NL-19-0307, Response to NRC Request for Additional Information on Relief Request FNP-ISI-RR-02

Response to NRC Request for Additional Information on Relief Request FNP-ISI-RR-02

ML19086A215
Person / Time
Site:	Farley
Issue date:	03/27/2019
From:	Gayheart C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-19-0307
Download: ML19086A215 (6)

Text

~ Southern Nuclear Cheryl A. Gayheart 3535 Colonnade Parkway Regulatory Affairs Director Birmingham, AL 35243 205 992 5316 tel 205 992 7601 fax cagayhea@ southernco.com MAR 2 7 2019 Docket Nos.: 50-348 NL-19-0307 50-364 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant- Unit 1 and 2 Relief Request FNP-ISI-RR-02 SNC Response to NRC Request for Additional Information Ladies and Gentlemen:

By letter dated November 30, 2018 (Agencywide Documents Access and Management System Accession Number ML18334A032), Southern Nuclear Operating Company (SNC) requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI. This relief request, FNP-ISI-RR-02, proposed an alternate examination coverage of certain welds during the fourth 10-year inservice inspection program interval for Farley Nuclear Plant Units 1 and 2.

By email dated February 25, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff notified SNC that additional information is needed for the staff to complete their review. The enclosure to this letter provides the SNC response to the NRC request for additional information (RAI).

This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.

Respectfully submitted, Cheryl Regulat ffairs Director Southern Nuclear Operating Company CAG/ndj/sm

Enclosure:

SNC Response to NRC Request for Additional Information (RAI)- Relief Request FNP-ISI-RR-02

U.S. Nuclear Regulatory Commission NL 0307 Page 2 cc: Regional Administrator, Region II NRR Project Manager- Farley Nuclear Plant Senior Resident Inspector- Farley Nuclear Plant RTYPE: CFA04.054

Joseph M. Farley Nuclear Plant- Unit 1 and 2 Relief Request FNP-ISI-RR-02 SNC Response to NRC Request for Additional Information Enclosure SNC Response to NRC Request for Additional Information (RAI)

Relief Request FNP-ISI-RR-02

Enclosure to NL-19-0307 SNC Response to NRC Request for Additional Information (RAI)

NRC RA11 (a) Discuss the materials of construction (e.g., ASME material specifications) of the subject welds and adjacent components (nozzles and pipes) in Tables RR-02.1 and RR-02.2 of the relief request.

(b) If Alloy 82/182 filler metal was used, discuss whether the subject welds have been mitigated to minimize the potential for primary water stress corrosion cracking.

(c) If stainless steel filler metal was used, discuss how the examination coverage of the subject welds was calculated and how the examination was conducted because claiming coverage for the volume on the opposite side of the weld centerline (far-side) requires meeting the 10 CFR 50.55a(b)(2)(xv)(A)(2) far-side UT qualifications, which has not been demonstrated in any qualification attempts to date.

SNC Response to RAI 1 (a)

Component ID Com_Q_onent Material Reference ALA 1-21 00-9 Head SA-533, Gr. A, CL. 2. U199396 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14<1l Nozzle SA-508, Cl2 U199396 ALA1-2100-10 Head SA-533, Gr. A, CL. 2. U199396 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14<1l Nozzle SA-508, Cl2 U199396 ALA 1-2100-11 Head SA-533, Gr. A, CL. 2. U199396 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14<1l Nozzle SA-508, Cl2 U199396 ALA1-21 00-12 Head SA-533, Gr. A, CL. 2. U199396 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 T_ype EH 14<1l Nozzle SA-508, Cl2 U199396 ALA 1-2100-13 Head SA-533, Gr. A, CL. 2. U199396 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14<1l Nozzle SA-508, Cl2 U199396 E1-1

Enclosure to NL-19-0307 SNC Response to NRC Request for Additional Information (RAI)

Component ID Component Material Reference ALA 1-2100-14 Head SA-533, Gr. A, CL. 2. U199396 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14(1l Nozzle SA-508, Cl2 U199396 APR 1-21 00-9 Head SA-533, Gr. A, CL. 2. U-206276 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14(1l Nozzle SA-508, Cl2 U-206276 APR1-2100-10 Head SA-533, Gr. A, CL. 2. U-206276 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14(1l Nozzle SA-508, Cl2 U-206276 APR1-21 00-11 Head SA-533, Gr. A, CL. 2. U-206276 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14(1l Nozzle SA-508, Cl2 U-206276 APR1-21 00-12 Head SA-533, Gr. A, CL. 2. U-206276 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14(1l Nozzle SA-508, Cl2 U-206276 APR1-2100-13 Head SA-533, Gr. A, CL. 2. U-206276 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14(1l Nozzle SA-508, Cl2 U-206276 APR1-2100-14 Head SA-533, Gr. A, CL. 2. U-206276 Weld Manual- SFA 5.5 82148RR Type E 9018-M Automated- SFA 5.17 Type EH 14(1l Nozzle SA-508, Cl2 U-206276 (1)

Per Westinghouse, the weld1ng process spec1f1cat1on 82148RR for the pressunzer 1nd1cated SFA 5.5 Type E 9018-M for manual welding and SFA 5.17 Type EH 14 for automated.

(b) Filler metal Alloy 82/182 was not used as indicated in the above table.

(c) Stainless steel filler metal was not used as indicated in the above table.

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Enclosure to NL-19-0307 SNC Response to NRC Request for Additional Information (RAI)

NRC RAJ2 Discuss other measures that could monitor structural integrity of the subject welds, given that certain volume of the subject welds could not be examined.

SNC Response to RAJ 2 The Class 1 pressure testing is performed per IWB-5000 during startup from refueling outages. A VT-2 examination of the Pressurizer inside the Pressurizer cubicle is performed every outage in conjunction with the performance of the Reactor Coolant System (RCS) Leak Test. In accordance with the Boric Acid Corrosion Control Program, Operations and Engineering personnel perform boric acid walkdowns inside containment early in the outage to identify potential leakage areas. Online monitoring and trending is performed on the identified and unidentified leakage in the RCS system per Technical Specification Surveillance Requirement 3.4.13.1.

NRC RAJ3 Section 2 of the relief request states that " ... FNP, Units 1 and 2 examinations were performed in accordance with the requirements of ASME,Section XI, Article 4 of Section V ... " Clarify whether the reference should be the ASME Code,Section V, Article 4".

SNC Response to RAJ 3 The reference should have stated the ASME Code,Section V, Article 4".

NRC RAJ4 Section 3 of the relief request states that:" ... The extent of examination requirement for Examination Category 8-D, Item Number 83.110, per Table IW8-2500-1, requires a volumetric examination of essentially 100% of the weld length ... " The NRC staff understands that Table IW8-2500-1 requires a volumetric examination of 100%, not essentially 100%, coverage of the weld length. The essentially 100% examination coverage is permitted only by ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1." Please clarify the above examination coverage statement.

SNC Response to RAJ 4 The statement should have read, The extent of examination requirement for Examination Category 8-D, Item Number 83.110, per Table IW8-2500-1 and in accordance with NRC approved ASME Code Case N-460, requires a volumetric examination of essentially 100% of the weld length."

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