ML23114A357

Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency

ML23114A357
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/10/2023
From:	Thomas Wengert NRC/NRR/DORL/LPL4
To:	Entergy Operations
References
EPID L-2022-LLR-0080
Download: ML23114A357 (1)

Text

May 10, 2023 ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc.

N-TSB-58 1448 S.R. 333 Russellville, AR 72802

SUBJECT:

ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - REGULATORY AUDIT

SUMMARY

CONCERNING REVIEW OF REQUEST FOR ALTERNATIVE ANO-CISI-002 REGARDING CONTAINMENT INSERVICE INSPECTION FREQUENCY (EPID L-2022-LLR-0080)

Dear Sir or Madam:

By letter dated November 10, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22316A001), Entergy Operations, Inc. (the licensee) submitted a request to use an alternative to certain requirements of subsection IWL of the American Society for Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, at Arkansas Nuclear One, Units 1 and 2. Per the ASME Code,Section XI, the periodic visual examination and physical testing of containment building concrete are required in accordance with table IWL-2500-1 L-A, as well as physical testing of unbonded post-tensioning systems in accordance with table IWL-2500-1 L-B.

The licensee also proposed an alternative to the requirements of ASME Code,Section XI paragraph IWL-2523 to limit the scope of wire strands required to be removed (under subparagraph IWL-2523.1) and examined (in accordance with subparagraph IWL-2523.2).

To support its review of the alternative request, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a regulatory audit via the use of an online reference portal set up by the licensee. The NRC staff reviewed calculations and analyses supporting the licensees alternative request. The audit summary is enclosed.

If you have any questions, please contact me at (301) 415-4037 or by email to Thomas.Wengert@nrc.gov.

Sincerely,

/RA/

Thomas J. Wengert, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368

Enclosure:

Audit Summary cc: Listserv

REGULATORY AUDIT

SUMMARY

CONCERNING REVIEW OF REQUEST FOR ALTERNATIVE ANO-CISI-002 REGARDING CONTAINMENT INSERVICE INSPECTION FREQUENCY ENTERGY OPERATIONS, INC.

ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 DOCKET NOS. 50-313 AND 50-368

1.0 BACKGROUND

By letter dated November 10, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22316A001), Entergy Operations, Inc. (Entergy, the licensee) submitted a request to use an alternative to certain requirements of subsection IWL of the American Society for Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),

Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, at Arkansas Nuclear One, Units 1 and 2. Per the ASME Code, the periodic visual examination and physical testing of containment building concrete are required in accordance with table IWL-2500-1 L-A, as well as physical testing of unbonded post-tensioning systems in accordance with table IWL-2500-1 L-B. The licensee also proposed an alternative to the requirements of paragraph IWL-2523 to limit the scope of wire strands required to be removed (under subparagraph IWL-2523.1) and examined (in accordance with subparagraph IWL-2523.2).

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensees alternative request and determined that a regulatory audit would assist in the timely completion of the licensing review process. The audit was conducted in accordance with the audit plan dated February 6, 2023 (ML23030A628).

2.0 AUDIT DATES AND LOCATION The regulatory audit was conducted via an internet portal established by the licensee from February 13, 2023, through April 7, 2023.

3.0 AUDIT ACTIVITIES The purpose of the audit was for the NRC staff to examine the licensees non-docketed information with the intent to gain a better understanding of the alternative request, to verify information, and to identify information that may require docketing to support the basis of the NRC staffs licensing decision. The audit activities conducted by the NRC staff included a review of calculations, reports, and analyses supporting the licensees proposed alternative request.

The audit team did not have a need for any clarification calls with the licensee during the audit period.

Enclosure

The licensee provided the following supporting calculations and evaluations for the NRC staff to review via the online reference portal:

Calculation No. CALC-97-E-0009-24, Unit 2 Tendon Surveillance Wire Force Curves, Revision 0, October 7, 1997 Calculation No. CALC-99-E-0015-01, Unit 1 Predicted Tendon Prestress Forces for 20 Year License Extension, Revision 0, November 20, 2013 Calculation No. CALC-97-E-0009-05, Unit 2 Containment Side Shell Design Report, Revision 2, June 23, 2022 Engineering Report No. M-EP-2004-005, Engineering Evaluation Report per IWL-3300 for the 30 Year ANO-1 Containment Building Tendon Surveillance and Concrete Inspection, Revision 1, January 10, 2022 Engineering Report No. CALC-ANO1-CS-09-00002, Engineering Evaluation Report per IWL-3300 for the 35th Year ANO-1 Containment Building Tendon Surveillance and Concrete Inspection, Revision 0, July 29, 2009 Engineering Report No. CALC-ANO1-CS-13-00006, Engineering Evaluation Report per IWL-3300 for the 40th Year ANO-1 Containment Building Tendon Surveillance and Concrete Inspection, Revision 0 Engineering Report No. CALC-ANO1-18-000005, Engineering Evaluation Report per IWL-3300 for the 45th Year ANO-1 Containment Building Tendon Surveillance and Concrete Inspection, Revision 0 Document No. AN-N1052-501, Final Report for the ANO Unit 2 30th Year Tendon Surveillance, Revision 0, September 15, 2010 Engineering Report No. CALC-ANO2-CS-14-00003, Engineering Evaluation Report per IWL-3300 for the 35th Year ANO Unit 2 Containment Building Tendon Surveillance and Concrete Inspection, Revision 0 Engineering Report No. CALC-ANO2-CS-20-00004, Engineering Evaluation Report per IWL-3300 for the 40th Year ANO Unit 2 Containment Building Tendon Surveillance and Concrete Inspection, Revision 0 Nonconformance/Corrective Action Report No. FN465-003 for Dome Tendon 3D20 in Unit 1 20th Year Surveillance, February 24, 1994 Condition Report CR-ANO-1-1999-00317, ANO-1 25 Year Tendon Surveillance on Tendon 21H8, September 16, 1999 Condition Report CR-ANO-1-1999-00352, ANO-1 25 Year Tendon Surveillance on Tendon 21H8, September 21, 1999

4.0 RESULTS OF THE AUDIT During the audit, the NRC staff did not make any regulatory decisions regarding the alternative request under the NRC staffs review. At the conclusion of the audit, the NRC staff informed the licensee that it would not be issuing a request for additional information following the completion of its review of the audit portal information. The NRC staff noted that the audit facilitated the NRC staffs timely review of the request.

5.0 AUDIT PARTICIPANTS NRC Participants from the Office of Nuclear Reactor Regulation George Wang, Division of Engineering and External Hazards (DEX)/Structural, Civil, and Geotechnical Branch (ESEB)

Bryce Lehman, DEX/ESEB Thomas Wengert, Division of Operating Reactor Licensing (DORL)/Plant Licensing Branch IV (LPL4)

Licensee Participants Bob Clark, Entergy Licensing 6.0 EXIT BRIEFING On April 18, 2023, Thomas Wengert of the NRC informed Bob Clark of Entergy, via telephone, that the NRC staff did not need to review any additional calculations or evaluations and, accordingly, the audit was concluded.

ML23114A357 *by email NRR-106 OFFICE NRR/DORL/LPL4/PM* NRR/DORL/LPL4/LA* NRR/DEX/ESEB/BC*

NAME TWengert PBlechman ITseng DATE 4/25/2023 4/25/2023 5/2/2023 OFFICE NRR/DORL/LPL4/BC* NRR/DORL/LPL4/PM*

NAME JDixon-Herrity TWengert DATE 5/4/2023 5/10/2023