ML22308A157

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Request for Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds
ML22308A157
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 11/04/2022
From: Coleman J
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
Shared Package
ML22308A156 List:
References
ND-22-0817
Download: ML22308A157 (1)


Text

A Southern Nuclear November 4, 2022 Docket No.:

52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 3 and 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel ND-22-0817 10 CFR 50.55a Request for Alternatives: Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds (VEGP 3&4-ISl1-ALT-17), and Alternative for Use of Code Case N-648-2 for lnservice Inspection of the Reactor Vessel Nozzle Inside Radius (VEGP 3&4-ISl1-AL T-18)

Ladies and Gentlemen:

Pursuant to 10 CFR 50.55a(z)( 1 ), Southern Nuclear Operating Company (SNC), the licensee for Vogtle Electric Generating Plant (VEGP) Units 3 and 4, requests NRC authorization to use alternatives to the requirements of Section XI, IWB-2500 and Table IWB-2500-1 of the ASME Boiler and Pressure Vessel (B&PV) Code, 2017 Edition. The proposed requests for alternative are applicable to activities related to the first lnservice Inspection (ISi} Interval at VEGP Units 3 and 4. The details of the 10 CFR 50.55a(z)(1) requests are contained in the enclosures to this letter. Approval is requested by August 4, 2023, to support activities during subsequent refueling outages at VEGP Units 3 and 4.

During an NRC public teleconference call on October 27, 2022, SNC presented drafts of the alternative requests and received feedback from the NRC in preparation for the final submittal of this letter and its enclosures. to this letter provides the proposed alternative VEGP 3&4-ISI 1-AL T-17 in accordance with 10 CFR 50.55a(z)(1 ). to this letter provides the proposed alternative VEGP 3&4-ISI 1-AL T-18 in accordance with 10 CFR 50.55a(z)(1 ).

This letter contains no regulatory commitments. This letter has been reviewed and confirmed to not contain security-related or proprietary information. Should you have any questions, please contact Mr. Will Garrett at (706) 848-7154.

U.S. Nuclear Regulatory Commission ND-22-0817 Page 2 of 2 Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 JMC/NBC/sfr

Enclosures:

1)

Vogtle Electric Generating Plant (VEGP) Units 3 & 4 - Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) -Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds (VEGP 3&4-ISl1-ALT-17)

2)

Vogtle Electric Generating Plant (VEGP) Units 3 & 4 - Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) - Alternative for Use of Code Case N-648-2 for lnservice Inspection of the Reactor Vessel Nozzle Inside Radius Sections (VEGP 3&4-ISl1-ALT-18) cc:

Regional Administrator, Region II VPO Project Manager Senior Resident Inspector - Vogtle 3 & 4 Director, Environmental Protection Division - State of Georgia Document Services RTYPE: VND.LI.L00 File AR.01.02.06