RA-23-0045, Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 26

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Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 26
ML23179A173
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 06/28/2023
From: Dewire M
Duke Energy Progress
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
RA-23-0045
Download: ML23179A173 (1)


Text

Brunswick Nuclear Plant ef,.-, DUKE 8470 River Rd SE

~ ENERGY Southport, NC 28461 June 28, 2023 Serial: RA-23-0045 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit No. 2 Renewed Facility Operating License No. DPR-62 Docket No. 50-324 lnservice Inspection Program Owner's Activity Report for Unit 2 Refueling Outage 26 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. 2. The report covers inspection activities performed during Brunswick Unit 2 Refueling Outage 26 (i.e., B2R26) for the second 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.

Manager - Nuclear Support Services Brunswick Steam Electric Plant

Enclosure:

Form OAR-1 Owner's Activity Report

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

Ms. Laura Dudes, 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, ANII, Bureau Veritas Inspection and Insurance Company

Enclosure RA-23-0045 Form OAR-1 Owners Activity Report

CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number B2R26 OAR-1 Form Plant Brunswick Steam Electric Plant (BSEP)

Unit No. 2 Commercial service date November 1975 Refueling Outage No. B2R26 (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 Second Period / First Refueling Outage (1st, 2nd, 3rd) 2007 Edition with 2008 Addenda; 2017 Edition is applicable for IWA-4340, IWA-4540(b), IWA-5120, IWA-5213, IWA-5241, IWA-Edition and Addenda of Section XI applicable 5242, and IWA-5250 in accordance with three RIS Letters; Ref.

to the inspection plans ML21029A335, ML21113A013 and ML20300A206.

BNP-PM5-002, Revision 3, Revision Date: December 5, 2022 Date and revision of inspection plans BNP-PM5-003, Revision 3, Revision Date: December 5, 2022 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans: 2017 Edition 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; Ref. ML21029A335, ML21113A013 and ML20300A206 Code Cases used for N-432-1, N-513-3, N-516-5, N-526, N-532-5, N-552-1, N-561-2, N-516-3, N-562-2, inspection and evaluation: 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-747, N-765, N-771, N-786-1, N-789, N-789-3, N-795, N-831-1, N-845, N-858, and N-864 (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 B2R26 conform to the requirements of Section XI.

(refueling outage number)

Signed Date 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 Insurance Company of Lynn, PA 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.

Commissions NB 13399 B, I, N, NS, NSI, R, NC Inspectors Signature National Board, State, Province, and Endorsements Date 6/26/2023 Page 1 of 2

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 E-A / E1.12 2-SC-ML-B9-BWL Visual (VT-3) examination identified one (1) spot corrosive SC Torus Liner pit indication with measured depth exceeded 37 mils (10%

Submerged nominal wall thickness). The corrosive pit measured depth Surface was 58.3 mils. 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 (NCR 02461741).

F-A / F1.10C 2-B32-HA8 During examination, the discovered as-found conditions were Constant Load 1) Loose / back off jam nut on hanger rod to clevis hanger Spring Support attached 2) Hanger Rod with thread damage approximately 2 inches above clevis hanger; and 3) Constant load spring travel stop device installed on one side but not engaged to restrict spring movement. Evaluation determined as-found conditions was acceptable for continued service. Action created to return support to designed condition (NCR 02460421 / WO 20585872).

F-A / F1.10B 2-B21-PS3566 During examination, discovered four (4) support steel nuts Pipe Restraint exhibited lack of thread engagement by approximately 2 threads below flush. Evaluation determined as-found conditions was acceptable for continued service without corrective measures. (NCR 02460374).

F-A / F1.20C 2-E11-46VH5 During examination, the discovered as-found conditions were Spring Hanger 1) Upper pipe clamp bolting: Bolting free spins inside clamp (nut tight to bolt) and 2) Lower Pipe Clamp Bolting: Nut engagement found two threads below flush. Evaluation determined as-found conditions was acceptable for continued service. Action taken to return support to designed condition (NCR 02460170 / WO 20502489)

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

Code Date Replacement Class Item Description Description of Work Completed Plan Number Performed weld repair of damage to 2-E11-F050A valve interval surface cause by steam 1 2/20/2023 20517989-36 Isolation Valve leak (leak repaired) at the body-to-bonnet bolted connection.

2-VA-2B-FCU-RB Weld Repair on internal surfaces and 3 ECCS Room divider plates of closure head on RHR 2/25/2023 20535698-20 Cooler HX / HPCI Pump Room Cooler Unit Page 2 of 2