View source for BSEP 17-0044, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 22

{{Adams
| number = ML17151A217
| issue date = 05/25/2017
| title = Inservice Inspection Program Owner'S Activity Report for Refueling Outage 22
| author name = Wooten B
| author affiliation = Duke Energy Progress, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000324
| license number = DPR-062
| contact person = 
| case reference number = BSEP 17-0044
| document type = Inservice/Preservice Inspection and Test Report, Letter type:BSEP
| page count = 6
}}

=Text=
{{#Wiki_filter:Brunswick Nuclear Plant
(_~ DUKE                                                                                         P.O. Box 10429 ENERGY                                                                                 Southport, NC 28461 May 25, 2017 Serial: BSEP 17-0044 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 1 Refueling Outage 22 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 22 (i.e., designated as B223R1) for the third inspection period of the fourth inservice inspection interval.
No regulatory commitments are contained in this letter.
Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.
Sincerely,
   ~- & #/~
Bryan B. Wooten Director - Organizational Effectiveness Brunswick Steam Electric Plant

U.S. Nuclear Regulatory Commission Page 2 of 2 WRM/wrm

==Enclosure:==
Form OAR-1 Owner's Activity Report cc (with enclosure):
U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. Cliff Dautrich, Bureau Chief North Carolina Department of Labor Boiler Safety Bureau 1101 Mail Service Center Raleigh, NC 27699-1101

Form OAR-1 OWNER'S ACTIVITY REPORT Plant: _ _ _ _ __,;;B"'"'r=u"'""n=sw..;..;..;.;ic=k;:....S;;;;..t=e=a;.;..:;m..:....;;::E:.:....;:le:;..;:c=tr~ic;:;....:_P..:..;:la=n=t_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Unit No.:
            -------      2            Com mercia I Service Date: ----'N_..o. . .v. . .e. . m                                              . .........
be....r_.1=9""'"7__5_ _ Refueling Outage No.:_--=B..-2....2...-3.....R......1...____
Current Inspection lnterval:_ ____,;,F--o;;..u=rt;..;;.;...;h_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Current Inspection Period: _ _...;.T--h=ir=d'--'P'-e=r;..;.io=d;;;......;:o;..;..f...;:.th;..;.e;;;.....;.F...;:o;..;:u;:.:..rt~h..;....;.;.ln.;.;:t=e"-'rv;..;:a=I----------------
Edition and Addenda of Section XI applicable to the inspection plans: __2_0_0_1_e_d..........,iti.....o_n_w___.ith_2....0.....0.....3_a_d_d_e                                                      ......n_d
__a_ _ _ _ __
Date and Revision of Inspection Plans:                                   Fourth Interval Revision 4                                                                04/29/2016 Edition and Addenda of Section XI applicable to Repair/Replacement activities, if different than the Inspection Plans: None Code Cases used:           N-460. N-532-4. N-578-1, N-613-1, N-638-4. N-648-1, N-663. N-695. N-700 and N-740-2 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 _-=8=2=2=3"'-"'R:....:.1_ _ _ _ __
(Refueling Outage Number) 04 ~gooe~
conform to the requirements of Section XI.
Signed:
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 The Hartford Steam Boiler Inspection and Insurance Company have inspected the items described in this Owner's 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.
Date: -~--_-_.3_-_:z_o_li         _____
Page 1of4

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Item Description                Evaluation Description Number This indication was originally B-A I Bl.30           2B11-RPV-F documented during B220Rl on report Flange To Shell Weld UT-11-001 and NCR 453572, and evaluated by Structural Integrity on report# 1100470.401 Rev.2. Letters BSEP 11-0037 and BSEP 11-0093 were submitted to the NRC and was approved on Docket No. 50-324.
The first of three required successive examinations was performed during B221Rl. The examination revealed no change in the indication and was documented on report UT-13-005 and Evaluation Report EV-13-001.
The second of three required successive examinations was performed during B223Rl. The examination revealed no change in the indication and was documented on report UT-17-004 and Evaluation Report EV-17-004.
The third of three successive examinations is scheduled to be performed during B224Rl.
During Scheduled B223Rl Inspection Augmented/ BWRVIP-75 Cat. D     2B11N9-RPV-FW2CRD52 a Ultrasonic Circumferential ID RX Vessel Nozzle N9 To Cap (DM) connected flaw was detected. It was documented on BNP report VEN                                                                 032 and AREVA report BNP2-DM-2017-9. NCR-2112313 was generated and a full structural weld overlay was performed per EC-408144 using Code Case N-740-2 under work order 20151889 task 06.
The Component BWRVIP status has been changed from Category "D" to Category "E" and is scheduled to be re-examined during the next refueling outage (B224Rl).
Page 2of4

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 1 (Cont.)
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Item Description              Evaluation Description Number This indication was originally C-F-2 / CS.51           2E1189-18-SWA documented during B222Rl under Elbow To Pipe Weld report UT-15-009 and evaluation report EV-15-005. NCR 736095 was generated and a evaluation was performed by Structural Integrity on report# 1500325.301 and reviewed on BNP calculation SA-Ell-937 for continued service. The required successive examination was performed during B223Rl.
The examination revealed no change in the indication and was documented on report UT-17-049 and Evaluation Report EV-17-005. The component will revert back to the original schedule per IWC-2420 ( c ).
During Scheduled VT-3 examination of F-A I Fl.lOC           2-B32-HB9 Constant Spring support 2-B32-HB9, Constant Support it was determined that the cold setting did not meet the design specifications.
NCR 2111249 was generated to document findings.
EC-408294 Evaluation was performed to evaluate the acceptability of the as found settings.
The examination documented an as found setting at increment 3.0 with a design cold position setting at increment 3.5.
Design review of the current cold position setting found it provides adequate travel to support pipe movement and is therefore acceptable.
The Evaluation concludes that the change does not adversely alter the Design Function of an SSC, as defined in NEI 96-07, Revision 1, Section 3.3.
Page 3of4

FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Date    Repair/Replacement Code Class  Item Description           Description of Work Completed     Plan Number N9 Nozzle to Cap Weld 1          2-Bll-RPV-N9                                          4/11/2017      20151889-06 Full Structural Weld Overlay Reset Spring Hanger to Design 1           2-E51-3VH48                                          4/10/2017     20158901-01 Specifications Replace 2B Recirc Pump 1           2-B32-C001B                                          3/24/2017      13527754-04 Mechanical Pressure Seal and Housing 2           2-E21-F012B        Replace Safety Relief Valve Disc  8/15/2016      13303089-01 Repair broken check valve hinge 2           2-E21-F003B                                          9/15/2016      13331030-01 support fastener 2           2-E21-6SS41       Replace Snubber Due To Leakage      4/6/2017      20155425-01 Replace HCU Nitrogen I Water 2       2-C12-125 (10-19)                                        4/17/2017      20158909-01 Accumulator 3           2-SW-PV-140         Replace Valve 2-SW-PV-140        3/19/2016      11610231-09 3        2-SW-103-24-157        Replace Service Water Spool       4/8/2017      11823223-01 Weld Repair Eroded Areas on Cooler 3         2-VA-2B-FCU-RB                                          4/4/2017      20106593-19 Cover 3             2-SW-V97            Replace Valve 2-SW-V97          4/4/2017      20155846-01 3           2-Ell-FOOSB              Replace Valve Disc           4/11/2017     20155852-01 Page 4of4}}