ML20239A746

Rif Letter to Plant Hatch Simulator Inspection 41502

ML20239A746
Person / Time
Site:	Hatch
Issue date:	08/25/2020
From:	Eugene Guthrie Division of Reactor Safety II
To:	Dean S Southern Nuclear Operating Co
References
Download: ML20239A746 (4)

Text

August 25, 2020 Mr. Sonny Dean Site Vice President Southern Nuclear Operating Company, Inc.

Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513

SUBJECT:

EDWIN I. HATCH NUCLEAR POWER PLANT UNITS 1 AND 2 - PLANT REFERENCE SIMULATOR INSPECTION REQUEST FOR INFORMATION

Dear Mr. Dean:

In September and October 2020, the U.S. Nuclear Regulatory Commission (NRC) will perform an inspection of the Edwin I. Hatch Nuclear Power Plant with the onsite inspection tentatively planned for October 19 through 23. The newly installed simulator is built on a slightly different platform and has a slightly different I/O system than the existing platform.

Therefore, the inspection will verify whether or not the newly installed plant referenced simulator is designed and implemented so that it is enough in scope and fidelity to be suitable for conduct of the evolutions listed in 10 CFR 55.45(a)(1) through (13), and 55.59(c)(3)(i)(A) through (AA) using NRC Inspection Procedure (IP) 41502, Nuclear Power Plant Simulation Facilities.

This inspection is resource-intensive for both the NRC inspectors and your staff. To minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. It is important that all these documents are up-to-date, and complete, to minimize the number of additional documents requested during the preparation, and/or the onsite portions of the inspection.

We have discussed the schedule for these inspection activities with your staff. We understand that our regulatory contact for this inspection will be Kip Wainwright ((334)-453-3617; bkwainwr@southernco.com ) of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, David Lanyi at 404-997-4487 (david.lanyi@nrc.gov), or the Chief, Operations Branch 2, Eugene Guthrie at 404-997-4662 (Eugene.Guthie@nrc.gov).

S. Dean This letter and its enclosure will be made available for public inspection and copying at https://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, and Requests for Withholding.

Sincerely,

/RA/

Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos.: 50-321, 50-366 License Nos.: DPR-57, NPF-5

Enclosure:

Document Request List cc: Distribution via Listserv

SUBJECT:

EDWIN I. HATCH NUCLEAR POWER PLANT UNITS 1 AND 2 - PLANT REFERENCE SIMULATOR INSPECTION REQUEST FOR INFORMATION dated August 25, 2020 DISTRIBUTION M. Kowal L. Gibson David Lanyi Gene Guthrie OE Mail RIDSNRRDROS PUBLIC RidsNrrPMHatchResource ADAMS Accession No:ML20239A746 OFFICE RII: DRS/OB2 RII: DRS/OB2 Names D. Lanyi G. Guthrie DATE 8/25/2020 8/25/2020

Document Request List Inspection Dates: September 2 - October 23, 2020 Inspection Procedure (IP): 41502, Nuclear Power Plant Simulation Facilities Note: This is a list of the documents to be provided to the inspector. The current version of these documents is expected unless specified otherwise. The preferred file format is Word or searchable .pdf files. [Note that the inspectors cannot accept data provided on USB or flash drives due to NRC IT security policies It is not the intent that large or burdensome data be scanned for this. This data will be inspected using original documentation. Material can be provided prior to the inspection via Southern Companys ftp site.

Follow-up Document Request (Due September 11, 2020)

• Steady State Performance at 100% Power - Test #: 617-1/2

• Startup from cold shutdown to 100% RTP - Test #: 601-0

• Maximum Size Un-isolable Main Steam Line Rupture - Test #: 709-0

• Simultaneous Closure of all Main Steam Isolation Valves Combined with Single Stuck Open Safety/Relief Valves (Inhibit Activation of High Pressure Emergency Core Cooling Systems)

- Test #: 710-0

• Feedwater System Failure

• Loss of SDC

• MSL/Feedline Breaks

• Failure of Auto Rx Trip System

• Rx Pressure Control Failure

• Core Performance Testing

• Complete Deficiency Reports for:

1. 18879

2. 22486

3. 22563

4. 22647

5. 23116 Lead Inspector Contact Information:

David.Lanyi 404-997-4487 David.Lanyi@nrc.gov Enclosure