HNP-12-091, Day Inservice Inspection Summary Report

Day Inservice Inspection Summary Report

ML12249A255
Person / Time
Site:	Harris
Issue date:	09/05/2012
From:	Corlett D Carolina Power & Light Co, Duke Energy Corp
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
HNP-12-091
Download: ML12249A255 (7)

Text

~ Duke David H. Corlett Supervisor, Licensing/Regulatory Programs

{#Energy Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 919-362-3137 10 CFR 50.55a September 5, 2012 Serial: HNP-12-091 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400

Subject:

90-Day Inservice Inspection Summary Report Ladies and Gentlemen:

In accordance with 10 CFR 50.55a, Carolina Power & Light Company submits the attached Inservice Inspection Summary Report for the Harris Nuclear Plant. This report has been prepared in accordance with Section XI ofthe American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 2001 Edition with addenda through 2003 as amended by ASME Code Case N-532-4,Section XI, Division 1. This report is for Harris Nuclear Plant's Cycle 17 Operations and Refueling Outage 17 of the third 10-year Inservice Inspection interval.

This document contains no regulatory commitments.

Please refer any questions regarding this submittal to me at (919) 362-3137.

Sincerely, Enclosure cc: Mr. J.D. Austin, NRC Sr. Resident Inspector, HNP Ms. A. T. Billoch Colon, NRC Project Manager, HNP Mr. J. M. Given, Jr., NC Department of Labor, Boiler Safety Bureau Mr. V. M. McCree, NRC Regional Administrator, Region II

Carolina Power & Light Company Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 HNP-12-091 Enclosure Inservice Inspection Summary Report for Refueling Outage 17 (5 pages plus cover)

Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 Date of Commercial Service: May 2, 1987 Contents Summary 1 Form OAR-1 Owners Activity Report 2 Table 1 3 Table 2 4

Summary The Shearon Harris Nuclear Power Plant, Unit 1, Third Ten Year Inservice Inspection (ISI) Plan complies with 10CFR50.55a (g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2001 Edition with 2003 Addenda.

This summary report is being submitted pursuant to the reporting requirements of ASME Section XI as amended by ASME Code Case N-532-4 Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission Section XI, Division 1.

Contained within this summary report are the form OAR-1 (Owners Activity Report) and Tables 1 and 2 of Code Case N-532-4 for Harris Nuclear Plant during cycle 17 and Refueling Outage 17 (RFO-17). RFO-17 is the second outage of the second period in the third inspection interval and includes the Repair/Replacement activities from February 4, 2011 through August 28, 2012.

During inspection of the Reactor Pressure Vessel Head (RPVH) Control Rod Drive Mechanism (CRDM) nozzle penetrations, flaws were discovered in four nozzles and were subsequently repaired. Refer to Table 1 of this report for a list of items with flaws or relevant conditions that required evaluation for continued service. Refer to Table 2 of this report for an abstract of repair/replacement activities required for continued service.

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CASES OF ASME BOILER AN D PRESSURE VESSEL CODE FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: _ _ _,_H!!.N,_,P_-~12.,_-_,.0""9"""1___,Pia nt: _ _:.H,.a:..:.r:...:.ris"-'-"N"""u"'cl"'"ea'"r'-'P'-'I,._an'""t...._. .=:5::;.4""13"-"'Sh,.e..,a..,_ro""n"'-'-'H"'-a!.!rr,.is._.R,.o.,a,.d.._.._,_N.,e'-'w"---'-'H!!.il ,._,....,

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Unit No.: _1_ Commercial Service Date: _ 2'""',1

_,M-"-'-"-ay~ =..9..8~,~;7__ Refueling Outage No.: __,R..l.!F. . :.0<!.:-. =1.!. . 7_ _ _ _ _ _ _ _ __

Current Inspection Interval: _ _.....:T""h""ir-==d....:.l'""nt,e"-rv""a:..:.l_ _ _ __ current Inspection Period: -----"-S""ec,o""'n"'d'-'P....:.e"'r"'io,.d'--- - -- -

Edition and Addenda of Section XI Applicable to the Inspection Plans: _ ____,.2,._00""1""-"'Ed"'i""'ti""o""-n--"w'-'i,_ th'-'2"'0..,0"'3'--'A"'d..,d,.e.,n~d,._a_ _ _ _ __

Date and Revision of Inspection Plans: _ ___NC!,o""v"'e""m""b~e..,r_,8....._,2""0~11""/"-R""e'"'" v"'-is,_,io,_,n'-'O'-----------------

Edition and Addenda of Section XI Applicable to Repair/Replacement Activities, if Different t han the Inspection Plans : ~

Code Cases Used: N-460. N-532-4. N-533-1, N-685, N-686. N-722-1. N-729-1. N-770-1 Certificate of Conformance lSI Inspections 1certify that (a) the statements made in this report are correct; and (b) the examinations and tests meet the Inspection Plan as required by he ASME Code,Section XI; and the completion of RF0-17 conform to the requirements of Section XI.

Date 8 Jgg/zo JZ.

Certificate of Conformance lSI Repair/ Replacement 1 certify that (a) the statements made in this report are correct; and (b) the repair/replacement activities and evaluations supporting the completion of RF0-17 conform to the requirements of Section XI.

SignedL~ Wayne Holley, Repair/Replacement PM Certificate of lnservice 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 HSBCT of Hartford, CT 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.

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Table 1 Items with Flaws or Relevant Conditions That Required Evaluation For Continued Service Examination Category and Item Description Evaluation Description Item Number A volumetric exam was RPVH CRDM Nozzle 5 performed resulting in the Augment E-3 (II-RV-001CRD-05) detection of 1 PWSCC flaw. The nozzle was repaired.

A volumetric exam was RPVH CRDM Nozzle 17 performed resulting in the Augment E-3 (II-RV-001CRD-17) detection of 3 PWSCC flaws. The nozzle was repaired.

A volumetric exam was RPVH CRDM Nozzle 38 performed resulting in the Augment E-3 (II-RV-001CRD-38) detection of 2 PWSCC flaws. The nozzle was repaired.

A volumetric exam was RPVH CRDM Nozzle 63 performed resulting in the Augment E-3 (II-RV-001CRD-63) detection of 2 PWSCC flaws. The nozzle was repaired.

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Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Item Description of Date Repair/Replacement Class Description/Component ID Work Completed Plan Number Replace valve due to Class 2 1CS-748 4/19/2011 WO 1461983-03 leakby Replace valve disc Class 2 1CS-207 4/19/2011 WO 1834256-01 due to leakby 1RC-E001 Reactor Vessel CRDM Inside Head, CRDM Housing, Partial Diameter Temper Class 1 Penetration Weld in Bead Weld Repair of 5/25/12 WO 1091074 -11 accordance with Code Case N- Nozzle 5 729-1, Nozzle 5 (Ref. RR I3R-09) 1RC-E001 Reactor Vessel CRDM Inside Head, CRDM Housing, Partial Diameter Temper Class 1 Penetration Weld in Bead Weld Repair of 5/25/12 WO 1091074 -11 accordance with Code Case N- Nozzle 17 729-1, Nozzle 17 (Ref. RR I3R-09) 1RC-E001 Reactor Vessel CRDM Inside Head, CRDM Housing, Partial Diameter Temper Class 1 Penetration Weld in Bead Weld Repair of 5/25/12 WO 1091074 -11 accordance with Code Case N- Nozzle 38 729-1, Nozzle 38 (Ref. RR I3R-09) 1RC-E001 Reactor Vessel CRDM Inside Head, CRDM Housing, Partial Diameter Temper Class 1 Penetration Weld in Bead Weld Repair of 5/25/12 WO 1091074 -11 accordance with Code Case N- Nozzle 63 729-1, Nozzle 63 (Ref. RR I3R-09)

Replace disk to Class 2 1CS-750 5/28/2012 WO 1841770-01 repair seat leak Replace leaking relief Class 2 1MS-51 7/17/2012 WO 01893435-01 valve and inlet nuts Replace valve plug Class 2 1CS-227 7/17/2012 WO 02007787-01 due to poor seating Replace bonnet Class 2 1MS-82 7/23/2012 WO 2074702-09 studs and nuts Replace bonnet Class 2 1MS-80 7/23/2012 WO 02077265-06 studs and nuts Replace bonnet nuts Class 2 1MS-84 7/23/2012 WO 01832703-11 and studs Repair threads on Class 1 1RC-E001 7/24/2012 WO 2077023-01 reactor vessel stud Replace valve due to Class 2 1CT-68 7/30/2012 WO 0676149-13 leakby 4

Code Item Description of Date Repair/Replacement Class Description/Component ID Work Completed Plan Number Replace valve due to LLRT leakage; replace Class 2 1FP-349 pipe from valve to 7/30/2012 WO 1857906-01 penetration due to corrosion Replace valve due to Class 2 1CS-748 7/30/2012 WO 01986798-05 seat damage Replace valve due to Class 2 1MS-230 7/30/2012 WO 01852124-08 seat leakage Replace valve due to Class 2 1MS-229 7/30/2012 WO 01852124-07 seat leakage Replace valve due to Class 2 1CT-81 7/30/2012 WO 676150-11 leakage Replace leaking AH-3 Class 2 1CV-E004 7/31/2012 WO 01888117-01 cooling coil Replace check valve Class 2 1CS-344 7/31/2012 WO 1876405-01 due to LLRT failure Replace Main Flange Class 2 1RH-HXA 7/31/2012 WO 02040559-01 Bolting Replace disc/stem Class 2 1MS-60 8/1/2012 WO 858184-01 assembly 5