Event Notification Report for March 22, 2024

EN Revision Imported Date: 3/22/2024

EN Revision Text: UNANALYZED CONDITION - INADEQUATE FUSES FOR FUEL POOL COOLING

The following information was provided by the licensee via email:

"On 2/9/24 at 1322 EST, it was determined that the unit was in an unanalyzed condition. A review of DC feeder circuit protection schemes identified a circuit for the fuel pool cooling system is uncoordinated due to inadequate fuse sizing. This results in a concern that postulated fire damage in one area could cause a short circuit without adequate protection, leading to the unavailability of equipment credited for in 10 CFR 50 Appendix R, Fire Safe Shutdown. This condition is not bounded by existing design and licensing documents; however, it poses no impact to the health and safety of the public or plant personnel. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B).

"The postulated event affects the following fire zones: fire areas 6S and 6N (within the Unit 2 reactor building). Compensatory actions for affected fire areas have been implemented. An extent of condition review is being performed.

"The NRC Senior Resident Inspector has been notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

Fire watches have been established in the affected areas. These will be maintained until the protection scheme is revised.

* * * UPDATE ON 03/08/24 FROM PAUL BOKUS TO TOM HERRITY * * *

The following updated information was provided by the licensee via email and phone call:

"On 03/08/24 at 1418, extent of condition reviews identified circuit(s) in the Units 2 and 3 Reactor Protection Systems (RPS) which are also uncoordinated due to improper fuse sizing. These circuits are not bounded by existing design and licensing documents for 10 CFR 50 Appendix R Fire Safe Shutdown and, therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). This event poses no impact to the health and safety of the public or plant personnel.

"The postulated event affects the following fire areas: 32, 33, 38 and 39 (Units 2 and 3 Switchgear Rooms). In accordance with procedural requirements, compensatory actions for the affected fire areas have been implemented and will remain until the condition is resolved.

"The NRC Senior Resident Inspector has been notified."

Notified R1DO (Arner)

* * * UPDATE ON 3/13/2024 AT 1538 FROM TROY RALSTON TO SAM COLVARD * * *

"On March 13, 2024, at 1350 EDT, extent of condition reviews identified a circuit in the Unit 2 reactor protection system (RPS) which is also uncoordinated due to improper fuse sizing. This circuit is not bounded by existing design and licensing documents for 10 CFR 50, Appendix R, Fire Safe Shutdown, therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). This event poses no impact to the health and safety of the public or plant personnel.

"The postulated event affects fire area 57 (Switchgear Corridor, common to Units 2 and 3). In accordance with procedural requirements, compensatory actions for the affected fire areas have been implemented and will remain until the condition is resolved.

"Additionally, it was previously reported that fire area 6N contained a circuit which was not bounded by the Fire Safe Shutdown analysis; however, after further review it has been determined that compliance is maintained in this fire area and is therefore retracted from the scope of this report.

"The NRC Senior Resident Inspector has been notified."

Notified R1DO (Jackson)

* * * UPDATE ON 3/21/2024 AT 1525 FROM PAUL BOKUS TO IAN HOWARD * * *

The following information was provided by the licensee via email:
"On 03/21/24 at 1211, extent of condition reviews identified an annunciator circuit for the Unit 3 emergency service water (ESW) and high pressure service water (HPSW) pump structure heating and ventilation panel that is also uncoordinated due to improper fuse sizing. This circuit is not bounded by existing design and licensing documents for 10 CFR 50 Appendix R Fire Safe Shutdown and, therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). This event poses no impact to the health and safety of the public or plant personnel.

"The postulated event affects fire area 47 (Unit 3 pump structure for `B' ESW and `3A'-`3D' HPSW pumps) and the yard fire area (Manhole 026D). In order to restore immediate compliance, the cable has been de-energized to eliminate the possibility of the event of concern. This circuit will remain de-energized or other measures will be implemented until the condition is permanently resolved.

"The NRC Senior Resident Inspector has been notified."

Notified R1DO (Ford)

AGREEMENT STATE REPORT - STUCK SOURCE

The following information was received from the Massachusetts Radiation Control Program (the Agency) via email:

"On 3/14/2024 at 1225 EDT, a MDS Nordion, Inc. GammaMed Plus iX high dose rate (HDR) remote afterloader device malfunctioned, leaving the source in an unshielded position. Since the quality assurance/quality control (QA/QC) checks are performed in a shielded room, no individuals received any excess dose due to this device failure.

"On the same day at 1630 EDT, individuals from a device manufacturer, Varian Medical Systems, Inc. (NRC License # 45-30957-01) came to the site and returned the device to a shielded position. One field agent received a dose of 0.025 mSv [2.5 mrem] during this operation.

"On 3/15/2024, Varian personnel performed work to repair the device. This repair work is ongoing at the time of this report.

"The Agency will follow up with UMass Healthcare Radiation Safety Officer (RSO) to determine event cause and corrective actions.

"The Agency considers this event open. The Agency will follow up with a special inspection of the licensee."

Device Information:
MDS Nordion, Inc. GammaMed Plus iX HDR remote afterloader (sealed source and device registry number: CA-1080-D-103-S)

Source Information:
MDS Nordion Inc. model GM 232, Ir-192, 4.4 Ci (sealed source and device registry number: CA-1080-S-104-S)

NMED Number: TBD

HIGH PRESSURE COOLANT INJECTION (HPCI) INOPERABLE

The following information was provided by the licensee via email and phone:

"At 0548 CDT on March 13, 2024, during a planned [high pressure coolant injection] HPCI maintenance window, a condition was identified not associated with the planned maintenance which caused HPCI to be inoperable. Specifically, the HPCI auxiliary oil pump start stop pressure switch could not be adjusted into calibration. Further investigation found that the pressure switch was not mounted as designed.

"Since HPCI is a single train system, this is a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D). The condition was corrected prior to HPCI being declared operable on March 15, 2024.

"The reason for the delay in the event notification beyond 8 hours from the event time was due to not recognizing the need to report the condition while in a planned HPCI maintenance window.

"The NRC Senior Resident Inspector has been notified."