IR 05000364/2020011

NRC Inspection Report 05000364/2020011

ML20265A285
Person / Time
Site:	Farley
Issue date:	09/21/2020
From:	Binoy Desai Division of Reactor Safety II
To:	Gayheart C Southern Nuclear Company
References
IR 2020011
Download: ML20265A285 (8)

Text

September 21, 2020

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - NRC POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL, INSPECTION REPORT 05000364/2020011

Dear Ms. Gayheart:

On August 21, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Joseph M. Farley Nuclear Plant. On August 20, 2020, the NRC inspectors discussed the results of this inspection with Mr. Chuck Kharrl, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Binoy B. Desai, Chief Engineering Branch 3 Div of Reactor Safety Docket No. 05000364 License No. NPF-8

Enclosure:

As stated

Inspection Report

Docket Number: 05000364 License Number: NPF-8 Report Number: 05000364/2020011 Enterprise Identifier: I-2020-011-0045 Licensee: Southern Nuclear Company Facility: Joseph M. Farley Nuclear Plant Location: Columbia, AL Inspection Dates: August 10, 2020 to August 21, 2020 Inspectors: P. Cooper, Reactor Inspector Approved By: Binoy B. Desai, Chief Engineering Branch 3 Div of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC Post-Approval for License Renewal inspection at Joseph M.

Farley Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===71003 - Post-Approval Site Inspection for License Renewal From August 10 - 21, 2020, the NRC continued monitoring licensee performance at the Joseph M. Farley Nuclear Plant by conducting a Post-Approval Site Inspection for License Renewal -

Phase II in accordance with the license renewal inspection program (LRIP). This inspection took place prior to the period of extended operation (PEO) for Unit 2, which will begin on March 31, 2021. Per Inspection Manual Chapter 2516, the LRIP is the process used by NRC staff to verify the adequacy of aging management programs (AMPs), Time Limited Aging Analyses (TLAAs), and other activities associated with an applicants request to renew an operating license of a commercial nuclear power plant beyond the initial licensing period under 10 CFR Part 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.

Post-Approval Site Inspection for License Renewal ===

(1) License Conditions and Commitments for License Renewal, Implementation of Aging Management Programs and Time-Limited Aging Analyses The inspector reviewed a sample of regulatory commitments and aging management programs (AMPs), associated with the renewed operating license for Joseph M.

Farley Nuclear Plant (FNP), Unit 2 issued in May 2005. This inspection took place prior to the period of extended operation (PEO) for Unit 2, which will begin on March 31, 2021. The inspector reviewed license renewal program documents and conducted interviews with licensee staff. These activities were performed to verify that the licensee completed the necessary actions to comply with the conditions listed in the renewed facility operating license.

The AMPs and commitment items selected for the inspection sample are listed below along with the completion status of the item at the time of the inspection. The full description of each commitment is available in the UFSAR supplement for license renewal, as revised, and Appendix A of the NRC SER (ML050630571).

• Commitment Item 1: Flow Accelerated Corrosion Program. Status: Complete

• Commitment Item 5: Fire Protection Program. Status: Complete

• Commitment Item 6: Reactor Vessel Internals Program. Status: Complete

• Commitment Item 8: External Surfaces Monitoring Program. Status: Complete

• Commitment Item 10: One-Time Inspection Program. Status: Complete For each inspection sample listed, the inspector reviewed the licensing basis, program basis documents, administrative procedures and implementing procedures to verify that the program was developed as described in the license renewal application and the NRC SER. The inspector also interviewed the program owners and reviewed the results of previous program walkdowns and inspections to verify that program procedures accomplished the actions as described in the commitment and that each commitment had been implemented prior to its due date. Specific documents reviewed for each commitment and AMP are listed in this reports attachment.

INSPECTION RESULTS

Observation: Observation for Commitment 8: External Surfaces Program 71003 The FNP-0-M-114.0, External Surfaces Monitoring Program states that it identifies, evaluates, and provides appropriate corrective action for corrosion or other damage to mechanical systems and components. The program outlines a methodology for visual inspections of the exterior surfaces of selected mechanical systems and components to meet the commitments for License Renewal described in Chapter 18.2.16 of the FSAR. Section 9.0 describes the disposition of results as acceptable, acceptable with deficiencies, and unacceptable. The result of an unacceptable condition is defined as systems or components which may not be capable of performing their intended function or may fail to meet the minimum requirements specified within the design code of record prior to the next inspection. Unacceptable conditions require the implementation of corrective which are tailored to the situation and can range from restoration/refurbishment to replacement.

The inspector reviewed a sample of CRs and identified that when restoration, refurbishment, or replacement was deemed the appropriate corrective action, a work order was created, and the CRs were subsequently closed. The inspector identified that the ESM procedure does not require the program owner to actively track the completion status of the work orders. The next opportunity for the program owner to review the completion status would be during the next scheduled inspection. For the components that are dispositioned as unacceptable, this presents a vulnerability where the adverse condition may not be corrected prior to a loss of function.

Observation: Observation for Commitment 10: One-Time Inspection Program 71003 Commitment #10 states that a one-time inspection will be performed on "an RCP thermal barrier CCW nozzle." FNP-0-M-113.0, One Time Inspection Program, implements the one time inspection requirements as outlined in UFSAR Section 18.2.18 and the NRC SER. Attachment 2, Section 2.3, "RCP Closed Cooling Water Thermal Barrier Nozzle" describes the basis for the component selection.

The basis acknowledges the past failures of the RCP 2B and 2C thermal barrier outlet nozzles and the RCP 1A and 1C thermal barrier inlet nozzles. The conclusion of the component selection states that, "the 1B RCP thermal barrier nozzle piping sections have not been replaced and will be leading in terms of time in service. Examination of different piping sections may be performed if it is determined that the 1B locations are not limiting in terms of environmental exposure and / or time in service."

The inspector reviewed the root cause evaluation for the the RCP 2B and 2C failures, as well as, the corrective actions described in AI 2003201222. The corrective action document states that "another root cause was performed in 1993 as a result of cracking in the 1B RCP Thermal Barrier CCW Inlet and Outlet Piping." The licensee confirmed the 1B nozzles had been previously replaced and is reviewing the additional information to determine if further actions are necessary as described in FNP-0-M-113.0.

Observation: Observations on Aging Management Programs 71003 The inspectors identified various observations associated with the implementation of certain AMPs. The observations involved issues of minor significance that were captured in the CAP documents listed below for evaluation and resolution.

• CR 10731729: Diesel Driven Pump Acceptance Criteria

• CR 10731726: Fire Sprinkler Inspection Frequency

• CR 10731520: Inspection Results of ESM Program

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On August 20, 2020, the inspectors presented the NRC inspection results to Mr. Chuck Kharrl, Site Vice President and other members of the licensee staff.

• On August 20, 2020, the inspectors presented the Post-Approval LR Phase 2 inspection results to Mr. Chuck Kharrl, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71003 Corrective Action CR 10290262

Documents

Miscellaneous NSAC-202L-R4 Recommendations for an Effective Flow-Accelerated 2013

Corrosion Program

Procedures FNP-0-FSP-201.1 No. 1 Diesel Driven Fire Pump Functionality Test Ver. 22

FNP-0-FSP-201.2 No. 2 Diesel Driven Fire Pump Functionality Test Ver. 20

FNP-0-M-113.0 One Time Inspection Program Ver. 4

FNP-0-M-114.0 External Surfaces Monitoring Program Ver. 7

FNP-2-FSP-422.1 Sprinkler Head Testing Ver. 1.1

FNP-2-FSP-423.1 Sprinkler System Piping Nondestructive Examination Ver. 2.1

For Wall Thinning and Flow Blockage

NMP-ES-011 Flow-Accelerated Corrosion (FAC) Program Ver. 17

NMP-ES-011-001 Flow-Accelerated Corrosion (FAC) Program Implementation Ver. 14

NMP-ES-035 Fire Protection Program Ver. 6.1

NMP-ES-035-001 Fire Protection Program Implementation Ver. 14

NMP-ES-063 License Renewal Program Ver. 4

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