ML21321A377

NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal

ML21321A377
Person / Time
Site:	Farley
Issue date:	11/16/2021
From:	Stephanie Devlin-Gill NRC/NRR/DORL/LPL2-1
To:	Sparkman W Southern Nuclear Operating Co
References
L-2021-LLA-0136
Download: ML21321A377 (4)

Text

From: Devlin-Gill, Stephanie Sent: Tuesday, November 16, 2021 10:40 AM To: Sparkman, Wesley A.

Cc: Joyce, Ryan M.

Subject:

RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal (EPID: L-2021-LLA-0136)

Attachments: RAIs - EPID L-2021-LLA-0136.docx

Wes, Attached are the NRC staffs requests for additional information (RAIs) for SNCs license amendment request for the Joseph M. Farley Nuclear Plant, Units 1 and 2 (Agency-wide Documents Access and Management System Accession No. ML21210A242), which proposes to modify the Updated Final Safety Analysis Report to allow the removal of the encapsulation vessels around the first Containment Spray and Residual Heat Removal/Low Head Safety Injection recirculation suction isolation valves.

The NRC staff anticipates your response to the attached RAIs by COB Friday, December 17, 2021.

Thank you.

stephanie Stephanie Devlin-Gill (she/her)

Licensing Project Manager

w. 301-415-5301 U.S. NRC, NRR, DORL, LPL2-1

Hearing Identifier: NRR_DRMA Email Number: 1419 Mail Envelope Properties (DM6PR09MB48062829FFA94F158EEC7E93BD999)

Subject:

RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal (EPID: L-2021-LLA-0136)

Sent Date: 11/16/2021 10:39:55 AM Received Date: 11/16/2021 10:39:00 AM From: Devlin-Gill, Stephanie Created By: Stephanie.Devlin-Gill@nrc.gov Recipients:

"Joyce, Ryan M." <RMJOYCE@southernco.com>

Tracking Status: None "Sparkman, Wesley A." <WASPARKM@southernco.com>

Tracking Status: None Post Office: DM6PR09MB4806.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 775 11/16/2021 10:39:00 AM RAIs - EPID L-2021-LLA-0136.docx 31257 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

REQUEST FOR ADDITIONAL INFORMATION REGARDING ELIMINATION OF THE ENCAPSULATION VESSELS AROUND THE FIRST CONTAINMENT SPRAY AND RESIDUAL HEAT REMOVAL/LOW HEAD SAFETY INJECTION RECIRCULATION SUCTION ISOLATION VALVES EPID: L-2021-LLA-0136 LICENSE AMENDMENT REQUEST JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 By letter dated July 29, 2021 (Agency-wide Documents Access and Management System Accession No. ML21210A242), Southern Nuclear Operating Company (the licensee) submitted a license amendment request for the Joseph M. Farley Nuclear Plant, Units 1 and 2 (FNP). The license amendment request proposes to modify the Updated Final Safety Analysis Report (UFSAR) to allow the removal of the encapsulation vessels around the first Containment Spray and Residual Heat Removal/Low Head Safety Injection recirculation suction isolation valves.

The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following requests for additional information (RAI) are needed.

RAI 01

In Section 3 Technical Evaluation of the proposed amendments, the licensee states that containment sump suction piping design pressure is 80 pound per square inch gauge (psig) and the design temperature is 300 degrees Fahrenheit (°F). The licensee also stated that the normal operating conditions for the containment sump suction piping are significantly lower as they are isolated with borated water under stagnant conditions. In its stress analysis to ensure the piping integrity, the licensee considers the containment sump suction piping as moderate-energy piping.

The NRC staff notes that the FNP UFSAR Revision 29, Section 3K.2.1, Analysis Criteria (General), states:

The effects of pipe whip were considered only for those piping systems whose operating pressure and temperature exceed 275 psig and 200°F, respectively [denoted as high-energy piping]. For piping systems whose pressure exceeds 275 psig, but whose temperature does not exceed 200°F, or whose temperature exceeds 200°F, but whose pressure does not exceed 275 psig [denoted as moderate-energy piping], the effects of a critical crack only were considered.

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Please clarify (1) the normal operating conditions (operating pressure and operating temperature) for the containment sump suction piping, and (2) whether the definition of the moderate-energy piping used in the proposed amendments is consistent with FNPs current design and licensing basis.

RAI 02

As noted in RAI 01 above, the licensees proposed amendments consider the containment sump suction piping as moderate-energy piping, and, therefore, only considers the effects of leakage cracks were considered. In its stress analysis to ensure the piping integrity, the licensee showed that the maximum stress range does not exceed 0.4 (1.2 Sh + SA) for ASME Code such that leakage cracks need not be postulated for those portions of the containment sump suction piping.

Please clarify whether the criteria used for postulating leakage cracks used in the proposed amendments is consistent with FNPs current design and licensing basis. If not, please specify the version of NRC Branch Technical Position (BTP) 3-4, Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment, that was used in the stress analysis in the proposed amendments.

RAI 03

In Section 3 Technical Evaluation of the proposed amendments, the licensee states:

The following criteria, inputs, and assumptions were used in the stress analysis:

• The Code of Record is ASME Boiler and Pressure Vessel Code,Section III, 1971 Edition, up to and including Addenda through 1971.

• The piping analysis model utilize the ASME Boiler and Pressure Vessel Code,Section III, 1974 which has been evaluated as acceptable with no adverse impacts to the Code of Record.

Please clarify whether the use of ASME Section III, 1974 Edition for performing piping analysis is the analysis of record for FNP.

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