RA-19-0094, Refuel 31 (R231) Owner'S Activity Report, Fifth 10-Year Inservice Inspection Interval

Refuel 31 (R231) Owner'S Activity Report, Fifth 10-Year Inservice Inspection Interval

ML19052A066
Person / Time
Site:	Robinson
Issue date:	02/20/2019
From:	Ellis K Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-19-0094
Download: ML19052A066 (7)

Text

Kevin Elifs DUKE Manager - Nuclear Support Ser.;ices H. R Robinson Steam ENERGY@ Electric Plant Unit 2 Duke Energy 3581 West Entrance Road Hartsville, SC 29550 843.951.1329 Kevin. Ellis@duke-enargy.com 10 CFR 50.55a February 20, 2019 Serial: RA-19-0094 United States Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 H.B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 I Renewed License No. DPR-23

Subject:

Unit 2, Refuel 31 (R231) Owner's Activity Report, Fifth 10-Year lnservice Inspection Interval Ladies and Gentlemen:

In accordance with the requirements of 10 CFR 50.55a "Codes and Standards", Duke Energy Progress, LLC is providing as an enclosure to this letter, the Owner's Activity Report, Form OAR-1. This report has been prepared in accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 2007 Edition, 2008 Addenda, and is subject to the limitations and modifications of 10 CFR 50.55a(b)(2), with the exception of design and access provisions and preservice examination requirements. This report is further prepared in accordance with the requirements of ASME Code Case N-532-5 and covers inspection activities during Cycle 31 and Refueling Outage 31 (R231). R231 is the last of two outages of the second period in the fifth inspection interval and includes the Repair/

Replacement activities from June 13, 2017 to January 30, 2019.

Enclosure 1 contains the R231 Owner's Activity Report.

This submittal contains no regulatory commitments. Should you have any questions concerning this letter, or require additional information, please contact Art Zaremba, Manager - Nuclear Fleet Licensing, at 980-373-2062.

iv,~

Kevin Ellis Manager - Nuclear Support Services, H.B. Robinson Steam Electric Plant, Unit No. 2

U.S. Nuclear Regulatory Commission Page 2 Serial: RA-19-0094 Enclosure(s):

1. Ninety Day Owners Activity Report for Refueling Outage 31 WEK cc: (with enclosure)

Nate Jordan, NRC Project Manager, NRR Catherine Haney, NRC Regional Administrator, Region II NRC Resident Inspector, HBRSEP, Unit No. 2

ENCLOSURE 1 Ninety Day Owners Activity Report For Refueling Outage 31

Form OAR-1 OWNER'S ACTIVITY REPORT Summary The H.B. Robinson Nuclear Power Plant, Unit 2, Fifth Ten-Year Interval Inservice Inspection Plan was developed and prepared to meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, 2007 Edition with 2008 Addenda, and is subject to the limitations and modifications of 10 CFR 50.55a(b)(2), with the exception of design and access provisions and preservice examination requirements. This summary report is submitted pursuant to the reporting requirements of ASME Section XI as amended by ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission Section XI, Division 1." Contained within this summary report are the Owner's Activity Report, Form OAR-1, and Tables 1 and 2 of Code Case N-532-5 for H.B. Robinson Nuclear Power Plant during Cycle 31 and Refueling Outage 31 (R2R31). R2R31 is the last of two outages of the second period in the fifth inspection interval and includes the Repair/Replacement activities from June 13, 2017, to January 30, 2019.

Form OAR-1 OWNER'S ACTIVITY REPORT Report Number: -------'R..,,2=R=3"-'1"------_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Plant: _ _ _ _ _ _...,H=.B"-'.'--'Rc,;os:..:b""'i~ns:..:so"-'n.!. .N"-=u""c.., le""ar~S., ta:,.:ct1""

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Unit No.: _ _ _-=2_ __ Commercial Service Date: _ _0=3~/0~7~/~l9~7~1~- Refueling Outage No.:_~R=2=R~3~l Current Inspection Interval: IWB, IWC,IWD, IWF: Fifth Interval IWE/IWL: Second Interval Current Inspection Period:

IWB, IWC, IWD, IWF: Second Period of the Fifth Interval IWE/IWL: Third Period of the Second Interval Edition and Addenda of Section XI applicable to the Inspection plans:

ISi: 2007 Edition Thru 2008 Addenda, IWE/IWL: 2001 Edition Thru 2003 Addenda Date and Revision of Inspection Plans:

ISi: RNP-PM-008, Revision 9, 09/12/2018 IWE/IWL: RNP-PM-007, Revision 6, 11/30/2017 Edition and Addenda of Section XI applicable to Repair/Replacement activities, if different than the Inspection Plans: NI A Code Cases used: N-639, N-731, N-722-1, N-716-1, N-729-4 N-770-2, N-586-1, N-532-5, N-600, N-648-1 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 -~R=2~R=3~1_ _ _ _ __

(Refueling Outage Number) conform to the requirements of Section XI.

Signed: {)O\v-: J G0i.f/;f' A/'...K..

Owner or Owner's Designee, Title Date:_Z----"/_l_<f /_2_o_/9'------

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 South Carolina and employed by OneCIS Insurance Company of Lynn MA 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.

Elmostafa Elkouri ~ -D ~ Commissions NB 13930 SC 264 ANIC Inspector's Signature National Board, State, Province, and Endorsements Date : _____ 0.2_)1---....4}......._~--

Form OAR-1 OWNER'S ACTIVITY REPORT Table 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Category and Evaluation Description Description Item Number Inservice Inspection Program This condition was evaluated under EC#413734: Support RC-3-2403 was found to be lacking full thread engagement on a turnbuckle by approximately 2 threads. Pursuant to ASME Section XI, Part IWF-3122.3 this condition requires specific disposition to 116/RC determine operability and potential ISi inspection scope expansion. This condition is F-A, Fl.lOC 2403, Welded documented in NCR 2234092. It was determined that support RC-3-2403 remained Spring Hanger operable for the condition described in NCR 2234092. The support was returned to its original design configuration per calculation RC-3-2403 such that it meets the requirements of civil specification CPL-HBR2-C-011. No further action is required.

Condition of the containment dome liner was reported in NCR#2235607. Blistering and L-DOME, peeling was identified in multiple areas cin the dome liner however, the primer was still E-A,El.11 Containment intact and no material wastage was identified. The coatings exempt log was updated Dome Liner under NCR 2235607 assignment 01. No further action is required.

This condition was evaluated under EC#413924: Joints in the concrete containment floor were inspected for adequate moisture barrier. Some areas inspected were identified as missing moisture barrier, lacking adhesion in the barrier, or degradation of the barrier in place as documented in AR 2235381 . With respect to joints at the crane and inner missile walls and radial construction joints:

The current configuration of the moisture barriers are largely judged to be effective, even though the field conditions are noted to differ from the approved design configuration.

The moisture barriers in place to prevent moisture intrusion to inaccessible areas of the floor liner are in need of repair. However, given the field observations, construction L-MB and L-details, and knowledge of corrosion potential, it is determined that the functionality of the MB Sump, floor liner panels are not challenged by corrosion due to degradation of the moisture E-A, El.30 Containment barriers. Dry field conditions and the performance of the seals over several years without Moisture repairs indicate continued function between now and the next refueling outage. Repairs Barrier to the moisture barrier are to be implemented during RO32 to ensure continued function.

With respect to joints in the cavity keyway:

The joints within the reactor sump keyway are consistent with that shown on design drawings. No material moisture barrier consistent with definition of moisture barriers in ASME Section XI are applied. Degraded conditions noted are in relation to the concrete finish coat, which is managed under the degraded coatings log. CR 2241647 has been initiated to assess, manage, and correct deficient coatings as deemed necessary. No other actions are required and functionality of the floor liner panels are not challenged by moisture intrusion at the keyway sump.

Form OAR-1 OWNER'S ACTIVITY REPORT Examination Item Category and Evaluation Description Description Item Number This condition was evaluated under EC#413889: Debris from components above the Reactor Pressure Vessel (RPV) Head has obstructed 5 Nozzle Penetrations during the bare-metal visual examination of the RNP RPV Head per ASME Code Case N-729-4.

Multiple attempts to remove the debris have been made, however penetrations 23, 28, 64, 65, and 66 still have debris in the crevice area obstructing approximately 10 to 15% of the circumference of the penetration. Chemical analysis of the debris showed negative for boric acid, however the 10 to 15% obstruction of the circumference of the penetration could potentially mask a relevant condition. The crevice area being obstructed from view RPVHead on penetrations 23, 28, 64, 65, and 66 is not expected to be masking evidence of an Penetrations Augmented adverse condition, particularly that of corrosion due to boric acid leakage. Chemical lOlC/64, 65, analysis of the debris has not only confirmed the absence of boric acid, but it has also 66, 23, and 28 helped validate the source of the debris to be a degraded silicone coating on components above the nozzle penetrations as noted in previous chemical analysis of debris in the RPV Head nozzle penetration crevices performed during past outages at RNP. All previous bare metal visual examinations of the RNP RPV Head have been satisfactory with no relevant conditions nor indications of boric acid leakage. There has been no known leakage as a result of PWSCC on any Alloy 690 RPV Head in the industry to date. Based on the completion of this exam as well as the examination coverage of 99.995% achieved, the ASME Code requirements for examination coverage have been satisfied.

Pressure Test Program NONE TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Date Repair/Replacement Code Class Item Description Description of Work Completed Plan Number Arc strikes were removed from 1 1010/CRDM SSS the CRDM Seismic Support 10/17/18 20153937 Structure Rounded PT indications were 1 108/04DM removed from pressurizer nozzle 10/6/18 20193596 to safe end weld Weld repair performed on Class 1 109/SI-3-3135-ATI 10/22/18 20286240 1 welded attachment 10/30/18 1 RC-525 Replace RC-525 20287364 Weld Repair on V12-7 Travel 2 V12-7 10/24/18 20212353 Stop