RA-19-0256, Submittal of Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24

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

ML19171A141
Person / Time
Site:	Brunswick
Issue date:	06/20/2019
From:	Pierce J Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-19-0256
Download: ML19171A141 (6)

Text

~., DUKE ENERGY Serial: RA-19-0256 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 Brunsw i ck Nuclear Plant P.O. Box 10429 Southport, NC 28461 lnservice Inspection Program Owner's Activity Report for Unit 2 Refueling Outage 24 Ladies and Gentlemen:

Duke Energy Progress, LLC, 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 24 (i.e., designated as B2R24 or B224R1) 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.

Jer Pierce Manager -Nuclear Support Services Brunswick Steam Electric Plant SBY/sby

Form OAR-1 OWNER'S ACTIVITY REPORT Report Number: ----=B"-N""P~-P_.,.M'--'5=--=0=0~2

=B=2R~2~4;...0=A~R~-..;1

__ _ Plant: Brunswick Steam Electric Plant, P.O. Box 10429. Southport, North Carolina.

28461 Unit No.: __ 2____ Commercial Service Date: November 1975 ___ Refueling Outage No.: B224Rl Current Inspection Interval:

_...,_F"'""'ift"'"h~ln,._,te"'rv'-=-a'--1

---

***-----

Current Inspection Period: --~Fi~rs~t~P-=e~ri=o=d

____________

_ Edition and Addenda of Section XI applicable to the inspection plans: ASME Sec. XI, 2007 Edition w/ 2008 Addenda Date and Revision of Inspection Plans: BNP-PM5-002 BSEP lnservice Inspection Plan, Revision O (Date: 05/10/2018)

BNP-PM5-003 BSEP Interval Inspection Schedule, Revision O {Date: 05/10/2018)

BNP-PM5-005 BSEP Pressure Test Plan & Schedule.

Revision 1 {Date:10/2/2018)

Edition and Addenda of Section XI applicable to Repair/Replacement activities, if different than the Inspection Plans: ___ _ Same as above Code Cases used for inspection and evaluation:

N-432-1, N-460. N-504-4, N-513-3. N-516-3, N-526, N-552-1, N-561-2.

N-562-2. N-578, N-586-1. N-597-2, N-600. N-606-1, N-613-2, N-638-6. N-639, N-648-1, N-661-2, N-702, N-705, N716-1. N-730-1, N-733, N-735, N-740-2. N-74 7, N-771. N-795, N-798 and N-800 (if applicable, including 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 (cl the Repair/Replacement activities and evaluations supporting the completion of _ _..B..,2 .. 2._4,..R ... 1.._ ________ conform to the requirements of Section XI. [Refueling Outage Number) Signed: dtfdt!'!:!.~

Stephen L Mays, ISi Program Owner Date: &-4?~Zotj 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 OneCIS Insurance Company Lynn, MA 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 the activities represented by this report in accordance with the requirements of Section XI. By signing this certificate neither the Inspector no his employer makes any warranty, expressed or implied, concerning the activities described in the Repair/Replacement Plan. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

_..::e§;@::;__....,.__.:.....d

_ _._~"-"------------

Commissions N~tt:\~93o

>Jltl~c.v A~lL-Inspector's Signature National Board, State, Province, and Endorsements Date: ~oG-=-.-(~\

t>-+-/ _to~l.0 __

TABLE 1 -B2R24 Refueling Outage (CORRECTION)

ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category Item Description Evaluation Description and Item Number E-A / El.11 2-DW-ML-4 General visual and VT-1 examination during the E-C/ E4.11 Drywall Shell B223R1 (March 2017) identified a relevant ELE 34' -10" to 53' -7" condition on the wall of the containment vessel near azimuth 265 degrees and elevation 42 feet (ref.: NCR 02111138 w/ IDO). The area of distress is approximately 3/32 inches deep (3/8-inch wide x 3-inch long). The material distress appears to be from removal of welded attachment jigs during construction.

An engineering evaluation (ref.: ORIP-1013) concluded that the remaining wall thickness 0.21875 inches is sufficient for continued service without corrective action. A successive VT-1 reexamination during the B224R1 (March 2019) revealed no change from the previous data for the relevant condition.

In accordance with IWE-2420(d), this component examination schedule will return to the original schedule for successive inspections.

NOTE: Evaluation of this IWE General Visual/VT-1 relevant condition was inadvertently omitted from the B223R1 (March 2017) OAR-1 report. F-A / F1.20B 2-E21-2PG3 VT-3 examination identified relevant indications Piping Support documented on report VT-19-008

/ EV-19-001 and Welded Restraint NCR 02261288.

A 0.25-inch deep area (3.5 x 1.5 inches) and a 0.125-inch area (1.5 x 1.5 inches) appear to be legacy defects in the base embedded plate of this support restraint.

An engineering evaluation was performed and concluded that the remaining design margin is sufficient for the support to perform its intended design function without corrective action. In accordance with IWF-2410(b), this component is scheduled for reexamination during the subsequent inspection period (March 2023).

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description of Work Date Repair /Replacement Class Description Completed Plan Number 1 2-B21-F013E Replaced SRV Pilot Assembly and Main Body 12/11/2018 20183403-01&06 due to seat leakage. SRV was replaced during a forced shutdown in response to elevated drywell floor drain flow (NCR 02214698).

1 2-B21-F013L Replaced SRV Pilot Assembly and Main Body 5/14/2019 20320003-01&02 due to failure during testing during B224Rl (NCR 02265786).

1 2-B21-F013C Replaced SRV Pilot Assembly due to elevated 5/13/2019 20320470-01 tailpipe temperatures during startup from B224Rl (NCR 02265802).

2 2-E51-F001 Replace 2-E51-F001 due to excessive internal 4/15/2019 11923619-01 bore found outside of tolerances during inspection (EC 414018). 2 2-B21-F037E Repaired vacuum breaker valve due to 11/1/2018 20259958-01 leakage by the seat identified during forced unit shutdown (NCR 02211357).

3 2-SW-2B-NUC-Replaced pump upper shaft, coupling, and 5/16/2019 13331215-01 PMP packing box due to erosion found on the pump shaft during maintenance activity.

3 2-Ell-F002A Repaired valve to prevent leakage from cover 4/17/2019 20071454-01 plate causing corrosion at bolted connection.

3 2-VA-2A-FCU-RB Base metal weld repair of eroded areas four 5/14/2019 20255171-20 locations on Header Box and Tube Plate of the RHR HX/ HPCI PMP Room Cooling Unit 2A. 3 2-SW-127-6-046 Repair Weld at 6x10 inch weld-a-let 5/14/2019 20315544-06 connection to line 2-SW-173-20-157 of the Service Water System 3 2-SW-100 Weld repair to localized 3x9 inch area on the 5/14/2019 20317128-01 157 interior of piping on line 2-SW-100-30-157 of the Service Water System