RA-24-0164, Inservicee Inspection Program Owners Activity Report Refueling Outage 25

Inservicee Inspection Program Owners Activity Report Refueling Outage 25

ML24171A007
Person / Time
Site:	Brunswick
Issue date:	06/19/2024
From:	Dewire M Duke Energy Progress
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
RA-24-0164
Download: ML24171A007 (1)

Text

U.S. Nuclear Regulatory Commission Page 2 of 2

Enclosure:

Form OAR-1 Owners Activity Report

cc (with Enclosure):

Ms. Laura Dudes, NRC Regional Administrator, Region II Mr. Luke Haeg, NRC Project Manager Mr. Gale Smith, NRC Senior Resident Inspector

Mr. Donald Kinney, North Carolina Department of Labor, Boiler Safety Bureau Chief Mr. Paul Arnett, Authorized Nuclear Inservice Inspector (ANII)

Enclosure RA-24-0164

Form OAR-1 Owners Activity Report DUKE ENERGY

INSERVICE INSPECTION

SUMMARY

REPORT UNIT 1 BRUNSWICK NUCLEAR PLANT 2024 REFUELING OUTAGE - B1R25

5th INTERVAL - 2nd PERIOD - 1st REFUELING OUTAGE

Location: 8470 River Road SE, Southport, North Carolina, 28461

Commercial Service Date: March 18, 1977

NRC Docket No. 50-325

Owner: Duke Energy Charlotte, NC

Revision 0

Originated: Stephen L Mays (PRINT NAME) (SIGNATURE & DATE)(SIGNATURE& DDATED)

Checked By: Angela Staller (PRINT NAME) (SIGNATURE & DATE)(SIGNATURE&

MAP9681 Digitally signed by MAP9681 (102140)

(102140) Date: 2024.06.13 08:53:11 Approved By: Mark Pyne-04'00' (PRINT NAME) (SIGNATURE & DATE)

ASME BPVC.XI.1-2019

FORM OAR-1 OWNER'S ACTIVITY REPORT

Report Number B1R25 OAR-1 Form

Plant Brunswick Steam Electric Plant (BSEP)

Unit No. 1 Commercial service date March 18, 1977 Refueling Outage No. B1R25 (if applicable)

Fifth Interval - Inservice Inspection and Pressure Test Plan Applicable inspection interval Third Interval - Containment (IWE/IWL) Inspection Plan (1st, 2nd, 3rd, 4th, other)

Applicable inspection period Second Period (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the 2007 Edition with 2008 Addenda; and inspection plans 2017 & 2019 Edition (see Attachment 1)

Date and revision of inspection plans See Attachment 1

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans: same as the above inspection plans N-432-1, N-513-3, N-516-5, N-526, N-552-1, N-561-2, N-561-3, N-562-2, N-586-1, N-597-2, N-600, N-606-1, N-613-2, N-639, N-648-1, N-648-2, N-661-2, N-702, N-705, N-711-1, N-716-1, N-730-1, N-733, N-735, N-740-2, N-747, N-765, Code Cases used for N-771, N-786-1, N-789, N-789-3, N-795, N-798, N-800, N-831-1, N-845, N-858, inspection and evaluation: N-864, and N885.

(if applicable, include cases modified by Case N-532 and later 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 B1R25 conform to the requirements of Section XI.

(refueling outage number)(refueling outage number)

Signed Date Stephen L Mays Owner or Owners Designee, TitleOwner or Owners D

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 Bureau Veritas Inspection and Insurance Company of Lynn, Maryland have inspected the items described in this Owners Activity Report, and state 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.his inspection.

Commissions NB 13399 B, I, N, NS, NSI, R, NC Inspectors Signature National Board, State, Province, and EndorsementsInspectors Signature

Date 6/17/2024

Page 1 of 4 ASME BPVC.XI.1-2019

Attachment 1 Brunswick Unit 1 Refueling Outage 25 Inservice Inspection Report

The Brunswick Steam Electric Plant, Unit 1, Fifth Ten-Year Interval Inservice Inspection (ISI) Plan and Third Ten-Year Containment Inservice Inspection (CISI) Plan complies with 10CFR50.55a(g),

which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2007 Edition through 2008 Addenda. The 2017 Edition of Section XI is applicable for IWA-4340, IWA-4540(b), IWA-5120, IWA-5213, IWA-5241, IWA-5242 and IWA-5250 in accordance with three RIS letters, ADAMS Accession Numbers ML21113A013, ML20300A206 and ML21029A335. The 2019 Edition of ASME Section XI is applicable for IWA-6230(b) in accordance with RIS Letter, ADAMS Accession Number ML23118A0.

Refueling Outage 25 (B1R25) is the only refueling outage of the second period in the fifth inspection interval for the Inservice Inspection and Pressure Testing programs and the only refueling outage of the second period in the third inspection interval of the Containment ISI program. See the table below for the dates and revisions of the inservice inspection plans.

Document Title Document Number Date of Issue and Revision UNITS 1 & 2 FIFTH INTERVAL INSERVICE BNP-PM5-002, Revision 3 December 6, 2022 INSPECTION PLAN UNIT 1 & 2 FIFTH INTERVAL INSERVICE BNP-PM5-003, Revision 3 December 6, 2022 INSPECTION SCHEDULE FIFTH INTERVAL INSERVICE INSPECTION BNP-PM5-005, Revision 3 February 7, 2023 PRESSURE TEST PLAN AND SCHEDULE AUGMENTED INSERVICE INSPECITON (AISI) BNP-PM5-010, Revision 5 January 24, 2024 PLAN AND SCHEDULE 5TH INSERVICE INSPECTION INTERVAL

Page 2 of 4 ASME BPVC.XI.1-2019

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE

Examination Category and Item Number Item Description Evaluation Description R-A / R1.11/16 1B21N4D-5-SW2-3 Performed successive inspection of a previously identified weld Augment / E-9 Nozzle Safe End to flaw and evaluated as unchanged since its discovery in B1R22 BWRVIP-75-A Pipe Extension (DM) (March 2018). No new weld flaws were identified during this Category F successive examination. Engineering evaluated the weld flaw and determined that the current condition remains bounded by the existing flaw growth-rate analysis (ref.: EC 411734; SI Calc.

1800389.301). This weld is scheduled for successive examination during each refueling outage in accordance with regulatory commitment NRC GL 88-03 and BWRVIP-75-A, Category F.

E-A / E1.12 1-SC-ML-B1-BWL Visual (VT-3) examination identified one (1) spot corrosive pit Shell Plate 01-06 indication with substrate depth in the torus metallic liner exceeding acceptance criteria 84 mils (ref. BSEP 22-0308 Relief Request).

This single corrosive pit indication was measured 140 mils actual metal loss and 1/4 wide. Evaluation determined that the minimum required thickness by design was not exceeded and found the discovered condition acceptable for continued service without corrective measures. The metallic liner protective coating was restored to arrest continued corrosive degradation.

(ref. EC EVAL 423910 & 420060)

E-A / E1.12 1-SC-ML-B2-BWL Visual (VT-3) examination identified one (1) spot corrosive pit Shell Plate 02-05 indication with substrate depth in the torus metallic liner exceeding acceptance criteria 84 mils (ref. BSEP 22-0308 Relief Request).

This single corrosive pit indication was measured 93.7 mils actual metal loss and 1/4 wide. Evaluation determined that the minimum required thickness by design was not exceeded and found the discovered condition acceptable for continued service without corrective measures. The metallic liner protective coating was restored to arrest continued corrosive degradation.

(ref. EC EVAL 423910 & 420060)

E-A / E1.12 1-SC-ML-B3-BWL Visual (VT-3) examination identified two (2) spot corrosive pit Downcomer 03-1A indication in steam header downcomers exceeding acceptance Downcomer 03-2A criteria. One corrosive pit indication was measured 75.7 mils metal loss on a weld seam of the downcomer. A second corrosive pit indication was measured 28.7 mils metal loss on top of the downcomer clamp. Evaluation determined discovered condition acceptable for continued service without corrective measures. The protective coating was restored to arrest continued degradation.

(ref. EC EVAL 423910)

Page 3 of 4 ASME BPVC.XI.1-2019

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE

Repair /

Code Date Replacement Class Item Description Description of Work Completed Plan Number 3 1-SW-5-20-157 Repair NSW Header Thru-Wall Leak (WO 20560022 & NCR 244298) 2/25/2024 20562607-01 3 1-VA-1B-FCU-RB Weld Repair of Closure Head on RHR HX / HPCI Pump Room Cooler Unit 2/26/2024 20601321-17 3 1-SW-PS-2112-3 Replace support broken hold-down threaded rod and nuts 11/17/2023 20634543-01

Page 4 of 4