NL-23-0584, Preservice Inspection Program Owner'S Activity Report

Preservice Inspection Program Owner'S Activity Report

ML23191A881
Person / Time
Site:	Vogtle
Issue date:	07/10/2023
From:	Brown R Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NL-23-0584
Download: ML23191A881 (1)

Text

Southern Nuclear

~ Southern Nuclear Operating Company, Inc.

3535 Colonnade Parkway Birmingham , AL 35243 July 10, 2023 Docket No.: 52-025 NL-23-0584 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 Preservice Inspection Program Owner's Activity Report Ladies and Gentlemen:

The Vogtle Electric Generating Plant (VEGP) Unit 3 Owner's Activity Report (OAR-1) for the Preservice Inspection interval is provided as an Enclosure to this letter, in accordance with ASME Section XI, Article IWA-6200 and ASME Section XI Code Case N-532-5. The OAR-1 Report in the Enclosure includes Table 1, "Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service," which lists evaluations performed for continued service, and Table 2, "Abstract of Repair/ Replacement Activities Required for Continued Service," which lists repair/replacement activities.

This report is for the Preservice Inspection interval (0 th Interval, 0th Period, 1st Report).

This letter makes no regulatory commitments. This letter has been reviewed and determined not to contain security-related information.

If you have questions, please contact Amy Chamberlain at 205-992-6361.

Respectfully submitted, R. Keith Brown Regulatory Affairs Director Southern Nuclear Operating Company

Enclosure:

Preservice Inspection (PSI) Program Owner's Activity Report cc: Regional Administrator, Region II VPO Project Manager Senior Resident Inspector - VEGP 3&4 Document Services RTYPE: VND.LI.L00 File AR.01 .02.06

Vogtle Electric Generating Plant - Unit 3 Preservice Inspection Program Owner's Activity Report Enclosure to NL-23-0584 Preservice Inspection (PSI) Program Owner's Activity Report

Enclosure to NL-23-0584 PSI Program Owner's Activity Report FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number 3-0-0-1 (Unit 3, 0 th Interval, 0 th Period, 1s1 Report)

Plant Vogtle Nuclear Plant Unit No. 3 Commercial seNice date July 12. 2023 (anticipated) Refueling outage no. N/A (t applicable)

Current inspection inteNal Preservice lns12ection (PSI} [June 1, 2015 to Commercial Service Date]

( 1Sl, 2nd, 3rd, 4th. o ther)

Current inspection period N/A

( 1SI. 2nd. 3rd)

Edition and Addenda of Section XI applicable to the inspection plans: 2007 Edition through 2008 Addenda Date and revision of inspection plans: SV3-GW-GEl-100 Rev 2, Vogtle Electric Generating Plant Unit 3 Preservice Inspection Plan, approved February 2019. SV3-GW-GEl-300 Rev 0, Vogtle Electric Generating Plant Unit 3 IWE Preservice lns12ection Plan, ap12roved July 2020 . The PSI Plans list applicable Alternatives approved per 10 CFR 50.55a.

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans: Prior to the 1 0 CFR 52.103(g} finding, which occurred on August 3. 2022, all Repair/Replacement activities were performed per the construction codes ASME Code Section Ill. 1998 Edition through 2000 Addenda and 2001 Edition through 2002 Addenda. From the 10 CFR 52.103(g} finding until the anticipated Commercial O12eration date, July 12, 2023, all Repair/Re12lacement activities were performed per the Preservice Inspection Code, ASME Code Section XI, 2007 Edition through the 2008 Addenda.

Code Cases used for inspection and evaluation: N-532-5, N-613-1, N-619, N-639, N-648-1, N-648-2 ,

N-683, N-697, N-729-1 , N-729-4, N-799, and Pro(2osed Code Case N-XXX (BC12-51}.

(if aoollcabla includino cases modified bv Case N-532 and laler revisions}

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of Preservice lnS(28C1ion (PSI) conform to the requirements of Section XI. (refueling outage number}

Signed Kenneth Baitv k1~JJ..

Owner or Owner's Designee. Tille tJ./Jd: t,

(/

Enaineerina Director Date 1{-,l23 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford. CT. have inspected the items described in this Owner's Activity Report, and slate that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Steven S Eddy ......... ~~ ~ Commission NB-14657 / Al IS N IR NS lnspector*s Signai (National Board Number and Endorsement)

Date 7/7/2023 E-1

Enclosure to NL-23-0584 PSI Program Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service t:.xammauon Cateswry and Item Description Evaluation Description ts-J, ti~.,,

Item umber SV3-CMTA-CW-041 The three listed Core Make-Up (Upper Head Inlet Nozzle Weld Tanks A&B welds contained Buildup-to-Nozzle Barrel on Core flaws, found ultrasonically, that Makeup Tank A), exceeded the maximum sizes allowed by ASME Section XI ,

SV3-CMTB-CW-040 IWB-3000, for PSI.

(Lower Crown Outlet Nozzle Flaw evaluations were performed Weld Buildup-to-Nozzle Barrel on on the three welds per ASME Core Makeup Tank B), Section XI , IWB-3000, as allowed by ISi and found SV3-CMTB-CW-041 acceptable.

(Inlet Nozzle Weld Buildup-to- The flaw evaluations were Nozzle Barrel on Core Makeup performed per VEGP3&4-PSI -

Tank B). ALT-14R1 approved by NRC in ML20147A663.

These flaws are not considered to be service-induced but rather are residual from component fabrication.

ts-u -.::::: 3-PXS-PL-V123A downstream Following a piping flange bolted flange/gasket leak replacement, a very small leak

( ~ 1 drop per 4 minutes) was evaluated for continued service in consultant (MPR) letter 1308-0058-LTR-001 Rev O "ASME Section X IWA-5251 Evaluation for Vogtle Unit 3 PXS-V123A" which concluded the very small leak is acceptable. The consultant letter was used as the basis for Technical Evaluation 1123676. This leak is also acceptable per plant Technical Specifications addressing RCS leakaoe limits.

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Enclosure to NL-23-0584 PSI Program Owner's Activity Report Table 2 Abstract of Repair/ Replacement Activities Required for Continued Service Code Item Description Description of Work Class ue to ea at ange, Downstream Flange replaced flange, pipe R3 stub and gasl<et to stop small leak, as a result of finding scratches on tfle flange surface.

However, leak of several drops per min remained after repair.

Leak evaluated to allow continued operation per TE 1123676.

Seal Assembly that is also part of the pressure boundary of the bonnet. Leaking borated water.

nstrumente manway 59 installed on SG#2 primary manway; 12 studs did not pass the VT-1 inspection. 20 new studs and nuts installed.

evIew o SNC1443159 of installed studs/nuts on Instrumented SG#2 primary manway, with VT-1 performed did not match installation in field. Six Studs and Nuts pulled and replaced with new that had VT-1 record.

1ssIng support strap replaced with new.

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Enclosure to NL-23-0584 PSI Program Owner's Activity Report 1ssmg support strap replaced with new.

trut rep ace w en nut could not be R1 removed.

3- trut rep ace w en 3 nut could not be removed.

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