Event Notification Report for October 17, 2019

REACTOR COOLANT SYSTEM PRESSURE BOUNDARY DEGRADED

"At 1951 [EDT] on October 17, 2019, fretting indications on the reactor coolant system pressure boundary piping (pressurizer spray line) were identified. This condition does not appear to meet original construction code, ANSI B31.1, 1967 Edition thru summer 1971 Addenda. The condition will be resolved prior to plant startup. This event is being reported as an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

This condition will be corrected prior to the plant entering Mode 4.

* * * RETRACTION ON 10/31/19 AT 1450 EDT FROM JIM SCHWER TO BETHANY CECERE * * *

"An engineering evaluation has determined that the subject fretting is not considered a flaw, but instead is considered wear. Appendix F of Section III of the ASME Boiler and Pressure Vessel Code was applied and it was determined that the pressurizer spray line piping maintained its required design safety functions in the as-found condition. The wear has been repaired during the current refueling outage in accordance with the original construction code (ANSI B3l.l, 1967 Edition through summer 1971 Addenda) as well as Owner's Requirements.

"The NRC Resident Inspector has been notified."

Notified R1DO (Young).

PART 21 - HARDWARE FAILURE IN RADIATION MONITORING SYSTEM

The following is a summary of information received from General Atomics via fax:

On October 17, 2019, General Atomics (GA) identified a hardware failure in GA's Model RP-2C radiation monitoring system, manufactured and supplied by GA's Electromagnetic Systems Group (GA-EMS). The RP-2C radiation monitoring systems are used for post-accident monitoring of the containment area.

The defect would prevent the RP-2C from sensing a high radiation condition. This could present a potential safety hazard to personnel by not indicating the actual radiation value and by not actuating the plant systems connected to the alarm relays. It is noted that there are typically redundant high range containment monitoring systems available to the control room operators, and the operators would be able to rely on the remaining operable channels during an accident.

GA-EMS will issue a Quality Bulleting to the affected sites that will include additional detail in identifying affected modules and what to do if a defect is found. Sites are advised to continue performing their normal surveillance testing of the RP-2C module by utilizing the front panel CHECK test feature.

If you have any questions or need additional information concerning this report please contact Michael Grogan, Senior Director of Licensing, at (858) 455-2809 or Michael.Grogan@ga.com. Technical questions can be directed to Arthur Evans at (858) 964-6948.

The following plants are affected: FitzPatrick, Millstone, Peach Bottom, Pilgrim, Susquehanna, Catawba, McGuire, Saint Lucie, Sequoyah, Turkey Point, Watts Bar, Fermi, LaSalle, Palisades, Point Beach, Prairie Island, Quad Cities, Arkansas Nuclear One, Columbia Generating Station, Crystal River, Kewaunee, San Onofre, Zion.