RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24

Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24

ML22160A429
Person / Time
Site:	Brunswick
Issue date:	06/09/2022
From:	Dewire M Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-22-0165
Download: ML22160A429 (6)

Text

Brunswick Nuclear Plant

~ ~ DUKE 8470 River Rd SE

~ ENERGY Southport, NC 28461 June 9, 2022 Serial: RA-22-0165 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 1 Renewed Facility Operating License No. DPR-71 Docket No. 50-325 lnservice Inspection Program Owner's Activity Report for Unit 1 Refueling Outage 24 Ladies and Gentlemen:

Duke Energy Progress, LLC (Duke Energy), is enclosing an American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Form OAR-1 Owner's Activity Report, for the Brunswick Steam Electric Plant (BSEP), Unit No. 1. The report covers inspection activities performed during Brunswick Unit 1 Refueling Outage 24 (i.e., B1 R24) for the first inspection period of the fifth inservice inspection interval.

No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Stephen Yodersmith, Brunswick Regulatory Affairs, at (910) 832-2568.

Si~ _ _ _ r Mark R. DeWire Manager - Nuclear Support Services Brunswick Steam Electric Plant SBY/sby

Enclosure:

Form OAR-1 Owner's Activity Report

U.S. Nuclear Regulatory Commission Page 2 of 2 cc (with Enclosure):

Ms. Laura Dudes, NRC Regional Administrator, Region II Mr. Luke Haeg, NRC Project Manager Mr. Gale Smith, NRC Senior Resident Inspector Chair - North Carolina Utilities Commission Mr. Donald Kinney, North Carolina Department of Labor, Boiler Safety Bureau Chief

Enclosure RA-22-0165 Form OAR-1 Owners Activity Report

CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number B1R24 OAR-1 Form Plant Brunswick Steam Electric Plant (BSEP)

Unit No. 1 Commercial service date March 18, 1977 Refueling Outage No. B1R24 (if applicable)

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

Current inspection period First Period / Second Refueling Outage (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition with 2008 Addenda BNP-PM5-002, Revision 2, Revision Date: February 10, 2022 Date and revision of inspection plans BNP-PM5-005, Revision 2, Revision Date: September 30, 2020 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans None N-432-1, N-513-3, N-516-3, N-526, N-532-5, N-552-1, N-561-2, 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, Code Cases used for inspection N-661-2, N-702, N-705, N-716-1, N-730-1, N-733, N-735, N-740-2, N-747, and evaluation: N-765, N-771, N-786-1, N-789, N-795, N-798, N-800, and N-845 (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 B1R24 conform to the requirements of Section XI.

(refueling outage number)

SLM4105 (137506) dc=com, dc=duke-energy, dc=ent, dc=nam, ou=Accounts, ou=Personal, ou=PNTransitional, cn=SLM4105 (137506), email=Steve.Mays@duke-energy.com Signed 2022.06.02 10:31:28 -04'00' Date 6/2/2022 Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of North Carolina and employed by Bureau Veritas Inspection and have Insurance Company 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.

Digitally signed by Paul P Arnett Paul P Arnett Date: 2022.06.07 08:17:13 -04'00' Commissions NB 13399 B, I, N, NS, NSI, R Inspectors Signature National Board, State, Province, and Endorsements 6/7/2022 Date Page 1 of 3

CASE N-532-5 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 Pipe Extension (DM) (March 2018). No new weld flaws were identified during this BWRVIP-75-A successive examination. Engineering evaluated the weld flaw and Category F 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 in BWRVIP-75-A, Category F.

E-A / E1.12 1-SC-ML-B5-BWL Visual (VT-3) examination identified eighty-eight (88) spot corrosive pit indications ranging in size from 1/8 to 1 diameter and with substrate pit depth exceeding 37 mils (10% acceptance criteria).

A deepest single corrosive pit indication was found to be 126.3 mils actual metal loss and 1/4 diameter. Evaluation determined that the required 0.025 minimum uniform thickness was not exceeded and found the discovered condition is acceptable for continued service without code repair. Liner protective coating was restored to arrest future corrosive degradation. (ref. EC EVAL 420842, Rev. 0)

E-A / E1.12 1-SC-ML-B6-BWL Visual (VT-3) examination identified seventy-two (72) spot corrosive pit indications ranging in size from 1/8 to 1 diameter and with substrate pit depth exceeding 37 mils (10% acceptance criteria).

A deepest single corrosive pit indication was found to be 75 mils actual metal loss and 1/4 diameter. Evaluation determined that the required 0.025 minimum uniform thickness was not exceeded and found the discovered condition is acceptable for continued service without code repair. Liner protective coating was restored to arrest future corrosive degradation. (ref. EC EVAL 420842, Rev. 0)

E-A / E1.12 1-SC-ML-B7-BWL Visual (VT-3) examination identified two-hundred twenty-five (225) spot corrosive pit indications ranging in size from 1/8 to 1 diameter and with substrate pit depth exceeding 37 mils (10%

acceptance criteria). A deepest single corrosive pit indication was found to be 118.7 mils actual metal loss and 1/4 diameter.

Evaluation determined that the required 0.025 minimum uniform thickness was not exceeded and found the discovered condition acceptable for continued service without code repair. Liner protective coating was restored to arrest future corrosive degradation. (ref. EC EVAL 420842, Rev. 0)

E-A / E1.12 1-SC-ML-B8-BWL Visual (VT-3) examination identified one-hundred fifty-three (153) spot corrosive pit indications ranging in size from 1/8 to 3/4 diameter and with substrate pit depth exceeded 37 mils (10%

acceptance criteria). A deepest single corrosive pit indication was found to be 100.7 mils actual metal loss and 1/8 diameter.

Evaluation determined that the required 0.025 minimum uniform thickness was not exceeded and found the discovered condition acceptable for continued service without code repair. Liner Page 2 of 3

CASE N-532-5 protective coating was restored to arrest future corrosive degradation (ref. EC EVAL 420842, Rev. 0)

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

Code Item Date Replacement Class Description Description of Work Completed Plan Number Welded Eye Rod on Pipe Support 1 1-B21-21VH123 discovered bent and replaced during 4/1/2022 12116806-09 scheduled maintenance activity 1-VA-1A-FCU- Weld Repair of Closure Head on RHR HX 3 3/23/2022 20482654-17 RB / HPCI Pump Room Cooler Unit Replaced support flange bolting on the 1-RB1-LNR-EL- SRV t-quencher discharge header that MC 3/22/2022 20482162-40 14-01 was discovered broken during torus containment liner underwater inspection Page 3 of 3