ON OCTOBER 25, 2021 FROM CHANTEL HATTAWAY TO BRIAN P. SMITH * * *

"The purpose of this notification is to revise Event Notification Report (EN) 55436 to include a partial retraction. On August 29, 2021, Waterford Steam Electric Station, Unit 3 (WF3) experienced a loss of offsite power (LOOP) event due to Hurricane Ida. Prior to the LOOP, WF3 had shutdown to Mode 3 (Hot Standby) in anticipation of the LOOP and was performing a plant cooldown in accordance with procedural guidance. When Mode 4 (Hot Shutdown) was achieved, all Safety Injection Tanks (SITs) were isolated as part of the plant cooldown. After the LOOP, Reactor Coolant System (RCS) temperature increased and the Core Exit Thermocouples (CETs) indicated that RCS temperature had exceeded 350 degrees F. Based on the CETs, this was above the temperature requirements for Mode 4 and, as such, WF3 declared entry into Mode 3. The SITs are required to be unisolated and Operable in Mode 3. Since no SITs were Operable at that time, it was determined that this constituted an event or condition that could have prevented the fulfillment of a safety function and included this as part of the EN 55436 report in accordance with 10 CFR 50.72(b)(3)(v)(D).

"An engineering evaluation has subsequently been performed to validate whether the RCS temperature excursion following the LOOP actually reached 350 degrees F. As defined in WF3 Technical Specification (TS) Table 1.2, Operational Mode temperatures are a function of RCS average temperature (Tavg), not just the indicated temperature of the CETs. Based on the calculated Tavg using validated temperatures, it was concluded that 350 degrees F was not reached. Thus, WF3 remained in Mode 4 following the LOOP and there was no event or condition that could have prevented the fulfillment of a safety function that was reportable pursuant to 10 CFR 50.72(b)(3)(v)(D).

"The remainder of EN 55436 remains correct and unchanged."

The licensee notified the NRC Resident Inspector.

Notified R4DO (Pick)


Agreement State
Event Number: 55530
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: Commercial Metals
Region: 4
City: Durant   State: OK
County:
License #: OK-32199-01
Agreement: Y
Docket:
NRC Notified By: Mike Broderick
HQ OPS Officer: Brian P. Smith
Notification Date: 10/18/2021
Notification Time: 14:24 [ET]
Event Date: 10/18/2021
Event Time: 13:00 [CDT]
Last Update Date: 10/18/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
GEPFORD, HEATHER (R4)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Event Text
EN Revision Imported Date: 10/26/2021

EN Revision Text: AGREEMENT STATE REPORT - FOUND GAUGE

The following summary was received via e-mail from the Oklahoma Department of Radiation Management [the department]:

On October 18, 2021 at 13:00 CDT, the licensee contacted the department to inform them that they had discovered a density gauge Model RLL 1, Sn 209689a, Cs-137 source, 0.9 millicuries as manufactured, in an incoming load of scrap. The date of manufacture was June 2008 and does not appear to be designed to have a shutter. Contact, no shutter, open side readings were 33 mR/hour while closed side readings at 3 feet were less than 1 mR/hour. The gauge had gotten past gate monitors but triggered an alarm on the conveyer belt. The licensee contacted the vendor who told them that the gauge was sold as a general license in Texas to be used for level detection on a dredge. The gauge is currently being held in a drum onsite under lock and key.


Agreement State
Event Number: 55532
Rep Org: RI DEPT OF RADIOLOGICAL HEALTH
Licensee: Rhode Island Hospital
Region: 1
City: Providence   State: RI
County:
License #: 7D-051-01
Agreement: Y
Docket:
NRC Notified By: Alexander Hamm
HQ OPS Officer: Brian P. Smith
Notification Date: 10/19/2021
Notification Time: 15:57 [ET]
Event Date: 04/17/2019
Event Time: 12:00 [EDT]
Last Update Date: 10/19/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
BICKETT, BRICE (R1)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
Event Text
EN Revision Imported Date: 10/26/2021

EN Revision Text: AGREEMENT STATE REPORT - MEDICAL EVENT - UNDERDOSE OF I-131

The following report was received via email:

"Rhode Island Department of Health was notified on May 2, 2019 by a representative from Rhode Island Hospital of a medical event that occurred during an attempted dosing of 25 mCi of I-131. On April 17, 2019, a patient was administered a capsule of I-131, but was unable to swallow and the capsule began to break down in the patient's mouth. As this was not the prescribed use of the radiopharmaceutical, the staff of Rhode Island Hospital transferred the capsule to a cup as the capsule was breaking down. The cup was then brought to the lead-lined safe in the hospital's nuclear medicine hot lab. During the transfer some of the I-131 that had begun to leak from the capsule spilled onto the floor and contaminated it with I-131.

"The floor of the injection room that had been contaminated with I-131 underwent decontamination. Before decontamination, the maximum counts/min (cpm) per 100 cm squared was equal to approximately 151,000 cpm. After decontamination the maximum amount in any location was 11,000 cpm. Similarly, before the protective covering was laid over the contaminated parts of the floor, the maximum dose rate as read by Ludlum Model 9DP was 70 mR/hour on contact. Rhode Island Hospital's Radiation Safety Officer (RSO) attempted to clean up the spill and then laid protective material over the floor and measured that the dose rate upon contact with a Ludlum Model 9DP ion chamber did not exceed 70 microR per hour. No other persons or surfaces were deemed to be contaminated after surface wipe tests and a thyroid scan bioassay. The following day, April 18, 2019, 25 mCi of I-131 was attempted to be administered orally in liquid form which the patient failed to swallow as well. This did not result in a spill. The State is not performing any additional action at this time.

"The referring physician, patient, and patient's legal guardians were notified that the dose of I-131 was not received to the patient. No overexposure occurred. This event was discovered due to be reported during the October 2021 IMPEP review of the Rhode Island Radiation Control Agency."

Rhode Island Event Number: RI-21-0002

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.